bibliography, subject index, and author index of the literature ...

Contract No. W-7405-eng-26

Engineering Physics Division

O R M L / R S I C — 5 / V 7

DE84 001557

BIBLIOGRAPHY, SUBJECT INDEX, AND AUTHOR INDEX OF THE LITERATURE EXAMINED BY THE V/

RADIATION SHIELDING INFORMATION CENTER

(P Jactor and Weapons Radiation Shielding)

" // Vol. 7 1

O ° u

Literature selected, reviewed, and categorized by: D. K. Trubey, R. W. Roussin, and A. B. Gustin

Date published: August 1983

O

NOTE:

This work partially supported by DEFENSE NUCLEAR AGENCY

under Subtask No. NA010-08 " and

U. S. NUCLEAR REGULATORY COMMISSION 0

Prepared by the OAK RIDGE NATIONAL LABORATORY

Oak Ridge, Tennessee 37830

operated by UNION CARBIDE COPORATION - for the

DEPARTMENT OF ENERGY

DISTRIBUTION OF THIS DOCUMENT IS UNLIMITED

NOTICE ' o

(

/.This is, ORNL/RSIC-5 (Vol.VII) (1982) ' including accession numbers

6201-10156 "

ORNL/RSIC-5 (REV. 1) (1966) includes accession numbers

0-1135 and which may be assumed to be

ORNL/RSIC-5 (VOL. 1, REV. 1) U

ORNL/RSIC-5 (VOL: II) (1968) includes accession numbers

1136-1700

o ORNL/RSIC-5 (VOL. Il l) (1971)

includes accession numbers 1701-2300

ORNL/RSIC-5 (VOL. IV) (1974) includes accession numbers

2301-3500

ORNL/RSIC-5 (VOL. V) (1978) includes accession numbers

- 3501-4950

^ ORNL/RSIC-5 (VOL. VI) (1980) ^ includes accession numbers

" 4951-6200

TABLE OF CONTENTS

PAGE u

Abstract , ' ' ( . . . . v j.

Acknowledgment ' '.' vii Cs

Description and Use of Bibliography ix • <i ,,

Subject Categories xiii

Bibliography by Subject Categories xxix •fl „ v

Author Index 'i 425 '

DISCLAIMER

This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their , employees, makes any warranty, express or implied, or assumes any legal liability or responsi-bility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Refer-ence herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recom-mendation, or favoring by the United States Government or any agency thereof. The" views and\|opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. °

Hi/11?

0 u

ABSTRACT «

An indexed bibliography of open literature selected by the Radiation Shielding Information Center since the previous volume was published in 1980 is presented in the area of radiation transport and shielding against radiation from nucleai' reactors (fission and fusion), x-ray machines, radioisotopes, nuclear weapons (including fallout), and low energy accelerators (e.g., neutron generators). The bibliography was typeset from computer files constituting the RSIC Storage and'Retrieval Information System. In addition to lists of literature titles by subject categories (accessions 6201 -j 10156), an author index is given. , J

Most of the literature selected for Vol. Vll^vas^ublished in the years 1977-1981.

ACKNOWLEDGMENTS f,> <!'•• , , .... Vi (?

n ,',; " f, W y, // I. "J, ' , 4- ••<<' '-li' -We are pleased to acknowledge the work of;,Ruth Slushei-'and Brooks McNeely of the Union

Carbide Corporation Nuclear Division; Computer Sciences/X>ivision who managed the .data process-ing required to print this bibliography. The required data vylire selected from the RSIC data base and formatted for the ORNL APS n5 phototypesetter. T f t '

'- •The RSIC Storage and RetrievalInformation System'(SARIS) is now maintained as an , i y > C; ' " ADSEP data baseband is, available for'on-line searching, by,, the U.S. Department of Energy RECON System. Ann Gustin of~the RSIC staff manages, the literature acquisition and cataloging,

°and prepares the data for updating, the SARIS files. •• « e

The several compilers of the bibliography are pleased to acknowledge the support of the entire RSIC staff. „ ' • " "

And finally, we wish to express appreciation to the many, research scientists and engineer? who call our attention to their published work by placing RSIC on direct distribution. It is thiskind of ' cooperation that makes the information center a more useful service to the shielding,community.

DESCRIPTION AND USE OF BIBLIOGRAPHY

This bibliography is the tenth edit of the literature concerned with nuclear reactors, „

3 nuclear weapons, and radioisotopes which has been selected by the Radiation Shielding Infor-mation,, Center. The review of ,space and accelerator shielding literature^ (generally involving charged particles at >medium and high energies) ended in the early 1970s, but it has been resumed on a very limited scale although the work is not supported financially. The last volume published was \ ORNL/ RSIC-11 (Rev. 2) in 1970.

Other RSIC publications of interest are the monthly RSIC Newsletter, abstracts of com-"^-^ putervcode packages assembled by the Radia-tion Shielding Information Center (radiation transport codes in ORIsTL/RSIC-13; other codes such as cross-section processing in ORNL/RSIC-31), and Abstracts of„ the data library packages assembled'by the3 Radiation Shielding Information Center (ORNL/ RSIC-30). An infqrmaL publication, A Cap-sule Review of the Computer Code Collection (CCC), Peripheral Shielding Routines (PSR), and Data Library Collection (DLC) Packaged by the Radiation Shielding Information

" Center, provid-'^a current summary of com-puting technology available from RSIC. i>

The ^present bibliography, produced from " the files of the RSIC Storage and Retrieval

Information System (SARIS), lists literature ^collected since the previous publication was

issued. This 'literature, mainly published in 1977-81, has been assigned RSIC accession / j

numbers 6201-10156. Vol. I (Rev. l)-Vol.,VI contain accessions 0-1135, 1136-1700, 1701-

£.2300, 2301-3500, 3501-4950, and 4951-6200, respectively. In contrast to volumes I-IV, the current author index in this issue covers only the present volume, accessions 6201-10156.

Starting with accession number 6201, the number is assigned at the time the title" is pro- , cessed for the newsletter announcement. It may be some time before some particular ciia-tions are indexed, and therefore at any given" time a list of the indexed entries will have gaps. Consequently, many accession numbers less than 10156 are omitted in this edition, but most of them will appear in future editions.

* The (.work related to weapons radiation transport and) shielding is funded by the Defense Nuclear Agency.

The present volume wss produced by a sequence of computer processing steps which selected the data, organized it by category number orc,author, introduced typesetting com-mands, and finally produced a file for input to the typesetter.

As in previous editions, the two major sec-tions in this bibliography are a list of docu-ments by subject category and an author index. The document list covers nine major subjects broken down by categories. A given „, document is listed under each category with; which i t \has been identified. The Author Indjx includes^ cross references to the categories under which the author's publica-tions' appear.S\Precilding the-bibliography is 'a list, of subject categories, their corresponding category numbers, and the pages on which th jy appear in the bibliography.

YPlease note that alphameric categories pre-cedc E similar fully numeric category, e.g., 11|2A0^) precedes 112110, and 32A000 pre-cedes 331000. a?

For sone categories there arc no accessions for the time' period covered by' this bibliogra-phy. In these" cases, all references to those categories are omitted from the bibliography printout. However^lhe categories are listed in the index to denote that they are valid for use in machine searches and for future literature review by the ..Center. The Author Index, includes only authors in this volume, aids the reader in quickly finding accessions associated with a particular subject category, citing the category in the First field followed by" relevant accessions for that individual author.

Examples of entries in the subject category and author index sections, are shown in Figs. 1 and 2, « respectively. "The,, ACCESSION NUMBER assigned t.o this particular docu-ment is given on the first^line together with the PUBLICATION °DATE. The second line in the example shown in Fig. 1 lists all the SUBJECT CATEGORIES relating'to a publi-cation and is included for purposes of cross referencing and performing hand searching. Next follows the TITLE and AUTHOR list.

" The line identified in Fig. 1 as CITATION, lists the installation designation of the docu-ment and its number, if it is a laboratory report. As many as three citations may .be listed, the primary citation being listed first.

In nearly all cases laboratory reports have been published under the auspices of a government-sponsored agency, and the installa-tion ^document designation will be familiar to most librarians. Journal articles will be identi-

/ /

fied as to volume, issue, and page numbers. Individual articles in books, symposium

' proceedings, etc., will be identified by author, ;f title, and chapter and/or page number, and •' the compilation in which the article appears

will also be adequately identified. Finally, a corporate code for the originat-

ing institution is given. This code, 6 charac-ters or less, is used for machine searching. In the case of U-S. universities, the code identifies the state in which the university is located. In the case of foreign institutions, the code identi-fies the nation. A list of the codes used is

available from RSIC upon request.. An exam-ple of an entry in the Author Index is shown in Fig. 2. Here.(each entry lists an author, subject, categories, and the accession number of each of the author's documents for each subject category. u

Most reports ; of\V government-funded research are available , from the National Technical Information Service (NTIS), U.S. Department of Commerce, Springfield, Vir-ginia 22161.' Telephone: (703) 557-4650. Some reports are available from the Superin-tendent of Documents, U.S. Government Print-

0 ing Office, Washington, DC 20402. Where the prices are kiiowri'l they have been listed under AVAILABILITY. NTIS has initiated a sliding price schedule . which is coded and is given wheri; known.JI Cy «

0

if

TITLES-

AUTHORS •

ACCESSION NO. PUBLICATION DATE

0

AVAILABILITY-

3723 Date 73C*900 111210 122310 329000 511110 795192'870007 j u

•Sensitivity of the Transport of 14-Mev Neutror.s-'to the Shape of the Nitrogen Elastic Angular Distribution

•Beverly, W. B. BRL-R-1666 >J—,

• AVAILABILITY-NTIS Ballistic Research Lab. -

SUBJECT CATEGORY

NUMBERS

CITATION

CORPORATE AUTHOR.,

<i> Fig. 1. Example of literature citation.

'O •> c 0

AUTHOR'S NAME. SUBJECT CATEGORY

,NUMBERS

Badyayev, V.V. 42;i|50 712, 5 l i l 2 0 712, 861000 712, 870013 712, 870022 712

\ Cr

ACCESSION NUMBERS

Fig. 2. Example of author index entry.

si o

0

SUBJECT CATEGORIES

000000 General Radiation Shielding References . 1 " 010000 Review Articles . . . '.' 2

020000 Standards and Benchmark Problems '." 25 ^ 111110 Sources - Neutron - Fission or^Reactor-Prompt >• 7 . . . 35

•Kl 11120 Sources - Neutron - Fission - Delayed ^ 37 t U \ 30 Sources - Neutron - Fission - Weapon 37 111-210 Sources - Neutron - Reaction - 14 MeV & D,T Fusion : 37 111'220 Sources - Neutron - Reaction - Spectral 42 111 300 Sources - Neutron - Activation p. 111 400 Sources - Neutron - Thermonuclear Weapon Q ' 111500 Sources - Neutron - Discrete Energies (calculation) . X? Il l 600 Sources - Neutron - Reaction - Photoneutron (in shield) 46 111700 Sources - Neutron - Mixed Oxide Fuels and Spent Fuel 46 112A00Sources - Gamma-Ray - Secondary Radiation from Weapons <>.... 112BOO Sources - Gamma-Ray - Discrete Energies (Calculation) 46 112110 Sources - Gamma-Ray - Fission - Prompt . '•'• • • ^ 112120 Sources - Gamma-Ray - Fission-Product-Decay (includingfields) 47 112130 Sources - Gamma-Ray - Fission - Weapon (initial) . . . / / , ,, 112200 Sources - Gamma-Ray - Bremsstrahlung < '• 53 112300 Sources - Gamma-Ray - Annihilation 112400 Sources - Gamma-Ray - Neutron-Inelastic-Scattering '». • , 53

o 112500 Sources - Gamma-Ray - Neutron-Capture 54 112600 Sources - Gamma-Ray - Neutron-Reaction-Product (n.x?) Charged Particles " 55 112710 Sources - Gamma-Ray - Radionuclide-Decay - general Surveys 55 112720 Sources - Gamma-Ray - Radionuclide-Decay - ^Co 57 112730 Sources - Gamma-Ray - Radionuclide-Decay - ^ Cs 0 57 112740 Sources - Gamma-Ray - Radionuclide-Decay - Au 112750 Sources - Gamma-Ray - Radionuclide-Decay - Na' 112760 Sources - Gamma-Ray - Radionuclide-Decay - Other (includes corrosion products) J. 57 112770 Sources - Gamma-Ray - Radionuclide-Decay - N 59 112800 Sources - Gamma-Ray - Thermonuclear Weapons . .o Jjf 112910 Sources - Gamma-Ray - Fallout from Weapons 59 112920 Sources - Gamma-Ray - Simulated Fallout from Weapons 59 112930 Sources - Gamma-Ray - Reactor Accident (airborne, fallouVor plume sources) 112940 Sources - Gamma-Ray - Mixed Oxide Fuels and Spent Fuel .a 62 113100 Sources - X-Ray v 63 114000 Low Background Radioactivity ' " 63 121100 Interactions of Radiation with Matter - Collision Processes - Neutron 63 121200 Interactions of Radiation with Matter - Collision Processes - Gamma-Ray and X-Ray 68 121300 Interactions of Radiation with Matter - Collision Processes - Neutral Atom (in plasma) <. 122100 Interactions of Radiation with Matter - Cross Section Evaluation or Compilation - Neutron ....'..<->..... 70

' 122110 Interactions of Radiation with Matter - Energy Group Cross-Sections - Neutron !' 80 122115 Interactions of Radiation with Matter - Energy Group Cross-Sections - Neutral Atom (in plasma) 122200 Interactions of Radiation with Matter - Cross Section Evaluation or

" Compilation - Gamma-Ray and X-Ray 85-122210 Interactions of Radiation with Matter - Enc.rgy Group Cross-Sections - Gamma-Ray . . . ,.." 88 122310 Cross-Section Evaluation by Integral Experiment, Sensitivity Study, or

Calculational^Analysis - Neutron . Q 89 122330 Cross-Section Evaluation by Integral Experiment - Gamma-Ray - Primary 122350 Cross-Section Evaluation by Integral Experiment - Gamma-Ray - Secondary 122370 Cross-Section'Evaluation by Integral Experiment - X-Ray 123000 Nuclear Structure and Parameters P 97

210000 Radiation Damage 99 220000 Biological Effects and Health Physics .£> ^ I l l

, 221000 Beta-Ray Dose . . . .T . r. & . . . . ? , ; J.. 123 222000 Environmental1 Dose c- -- 1 2 3

223000 Occupational Exposure 127 230000 Radioactive Waste Management 1 3 1

sD xiii , a

310000 General Treatment of Transport Theory 134 311000 Method of Solution - Adjoint (includes channel theory) 136 312000 Method of Solution - Perturbation Theory and Sensitivity a , 137 32A000 Method of Solution - Carlson S and Discrete-Ordinates 142 32AI00 Method of Solution - Carlson S"and Discrete-Ordinates - Plasma Applications 146 32B000 Method of Solution - Variational .V 147 32C000 Method of Solution - Finite Element 147 32D000 Method of Solution - Response-Matrix or Transfer Matrix 148 32E000 Method of Solution - Invariant-Imbedding „ 32F000 Method of Solution - Spinney (Removal-Diffusion) " 148 321000 Method of Solution-One-Velocity ' • 148 322000 Method of Solution - Straight-Ahead-Approximation " 149 323000 Method of Solution - Asymptotic ." 149 324000 Method of Solution - Fermi-Age .' 149 , 325000 Method or Solution - Multigroup-Diffusion : .v 150 326000 Method of Solution - Spherical-Harmonics and Polynomial Expansions . . . . . ^ ^ 152 327000 fMethod of Solution-.iMoments 153 328000 Method of Solution - Successive Scattering (includes single scattering) 153 329000 Method of Solution - Monte Carlo V .< 153 329100 Method of Solution - Monte Carlo - Plasma Applications • 330000 Method of Solution - Integral Boltzmann Equation 164

<> o 410000 Description of Facilities ° 165 420000 Instruments - General Descriptions - • • • it • • • 1 6 9

421000 Instruments - Collimators ° 6 .„ , »..!>.'. | . . . . 170 421110 Instruments - Energy Spectra - Neutron - ^LKn.a) Reaction v. • • • 171 421120 Instruments - Energy Spectra - Neutron - He(n,p) Reaction 171/ 421130 Instruments - Energy Spectra - Neutron - Proton-Recoil Process (including scintillation) 172 421140 Instruments - Energy Spectra - Neutron - Threshold and Resonance Reactions 174 421150 Instruments - Energy Spectra -^Neutron - Other Means a 181 421160 Instruments - Energy Spectra - Neutron - Time of Flight 182 421200 Instruments - Energy Spectra - Gamma-Ray 1 8 2

421300 Instruments - Energy Spectra - X=Ray ^ J ^ 1 ' ' ' 422110 Instruments - Flux - Neutron - Activation Techniques ,184 422120 Instruments - Flux - Neutron - B(n,a) Reaction 186 422130 Instruments - Flux - Neutron - Fission Process 186 422140 Instruments - Flux - Neutron - Moderation . " . . . . . . .» . . . 187 422150 Instruments - Flux - Neutron - Nuclear Track Detector 187, 422200 Instruments - Flux - Gamma-Ray 187 422300 Instruments - Flux - X-Ray "• (1 423110 Instruments - Dose Rate - Neutron - Ion Chamber v 187 423120 Instruments - Dose Rate - Neutron - Proportional Counter V « 188 423130 Instruments - Dose Rate - Neutron - Scintillation Counter '. '. . 188

' 423135 Instruments - Dose Rate--, Neutron - Thermoluminescencse (TLD) . .? . ^ • • 188 o 423140 Instruments - Dose Rate - Neutron - Other 189

423210 Instruments - Dose Rate - Gamma-Ray - Ion Chamber, • •. 189 423220 Instruments - Dose Rate - Gamma-Ray - Proportional Counter v

423230 Instruments - Dose Rate - Gamma-Ray - Scintillation Counter ' v ? 190 423240 Instruments - Dose Rate - Gamma-Ray - Other . . £.90

„ 423250 Instruments - Dose Rate - Gamma-Ray - Thermoluminescence (TLD) ¥. 191 423300 Instruments - Dose Rate - X-Ray 193 424000 Density, Water Content, Non-Destructive Testing - Radiation Methods . . . ? 193 425000 Aerial Surveying Techniques O-430000 Analysis - Energy Spectra Unfolding and Detector.Response 194

510000 Time Dependent Results ; ! . . f . . . 205 511110 One Dimension;- Neutron - Primary - Calculation ^ 205 511120 One Dimension - Neutron - Primary - Experiment 209 511200 One Dimension - Neutron - Secondary . . .Q !' 512 f 10 One Dimensior - Gamma-Ray - Primary - Calculation u • 214 '512120 One Dimension - Gamma-Ray - Primary - Experiment - 216

: U ,, . ' " -- . XIV , . . -

• \

512210 One Dimension - Gamma-Ray - Secondary - Calculation 216 512220 One Dimension - Gamma-Ray - Secondary - Experiment 217 5131 i 0 One Dimension - X-Ray - Primary - Calculation v. ' f ! 5 i 3120 One Dimension - X-Ray - Primary - Experiment 218 513200 One Dimension - X-Ray - Secondary and Brcmsstrahlung ». 218 514110 One Dimension - Plasma - Primary - Calculation '218 521110 Interface Effects - Albedo and Scattering - Neutron - Calculation 218 521120 Interface Effects - Air Over Ground - Neutron - Calculation 219 521130 Interface Effects - Laminar Layers'- Neutron -"Calculation « 219 521210 Interface Effects - Albedo and Scattering - Neutron - Experiment 228 521220 Interface Effects - A i r Over Ground - Neutron - Experiment 228 521230 Interface Effects - Laminar Layers - Neutron - Experiment 229 522110 Interface Effects -.Albedo and Scattering - Gamma-Ray - Calculation 230 522120 Interface Effects - Air Over Ground - Gamma-Ray - Calculation 230 522130 Interface Effects - Laminar Layers - Gamma-Ray - Calculation 231 522210 Interface Effects - Albedo and Scattering - Gamma-Ray - Experiment v 234 522220 Interface Effects - Air Over Ground - Gamma-Ray - Experiment 522230 Interface Effects - Laminar Layers - Gamma-Ray - Experiment 0 ft 235 523100 Reflection and Interface Effects - X-Ray - Calculation 523200 Reflection and Interface Effects - X-Ray - Experiment . . .

"531000 Heating - Neutron : " f . 235 532000 Heating - Gamma-Ray (includes fission products) .''. 237 533000 Heating - X-Ray « ". 540000 Neutron Thermalteation and Low-Energy Spectra H 242 551110 Two Dimensions -^Neutron - Primary - Calculation v 243 551120 Two Dimensions - Neutron - Primary - Experiment r 248 551200 Two Dimensions - Neutron - Secondary ^ 249 552110 Two Dimensions - Gamma-Ray - Primary - Calculation . . . " 250

• 552120 Two Dimensions - Gamma-Ray - Primary - Experiment 0 P.. 251 552210 Two Dimensions - Gamma-Ray - Secondary - Calculation 251 552220 Two Dimensions - Gamma-Ray - Secondary - Experiment 252 553110 Two Dimensions - X-Ray - Primary - Calculation > •' 553120 Two Dimensions -r,X-Ray - Primary - Experiment 252 553200 Two Dimensions - X-Ray - Secondary and Bremsstrahlung 554110 Two Dimensions - Plasma - Primary - Calculation 25|2

,j , eS3 610000 Formulas, Graphs, Tables, and Nomograms - n and 7 ray ~ 253 613000 Formulas, Graphs, Tables, and Nomograms - X-Ray o. 255' 620000 Shield Shaping, Placement, and Optimization " . 255 631000 Gross Models for Approximate Calculations 256 632110 Special Models for ApproximattSCalculations - Calculated Attenuation Kernels

(includes buildup factors) 4 . 256 632120 Special Models for Approximate Calculations - Semi-empirical Attenuation^Kernels

(includes buildup factors) >.> '.P. 258 , 632200 Special Models for Approximate CalCulations - Geometric Transformations or Geometry *'

Computations 258 632300 Special Models for Approximate Calculations - Special Shielding Formulas 259 632400 Special Models for Approximate Calculations - Energy Independent Removal

Cross-Sections n 632500 Analysis of Structures by Engineering Method - > '-•* a u 710000 Engineered Shields and Shielding Projects ^ \\ 259 711000 Hot Cells r r J I 711100 Fuel Reprocessing and Fabrication . V 260 712000 Shipping Casks 261 713000 Fast Reactors 262 714000 Isotope Power Sources ( ^ 715000 Nuclear Energy Rocket Vehicle Propulsion 716000 Space Nuclear Auxiliary Power 717000 iCsion Reactor Shielding (CTR Neutronics) 270 717100 Fission-Fusion Hybrid Systems * .^frTZ 291

* \ 0 ,J <£) * 1 ' , XV o 6 ~

717500 Accelerator Breeder 2 9 6

718000 Ship Propulsion 297 719A00 Light-Water Cooled Reactors ° ' 297, 719B00 Gas-Cooled Reactors )., 1' h •'<• 3(>8

719C00 Heavy-Water Cooled Reactors 1 310, 719D00 Pebble-Bed Reactors " 3 1 1

721100 Ducts, Mazes, Voids, and Streaming - Neutrons - Calculation y a,, 311 721200 Ducts, Mazes, Voids, and StreamingNeutrons - Experiment . . . . o 314 722100 Ducts, Mazes, Voids, and Streaming - Gamma-Ray - Calculation • 315 722200 Ducts, Mazes, Voids, and Streaming - Gamma-Ray - Experiment J L ; 731100 Structure Shielding - Vehicle ? „ 0 317 731200 Structure Shielding - Buildings, Bunkers, and Shelters 317 731300 Structure Shielding - Ships and Compartmented Structures 0 318' 740000 Shield Construction and Fabrication ''. . , (/ • 318 750000 Accelerator Shielding (including neutron generators) ' , 318 760000 Medical Facilities T . 19, -770000 Irradiation Facilities c, t- < 3 2 1

793000 Data Library Collection Used << 321 794000 Peripheral Shielding Routines Used ' ?. 328

810000 General Survey of Shielding Materials 333 (820000 Water .<• . . . . : . . . . 365„o

. 821000 Heavy Water ?>..... -g. . -830000 Air .. (3 '• 368 841000 Organic Material - Hydrocarbon • • • 369 842000 Organic Material ^Plastic-,, 'f . s . . . . . . . . . : 370 843000 Organic Material - Wood 7 • / 7 1 844000 Organic Material - Other u • 371 845000 Organic Material - Biological Tissue • '371 851000 .Siliceous Material - Earth and Sand ° " ».. 4 ' <: „ •. • <-374 852000 Siliceous Material - Glass „ " . . . . . ' 374 ^ 853100 Siliceous Material - Ordinary Concrete & . . . . '374 853200 Siliceous Material - Barytes Concrete t» o ."->...... 377 853300 Siliceous Material - Ferrophosphorous Concrete A . .,...,. 378 853400 Siliceous Material - Magnetite Concrete P 378'i> 853500 Siliceous Material - Ilmenite Concrete 378 853600 Siliceous ivTaterial - Limonite Concrete •„• - .-y • • l3,78 853700 Siliceous Material - Heavy-additive Concrete «. • • 379 853800 Siliceous MaterialSerpentine "Concrete . - • • • 379 853900 Siliceous Material - Special or Local Aggregate Concrete' ^379 861000 Ironrand Iron Alloys " 3 7 9

862000 Nickel and Nickel Alloys " • 387 863000 Tungsten and Tungsten Alloys . f ? r ! • 3,87 869999 Tritium -.-!'.. 0 , * '•'• • • • •"• • • •/ * 3 8 7" 870001 Hydrogen ^ . . . . ' " A'... . V 387 870002 Helium " 870003 Lithium b- " • ' . . „ 388 ' 870004 Beryllium 77..". =? U 3 8 9

870006 Carbon ° ^ :. 389 870007 Nitrogen 7 ^ • • -i>. ••••••••• S • 391 870008 Oxygen ^ .:. 392 870009 Fluorine V " 392 870011 Sodium 3 9 V 870012 Magnesium • • • • • : 394 , 870013 Aluminum .Yi. ^ : . . .-. .- 394; 870014 Silicon ....7...:.. 395 870016 Sulfr-r Ks v : . . _ . , . . . . ^ " 870017 Cfilonne . . . ' . . . . . . . ' ? ' 395 870019 Potassiums : 1 : 396 870020 Calcium *.c?. ^ « 870022 Titanium ? • • -C.' 396

, , - - ^ 3 . -

r o , -- • • , ' xvi ° ' • ' • *, . " O f> . .o -. . , . . . .

„ - • ' ,r 870023 Vanadium,, • • • •<»• •« • « 3 9 ^ 870024 Chromium ^ I 3 9 7

870025 - Manganese , ^ 870027 Cobalt - . . . 'J . <?97

870029 Copper" ' </ 3 9 ] 870036 Krypton t " 3 9 8 > 870037 Rubidium ." ; 6 e

870040, Zirconium'-' 3 9 8 , 870041 Niobium ' 3 9 8

870042 Molybdenum •' 3 9 9

870047 Silver ; 3 9 9

870049 Indium 870050 Tin 3 9 9 < 87Q054 Xenon \i 's>

870055 Cesium 870056 Barium » 1

870063 Europium £ , 870072. Hafnium 870073 Tantalum <>' 4 0 0

870079 Gold 4 0 0

870080 Mercury * 870082 Lead 400 870083 Bismuth •* " 870084 Polonium • • • 870088 Radium o 4 0 i

870090 Thorium 4 0 1

rt 870091 Protactinium 870092 Uranium 4 0 3

870093()Neptunium '' *•' 4 1 1

870094 Plutonium ... 4 1 2

870095 Americium " 4 1 1

870096 Curium . ^ * 4 1 8

870098 Californium - 4 1 8

881000 Hydrides ^ H i v , ' ' 4 2 0

882000 Boron-Containing Compounds or Mixtures . . 4 2 0

883000 Metal-Hydrogenous Mixtures ? 4 2 1

884000 Alkaline-Salt Compounds or Mixtures 885000 Metal-Oxide Compounds or Mixtures 886000 Fluorides 887000 Actinides 4 2 1

'f Author Index 4 2 ^

xvi i

BIBLIOGRAPHY BY SUBJECT CATEGORIES

General Radiation Shielding References

CATEGORY NUMBER 000000

6740. 000000 Nuclear Reactor Shielding. Chapter 5. Moteff, J.

Date 1977

BOOK, PP. 113- „ ^ AVAILABILITY-AMSTERDAM,

LANDS; ELSEVIER U - O H

"THE NETHER-

6884. Date 1977 000000 113100 THE FUNDAMENTALS OF X-RAY AND RADIUM

PHYSICS. 6th Ed. Selman, J.

"BOOK AVAILABILITY-C.C. THOMAS, SPRINGFIELD,

ILL. U-TX

6901 Date August 1977 000000 111110 312000 Use of Perturbation Theory in the Physics of Nuclear Reac-

tors. Stumbar, E.A. ERDA-TR-297 AVAILABILITY-DEP., NTIS RUSSIA

7051 Date January 1977 000000 010000 Radiation Physics. Ghose, A.M.; Gopinath, D.V.; Hubbell, J.H.; Roy, S.C. NBS SPEC. PUB. 461 AVAILABILITY-SUPT. OF DOCUMENTS, GPO,

WASHINGTON, D.C. 20402 $3.25 INDIA

o

; 7075 Date January 1977 000000 010000 Computer Codes and Data Available from the Radiation

Shielding Information Center. Trubey, D.K.; Maskewitz, B.F.; Roussin, R.W. " NBS SPEC. PUB. 461, PP. 171 -173 AVAILABILITY-SUPT. OF DOCUMENTS, GPO,

WASHINGTON, D.C. 20402 OARNL

7097 Date 1974 000000 Questions on the Physics of Reactor Shielding. Vol.6,j 11

Egorov, Yu.A.; Mashkovich, V.P.; Pankrat'yev, Yu.V.; Suvorov, Ya.P.; Tsypin, S.G.

ERDA-TR-125 AVAILABILITY-NTIS $9.25 RUSSIA

8259 Date No Date 000000 Treatise of Neutronics — Physics and Calculations of

Nuclear Reactors with Applications to Pressurized Water Reactors and Fast Neutron Reactors.

Bussac, J.; Reuss, P. BOOK (IN FRENCH) 'Q AVAILABILITY-HERMANN PUBLISHERS, 293

LECOURBE STREET, 75015 PARIS (FRANCE) FRANCE

826 l<v. Date 1977 000000 111T30 111400 112130 112800/112910 521120

522120 731200 830000 " " ''a The Effects of NuclearvWeapons , Glasstone, S.; Dolan, P.J. BOOK » ^ AVAILABILITY-U.S. DEPT. OF DEFENSE, U.S. DOE DOE &

8930 Date 1974 000000,220000 SAFE HANDLING OF RADIATION SOURCES. Oberhofer, M. -BOOK AVAILABILITY-MUNCHEN, VERLAG TH1EMIG GERMAN

9958 Date 1978 000000 Concepts of Radiation Dosimetry. ' Kase, K.R. BOOK AVAILABILITY-NEW YORK, PERGAMON PRESS,

C1978 U - M A

9959 Date 1979 000000 Radiation Shielding and Dosimetry. Profio, A.E. BOOK AVAILABILITY-JOHN WILEY AND SONS, INC.,

NEW YORK, N.Y.

1

U - C A

10040 Date 1980 000000 420000 , ' Radioactivity and Its Measurement - SI Units. 2nd Edition Mann, W.B. BOOK AVAILABILITY-NEW YORK, PERGAMON PRESS,

1980 NABS

N1JCL. SAFETY, 18(5), 596-616 OARNL

6365 Date 1977 010000 329000 Computational Methods for Data Analysis. Chambers, J.M. BOOK " ' AVAILABILITY-NEW YORK! WILEY BELL

Review Articles


6213 Date November 1975 010000 112710 112760 112930 713000 870092 870094 Radionuclide Production, Transport, and Release from Nor-

mal Operation of Liquid-Metal-Cooled Fast Breeder iRea3ors.

Erdman, C.'A.; Kelly, J.L.; Kirbiyik, M.; Reynolds, A.B. j E P A - 5 2 0 / 3 - 7 5 - 0 1 9

AVAILABILITY-DEPT. OF NUCLEAR ENGINEER-ING, VIRGINIA UNIV., CHARLOTTESVILLE, VA.

U - V A

,6309 Date June 1977 o ioooo i 12600 112710 230000 Regulation of Naturally Occurring and Accelera-

tor-Produced Radioactive Materials. A Task Force Review.

Nussbaumer, D.A.; Lubenau, J.O.; Cool, W.S.; Cunning-ham, L.J.; Mapes, J.R.; Schwartz, S.A.; Smith, D.A.

NUREG-0301 AVAILABILITY-NTIS NURC

6322 Date July 1977 010000 329000 MOCARS: A Monte Carlo Code for Determining the Dis-

tribution and Simulation Limits. Matthews, S.D. TREE-1138 AVAILABILITY-NTIS EDGERT

6343 Date Sept.-Oct. 1977 010000 112120 532000 A Review of Short - Term Fission - Product - Decay Power. Bjerke, M.A.; Holm, J.S.; Shay, M.R.; Spinrad, B.I.

6369 Date Dec. 1977 010000 " Where Are We and Where Are We Going in Reactor Shield-

ing? Maienschein, F.C. CONF-770401, PP.1-10; ATOMKERNENERGIE,

30(4), 229-233(1977) AVAILABILITY-SCIENCE PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 jj OARNL

•r5 ° v n (} 6370 Date Dec. 1977 " U 010000

The Evolution of Shielding Methods and Data A Con-tinuing Process of Adjustment to Changing Project

,„ Needs. Butler, J. CONF-770401, PP.11-21; ATOMKF.RNENERGIE,


' DR., PRINCETON, NJ 08540 ENGLAN

(j _ • 6376 Date Dec. 1977

010000 312000 A Survey of Cross-Section Sensitivity Analysis as Applied

to Radiation Shielding. Goldstein, H. CONF-770401, PP.75-90; ATOMKERNENERGIE,


DR., PRINCETON, NJ 08540 U - N Y

6380 Date Dec. 1977 010000 020000 312000 A Review of Progress in the NEA/IAEA Collaborative Pro-

gram of Sensitivity Studies and Shielding Benchmarks. Butler, J. i '< CONF-770401, PP.120-131 AVAILABILITY-SCIENCEPRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540

2

E N G L A N

6385 . . . . . Dale Dec. 1977 010000 713000 721100 Radiation Streaming The Continuing Problem of

Shield Design. Avery, A.F.S--CONF-770401, P^P.169-178; ATOMKERNENERGIE,

30(4), 261-264(1977) A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

( DR., PRINCETON, NJ 08540 E N G L A N

6399 Date; Dec. 1977 010000 223000 719A00 Radiation Exposure and Protection Problems in Nuclear

Power Plants U.S. Overview. Verna, B.J. CQNF-770401, PP.288-299; ATOMKERNENERGIE,

30(4), 282-286(1977) , A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 NUPE //

.6407 Date Dec. 1977 010000 112760 719A00 An'Overview of the Activated Corrosion Product Reduction

Program at U.S. Power Reactors. Murphy, T .D. ' CONF-770401, PP.364-373; ATOMKERNENERGIE,

30(4), 293-296(1977) ( i

A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE DR., PRINCETON, NJ 08540

NURC

6415 Date Dec. 1977 010000 223000 RSIC After 14 Years--Where Do We Go From Here? Trubey, D.K.; Maskewitz, B.F.; Roussin, R.W. CONF-770401, PP.442-447; A T O M KERN EN EN ER-

GIE, 30(4), 303-304(1977) A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 O A R N L

6422 Date Dec. 1977 010000 717000 . Important Aspects of Radiation Shielding for Fusion Reac-

tor Tokamaks. Abdou, M.A. ,, CONF-770401, PP.501-511; ATOMKERNENERGIE,

3.0(4), 308-312(1977) A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

r DR., PRINCETON, NJ 08540 A R G O N N

6427 Date Dec. 1977 . 010000 719C00 The Methods of Calculation Used in the Design of Shielding

Within the Primary Containment of a Commercial SGHWR.

Dutton, L.M.C.; Solari, P.A. CONF-770401, PP.545-553 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 ENGLAN *>•

6430 Date-Dec. 1977 010000 719B00 Application of an Advanced Shielding Analysis System to

Gas Cooled Fast Reactor Designs. Bartine, D.E.; Williams, L.R.; Slater, C.O.

' CONF-770401, PP.570-579 < A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

^DR., PRINCETON, NJ ^3540 O A R N L

I) / 6446 Date Dec. 1977

32F000 010000 The Use of Removal Diffusion Theory for Calculating the

Effectiveness of Neutron and Gamma-Ray Shields for Nuclear Reactors and Chemical Plants.

Richardson, B.L.; Burstall, R.F. CONF-770401, PP.703-710 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 E N G L A N

6416 Date Dec. 1977 020000 010000 Radiation Protection and Shielding Standards. Vallario, E.J.; Trubey, D.K. <-

1 CONF-770401, PP.448-456 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 DOE

6461 Date Dec. 1977 010000 713000 . U K Fast Reactor Shield Design and Performance. Butler, J.; Brindley, K. W. CONF-770401, PP.819-832 AVAILABI thTY-SCIENCEPRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 E N G L A N 0

0 3

6501 Date December 1977 010000 121100 810000 An Index to the Literature on Microscopic Neutron Data. I A E A C I N D A 76/77-SUPPL.3 A V A I L A B I L I T Y - I A E A , V I E N N A I A E A

6535 Date February 1978 010000 421140 430000 Contributions to Few-Channel Spectrum Unfolding. Perey, F.G. O R N L / T M - 6 2 6 7 ; E N D F - 2 5 9 A V A I L A B I L I T Y - N T I S $6.00 O A R N L

Tunnicliffe, P.R. ' CONF-770107, PP.69-84/ AVAILABILITY-NTIS ' CANADA

6602 Date 1977 010000 111220 717500 810000 Analysis of Accelerator Breeder Concepts with L M F B R , " GCFR, and Molten Sal t^Type ^Blankets. Mynatt , F.R. CONF-770107 , PP.85-T06 A V A I L A B I L I T Y - N T I S « O A R N L - u

6583 Date 1976 ,010000 111110 121100 870092 870094

v Theory of Nuclear Fission: A Review. " " Mosel .U. A N L - 7 6 - 9 0 , PP.3-30 0 „ A V A I L A B I L I T Y - N T I S G E R M A N

6607 Date February 1978 010000 111210 210000 717000 810000 Special Purpose Materials for the Fusion Reactor Environ-

ment. A Technical Assessment. Scott, J.L. (Ch.) D O E / E T - 0 0 1 5 " A V A I L A B I L I T Y - N T I S $6.50 DOE

6591 '. . Date 1976 010000 020000 122100 «' Requirements on Experiment Reporting to Meet Evaluation

Needs. ° P e e l l e , R.W.

A N L - 7 6 - 9 0 , PP.421-430 A V A I L A B I L I T Y - N T I S O A R N L u

i

6599 Date 1977 010000 111220 717500 810000 A Brief History of the M T A Project. Van Atta, C.M. CONF-770107, PP.9-29 , A V A I L A B I L I T Y - N T I S L A L L

6600 Date 1977 010000 111220 717500 810000 Linear Accelerator Breeder for Energy Security. Steinberg, M . CONF-770107 , PP.41-68 A V A I L A B I L I T Y - N T I S B R O O K H

6601 Date 1977 010000 111220 717500 810000 High Current Linear Accelerators and Nuclear Power.

a

6612 Date December 1977 111110 010000 719B00 713000 810000 Shielding and Control Materials for the Gas-Cooled Fast

Breeder Reactor. Simnad,<iM.T. ^ G A - A - 1 4 4 7 8 A V A I L A B I L I T Y - NTIS , $ 14.50 G E A C

6630 Date Apr i l 1978 010000 122100 810000 Status Report to the DOE Nuclear Data Committee. Perey, F.G.; Gentry, J.C. O R N L / T M - 6 3 3 8 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

&

6634 • Date January 16, 1978 010000 121100 Relativistic Transformations Between Cen te r -o f -Mass

and Laboratory Systems for Two-Body Nuclear Reac-tions.

Howerton, R.J. ' UCRL-50400 , VOL.5, PT.B A V A I L A B I L I T Y - N T I S L A L L

r

- 6658 , -V Date March 1977 010000 421140 430000 511120 810000 Activation Detectors for Neutron Flux and Spectrum Deter-

mination. Boot, S.J. A E R E - R - 8 6 5 4 A V A I L A B I L I T Y - H . M . S . O . PRICE POUND1.50; NT IS

(U.S. SALES O N L Y ) E N G L A N

A V A I L A B I L I T Y - N T I S S3.50 L A L L ' ;

" 6731 Date August 15, 1977 010000 111210 111220 High Energy and High Intensity Neutron Sources. Ullmaier, H. (Ed.) N U C L . , I N S T R U M . METHODS, 145(1), 1 -218 G E R M A N

O o

6661 Date February 1978 010000 111110 122100 122110 713000 810000 Energy-Averaged Neutron Cross Sections of

; Fast-Reactor Structural Materials. Smith, A.; McKnight, R.; Smith, D. a

A N L / N D M - 4 1 A V A I L ' A B I L I T Y - N T I S A R G O N N

6666 //. Date Apr i l 1978 tt

010000 112930 J / Proceedings of a Worksho^on the Evaluation of Models

Used for the Environmental Assessment of Radionuclide Releases.

HofTman, F.O. (Ch.) CONF-770901 A V A I L A B I L I T Y - N T I S S7.25 O A R N L

<- " " € • , ' >>

6668 Date October 1977 111210 111220 010000 421140 717000 Dosimetry Needs for the Magnetic Fusion Materials Pro-

gram. Heinrich, R.R.; Greenwood, L.R.; Odette, G.R.; Farrar,

H., IV; Dierckx, R.; Gold, R. C O N F - 7 7 1 0 3 6 - 6 A V A I L A B I L I T Y - D E P . , NT IS A R G O N N

6743 Date May 1977 010000 112120 , w o The Status of Fission Product Yield Data (FPND) in 1977. Cuninghame, J.G. ^ „ A E R E - R - 8 7 5 3 A V A I L A B I L I T Y - H . M . S . O . , PRICE POUND2.50 E N G L A N ,., <Al

6748. . .,. . V . . . Date March 1978 " o fj > a 010000 430000

Generalized Least-Squares for Data Analysis. Schmittroth, F. - ' " H E D L - T M E - 7 7 - 5 L v' A V A I L A B I L I T Y - N T I S H A N F O R "

6768 ;. . . Dale.October 1977 010000 111210 210000 717000.810000"' Progress in Materials Research for Fusion Reactors. Kulcinski, G.L. U W F D M - 2 2 8 , t

A V A I L A B I L I T Y - F U S I O N RESEARCH P R O G R A M , N U C L E A R E N G I N E E R I N G DEPT., U N I V E R S I T Y OF WISCONSIN , M A D I S O N , W I S C O N S I N 53706

U - W I

6679 Date 1977 010000 111110 531000 532000 713000 Overview of Gamma-Ray Energy Deposition and Spectra

in Fast Reactor Environments. Gold, R. H E D L - S A - 1 2 3 8 ; C O N F - 7 7 1 0 3 6 - 7 A V A I L A B I L I T Y - D E P . , N T I S W E E ' '

I 6704 Date February 1, 1977 ^

010000 717100 Fusion-Fission Hybr id Reactors': "A Capsule Introduction. Holdren, J.P. UCID-17397

i\ tJ*

6769 Date March 1978 010000 111210 111220 210000 717000 810000 Intense Sources of Fast Neutrons. Barschall, H.H. . U W F D M - 2 3 1 A V A I L A B I L I T Y - F U S I O N RESEARCH P R O G R A M ,

N U C L E A R E N G I N E E R I N G DEPT., U N I V E R S I T Y OF WISCONSIN , M A D I S O N , W I S C O N S I N 53706

U - W I

6773 Date Apr i l 1978 010000 111210 717100 810000 Notes on Fusion Hybrid Reactors. Conn, R.W.; Moses, G.A.; Abdel -Khal ik , S.I. U W F D M - 2 4 0

5

AVAILABILITY-FUSION RESEARCH PROGRAM, NUCLEAR ENGINEERING DEPT^ UNIVERSITY OF WISCONSIN, MADISON, WISCONSIN 53706

U-WI

6785 Date April 1, 1978 < oioopo 12Y200

Z Dependence- of Elastic Scattering 'of Gamma Rays Rechecked. „

Roy, S.C. 11 NUCL. INSTRUM. METHODS, 150(2), 283-287

INDIA •rv<k ,«,

Date June 1978 6800 " 010000 32AOOO 325000

Computational Procedures for Multidimensional Core Anal-ysis. (i '

Lathrop, K.D. „ • a> CONF-780401, PP.93-105 , , . ' ^ AVAILABILITY-NTIS ,, • 0

, LOASL "t v, " .Or

ff I V

,'J ,6808./:.,: , Date 15,78 c 010000 f i l l 10 122200(210000 421140,430000 511120

" a 10000;' , ' ' (J lrf J ... ^ j.j . -"V, a

V Neutron Cross Sections fory Reactor Dosimetry - Review c> . i'" " o ( Papers. Summary'Report. >t .tjf ,, . Vlasov, M.F. (Ed.)

p IAEA-208, VOL.I, PP.1-49 ' ' AVAILABILITY-INIS MICROFICHE CLEARING-

HOUSE" IAEA ' ^ ,

6809. . . Date 1978 010000 111110 410000 122200 511120 421140 770000

430000 Benchmark Neutron Fields for Reactor Dosimetry. Grundl, J.; Eisenhauer, C. IAEA-208, VOL.I, PP.53-104 AVAILABILITY-INIS MICROFICHE CLEARING-

HOUSE

6810.^ '.< Date 1978 010000 210000 421130 421140 511120 719A00 861000 Power Reactor Pressure Vessel Benchmarks. Rahn, F.J. j? (I IAEA-2G8!/vOL.I, PP.105-140 AVAILABILITY-INIS MICROFICHE CLEARING-

HOUSE EPRI

6811 Date 1978 010000 420000 <-- ' ,, Remarks on Terminology and Symbols for Physical Quanti-

ties in Neutron Metrology. , ,, )fiagner, S.R. IAEA-208, VOL.I, PP.141-143 ^ AVAILABILITY-INIS MICROFICHE^CLEARING-

HOUSE „ i f GERMAN

J'*)

Integral i) 0 «

?

6812 Datei978 'OlOOOO 430000 122310 795112 Spectral Characterization by Combining Neutron Spectros-

copy, Analytical Calculations, and Measurements.

McElroy, W.N.; Gold, R.; Lippincott, E.P.; Fabry, A.; Rob-erts, J.H. A, " \

IAEA-208, VOL.I, PP.147-181 AVAILABILITY-INIS MICROFICHE CLEARING-

HOUSE. Q HANFOR

6813. . . Date 1978 010000 11^110 870092 870098 A Review on Standard Fission Neutron Spectra of 235-U

and 252-Cf. ' < Knitter, H.H. IAEA-208, VOL.1, PP.183-195 AVAILABILITY-INIS MICROFICHE CLEARING-

HOUSE BELGIU

6814 Date 1978 010000 111110 421110 421120 421130 870092^ In-Pile Neutron Spectrometry: Status. De Leeuw-Gierts, G.; De Leeuw, S. IAEA-208, VOL.1, PP.197-230 f AVAILABILITY-INIS MICROFICHE CLEARING-

HOUSE BELGIU

6815 Date 1978 010000 111110 122310 5,11120 810000 870092 870098 Review of Microscopic Integral Cross Section Data in Fun-

damental Reactor Dosimetry Benchmark Neutron Fields.

Fabry, A.; McElroy, W.N.; Kellogg, L.S.; Lippincott, E.P.; Grundl, J.A.; Gilliam, D.M.; Hansen, G.E.

IAEA-208, VOL.I, PP.233-263 AVAILABILITY-INIS MICROFICHE CLEARING-

HOUSE HANFOR ^

> 6817 Date 1978 010000 112120 713000 Status of Fission Product Yields Required for Fast Reactor

Dosimetry. Lammer, G.; Lammer, M . I A E A - 2 0 8 , VOL.1, PP.301-318 A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE B E L G I U

6818 s\. . r»T . . Date 1978 010000.122310 210000 421140 „ J ) Remarks Concerning the Accurate Measurement of(Differ-

/ en t i a l Cross Sections for Threshold Reactions Used in il Fast-Neutron Dosimetry for Fission Reactors.

Smith, D.L. - i', I A E A - 2 0 8 , VOLT, 321 -351 A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE A R G O N N E

6819 Date 1978 010000 122100 421140 Comments on Excitation Functions of Threshold Reactions

Used in Reactor Neutron Dosimetry. Vlasov, M. I A E A - 2 0 8 , VOL. I , PP.353-360 A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE A U S T R I

6820 Date 1978 010000 111210 421140 Status of Some Activation Cross Sections for Reactor Neu-

tron Dosimetry in the Range 13-15 MeV. Vonach, H. I A E A - 2 0 8 , VOL. I , PP.361-373 A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE A U S T R I

6824 Date 1978 f )

010000 111110 421140 430000 810000 Foil Activation Detectors - Some Remarks on the Choice

of Detectors, the Adjustment of Cross-Sections and the Unfolding of Flux Spectra.

McCracken, A.K.; Packwood, A. I A E A - 2 0 8 , VOLT , PP.431-442 A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE E N G L A N

K\ 682 6 Date 1978

010000 540000 „ Standards for Thermal Neutrons at the PTB. " Wagner, S.R. I A E A - 2 0 8 , VOL.11, PP.3-14 A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE G E R M A N , " ^

\\

IW'p 682 7 ". Date 1978

010000 020000 111-110 111220 410000 • t, o Fast Neutron Standards at the PTB. Wagner, S.R. j p I A E A - 2 0 8 , VOL.11, PP. 15-^7 9 A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE,, fJi

GERMAN

6842 Date 1978 010000 020000 111110 421140 51,1120 Measurement and Evaluation of Threshold Reaction Cross

Sections in Standard Neutron Fields; Kimura, I.; Kobayashi, K.; Hayashi, Shu A.; Yamamoto, S.;

Gotoh, H.'; Yagi, H. I A E A - 2 0 8 , VOL.11, PP.265-290 A C V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE J A P A N

!' 1) , 6849 Date 1978

010000 111110 210000 421140 Cross-Section Requirements for Reactor Neutron Flux

Measurements from the User's Point of View. Mas, M.; Lloret, R. I A E A - 2 8 , VOL.11, PP.387-394 ( I N F R E N C H ) A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE F R A N C E

6851 Date May 1978 010000 122200 810000 Compilations and Evaluations of Data on the Interaction of

Electromagnetic Radiationrwith Matter. Lorenz, A. (Comp.) (Q INDC(NDS) - 9 4 / L N A V A l L A B I LITJY - I A E A N U C L E A R D A T A SECTION,

K A R N T N E R R I N G 11, A - 1 0 1 0 V I E N N A I A E A

6889 Date June 1978 010000 1221jD0 810000 A n Index to the Literature on Microscopic Neutron Data. I A E A

C I N D A ,78 - SUPPL.4 TO C INDA 76/77 A V A I L A B I L I T Y ' - I A E A , AUSTRIA IAEA

6890. . . , c) Date November 1977 010000 112120 532000 610000 713000 The Distribution of Fission Product Decay Heat. 11

Turland,,B.D.; Peckover, R.S. C L M - P - 5 1 0 A V A I L A B I L I T Y - U K A E A RESEARCH ,GROUP,

C U L H A M LABORATORY, ABINGTON, OXFORDSHIRE, E N G L A N D

E N G L A N ,

6957. . . . . . . > Date 1977 010000 220000 Sources and Effects of Ionizing Radiation: UNSCEAR 1977

Report. ., -United Nations Scientific Committee on the Effects of

Atomic Radiation U N PUB. SALES NO.Ei77. IX-1 AVA ILAB IL ITY -^UNITED NATIONS, SALES SEC-

T ION, NEW YORK OR GENEVA $28.00 IAEA" <• „

7014.° Date September 1976 010000 111210r717000 810000 Technology Problems in Theta Pinch Reactors. ThomassCj, K.I. • 1

CONF-760935-P2, PP. 591^-599 A V A I L A B I L I T Y - N T I S LOASL—- "

7016 Date September 1976 010000 111210 717000 810000 u The Elmo Bumpy Torus Reactor. McAlees, D.G.; Uckan, N.A.; Bettis, E.S.; et al. CONF-760935-P2, PP. 619-628 A V A I L A B I L I T Y - N T I S O A R N L

7018 ? Date September 1976 010000 111210 111110 717000 A Brief Review of the Fusion-Fission Hybrid Reactor. Tcnney, F.H. CONF-760935-P2, PP. 641-655 „ A V A I L A B I L I T Y - N T I S U - P A 0 °

%

/

" 7011 Date September 1976 010000 111210 717000 810000 What is Past is Prologue: Future Directions in Tokamak

Power Reactor Design Research. Conn, R.W. „ CONF-760935-P2, PP. 539-553 A V A I L A B I L I T Y - N T I S U - W I 0

7012 Date September 1976 010000 111210 717000 810000 Mirror Machine Reactors. Carlson, G.A.; Moir, R.W. CONF-760935-P2, PP. 555-573 A V A I L A B I L I T Y - N T I S L A L L "

7021 Date September 1976 010000 111110 111210 717000 810000 V

Mirror Hybrids - A ;Status Report. Lee, J.D.; Bender, D?J.; Moir; R.W.; Schultz, K.R. CONF-760935-P2, PP. 689-710 AV A I L A B I L I T Y - N T I S GEAC

7028 Date September 1976 010000 111210 210000 32A000 329000 531000 532O0CL

521130 717000 810000 An Assessment of Nucleonic Methods and Data for Fusion

Reactors. Dudziak, D.J. < CONF-760935-P3, PP. 819-832; L A - U R - 7 6 - 2 0 8 6 A V A I L A B I L I T Y - N T I S LOASL //

H

7013 Date September 1976 010000 111210 717000 810000 A Technology Assessment of Laser Fusion Power Produc-

. tion. Booth, L.A.; Frank, T.G. CONF-760935-P2, PP. 575-589 A V A I L A B I L I T Y - N T I S LOASL t

7030 . . Date September 1976 010000 111210 329000 531000 532000 717000 810000 Multidimensional Neutronics Analysis of Major Penetra-

tions in Tokamaks. Abdou, M.A.; Milton, L.J.; Jung, JIG.; Gelbard, E.M. -CONF-760935-P3, PP. 845-860 * % A V A I L A B I L I T Y - N T I S A R G O N N

ff 8

7036 Date September 1976 010000 210000 717000 Development and Technology in the U.S. Magnetic Fusion

Power Program. Will iams, J.M.; Beal, J.W.; Coffman, F.E.; Henning, C.D.;<~

Zwilsky, K.M. CONF-760935-P3 , PP. 1075-1094 A V A I L A B I L I T Y - N T I S DOE „ "

/ to

<> 7037 . . . Date September 1976 010000 111210 717000 The Euratom Fusion Technology Programme. Hancox, R. '• CONF-760935-P3 , PP. 1095-1103 A V A I L A B I L I T Y - N T I S ENGL r AN

7042 Date September 1976 010000 111210-112760 223000x210000 521130 522130

531000 532000 717000 795254 810000 Radioactivity and Associated Problems in Thermonuclear

Reactors. / j <• * ' Vogelsang, W.F. M J / CONF-760935-P4, ;FP. 1303-1318; U W F D M - 1 7 8 A V A I L A B I L I T Y - N T I S , U - W I o

7043 Date September 1976 010000 111210 717000 810000 An Assessment of Blanket and Shield Technology. Twining, B.G.; Powell, J.R. CONF-760935-P4 , PP. 1433-1446 A V A I L A B I L I T Y - N T I S B R O O K H

))

7038 Date September 1976 010000 111210 717000 The Fusion Technology Prograrrri.T_Japan. Mor i , S. <• CONF-760935-P3 , PP. 1105-1112 A V A I L A B I L I T Y - N T I S J A P A N t i V

7051. . ,.t Date January 1977 000000 010000 Radiation Physics. Ghose, A.M. ; Gopinath, D.V.; Hubbell, J.H.; Roy, S.C. NBS SPEO.XPUB. 461 A V A I L A B I L I T Y - S U P T . OF D O C U M E N T S , GPO,

W A S H I N G T O N , D.C. 20402 $3.25 I N D I A

7039 Date September 1976 010000 111210 717000 U.S. Laser Fusion Technology Program. Schriever, R.L. CONF-760935-P3 , PP. 1113-1120 A V A I L A B I L I T Y - N T I S DOE

7055 Date January 1977 010000 121100 121200 810000 " Radiation Physics and Nuclear Technology. Iyengar, P.K. NBS SPEC. PUB. 461, PP. 32-40 A V A I L A B I L I T Y - S U P T . OF D O C U M E N T S , GPO,

W A S H I N G T O N , D.C. 20402 I N D I A

70*10 Date September 1976 010000 11*1210 717000 Status of the JET Project and Its Supporting Technological

Programme. Bertolini, E. CONF-760935-P3 , PP. 1121-1135 A V A I L A B I L I T Y - N T I S E N G L A N

7062 Date January 1977 010000 020000 Development of Radiation Shielding Standards in USA. Trubey, D.K. NBS SPEC. PUB. 461, PP. 74-78 o A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

W A S H I N G T O N , D.C. 20402 O A R N L

7041 Date September 1976 010000 111210 717000 The EPRI Fusion Power Program - Status and Goals. Gough, W.C. CONF-760935-P3 , PP. 1137-1152 A V A I L A B I L I T Y - N T I S EPRI 6

7068 Date January 1977 = 010000 112BO0 310000 522110 522210 6.\0000 810000 Backscattering of Gamma Rays. ' Hyodo, T. NBS SPEC. PUB. 461, PP. 110-118 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

W A S H I N G T O N , D.C. 20402 J A P A N

» 9

7074. . . Date January 1977 010000^/11110 32AOOO 325000 32FOOO 521130 713000

81,0000 Neutron Transport Studies in Fast Reactor Shields. Vhvifyanathan, R.; Murthy, K.P.N.; Singh, R.S. „ N B S SPEC. PUB. 461, PP. 163-165 A V A I L A B I L I T Y - S U P T . O F D O C U M E N T S , GPO,

W A S H I N G T O N , D.C. 20402 INDIA 6

I C R U tU-t

8140. . . Date September 1, 1978 010000 111120 4)l0000 424000 A Review of the Delayed Fission Neutron Technique. Binney, S.E.; Scherpelz, R.I. NUCL. I N S T R U M . M E T H O D S , 154(3), 4 1 3 - 4 3 1 U - O R

t) u „ " 7075 Date January 1977

000000 010000 Computer Codes and Data Available from the Radiation

Shielding Information Center, Q Trubey, D.K.; Maskewitz, B.F.; Roussin. R.W. N B S SPEC. PUB. 461, PP. 171-173 A V A I L A B I L I T Y - S U P T . OF D O C U M E N T S , GPO,

W A S H I N G T O N , D.C. 20402 O A R N L

8191 Date 1978 010000 111110 122310 870090 870092

^Evaluat ion of Fast Integral .Data Related to 2 3 3 - U and o Thorium. Beck, C.L.; Lineberry, M.J.; Schaefer, R.W.; Carpenter,

S.G.; Wade, D.C. „ „ C O N F - 7 8 0 4 0 1 - 1 4 <> ' {( AVAILABILITY-DEP. , N T I S A R G O N N O

7078. . p . Date January 1977 010000 121200\220000 423240 Actual Problems in Photon Dosimetry. Regulla, D.F.; Drexler, G. N B S S P E C r P U B . 461, PP. 197 - 208 A V AILABI LIT Y - SUPT. OF DOCUMENTS, GPO,

W A S H I N G T O N , D.C. 20402 G E R M A N

<)

7118 Date July 1976 010000 420000 421150 511120 861000 Modern Methods and Experience of Analyses of Neutron

Energy Distributions in Nuclear Reactor Experiments. Yegorov, Yu.A.; Pankrat 'yev, Yu.V. E R D A - T R - 1 2 5 , PP. 176-190 A V A I L A B I L I T Y - N T I S RUSSIA

«

8212 Date October 1978 010000 111130 112130 220000 521120 522120 Organ Dose Estimates for the Japanese Atomic - Bomb Sur-

vivors. Kerr, G.D. O R N L - 5 4 3 6 AVAILABILITY - NTIS ' $5.25 « O A R N L ^

<r o 8239 Date February - March 1978

010000 112710 610000 <• Internal Conversion Coefficients for all Atomic Shells I C C c

" Values for Z = 30 -67 . Rosel, F.;'Fries, H.M.; Alder, K.; Pauli, H.C. A T O M I C DATA A N D N U C L . DATA TABLES,0

21(2-3) , 91 -289 S W I T Z E "

8089 Date Mid -Augus t 1978 010000 210000 How Does One Predict and Measure Radiation Damage? Nichols, F.A.

, ,NUCL. T E C H N O L O G Y , 40(1), 9 8 - 1 0 5 A R G O N N

8112 Date 1978 010000 111110 111220 410000 423110 423120 423130

423135 423140 511120 0 o An International Neutron Dosimetry Intercomparison; 0

ICRIT ' lCRU- r

S27 A V A l L A B I L I T Y - I C R U PUBLICATIONS, P.O: BOX

30165® W A S H I N G T O N , D.C. 20014

<3 %(/ h

it 0

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», -

8257 Date 1970 010000 111130 112130 521120 522120 731200 Protection Against Penetrating Radiation from a Nuclear

- Plant. Kukhtevich, V.I.; Goryachev, I.V.; Trykov, L.A. BOOK ( IN R U S S I A N ) p H A V A I L A B I L I T Y - A T O M I Z D A T , M O S C O W RUSSIA 0 " „

0 a o n ij "

8258. . . !>.,. . Date 1976 010000 210000 o a '' * " =1 Radiation Damage in Metals.4 ' Peterson, N.L.; Harkness, S.D.?" ' K v "" BOOK . 0 m " V " ^ ' • ' ' c A V A I L A B I L I T Y - A M E R I C A N SOCIETY FOR MET-

ALS, METALS PARK? O H I O V , ' • o vf '' "

10

ARGOP/N " ,,, A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) t> E N G L A N

8264 u., Date May 1977 010000 223000 Survey of Decontamination and Decommissioning Tech-

niques. „ " Kusler, L.E. « A R H T j C D - 9 8 4 A V A I L A B I L I T Y - NTIS

• ATRA

8268 Date August 1978 010000 11217.0 8 70092 870094 Review of Existing Compilations and Evaluations of FPND. Lammer, G. o I A E A - 2 1 3 , P P . 5 - 3 2 „ A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) IAEA

G

8269 Date August 1978 010000 112120 222000 870092 870094 •• o Nseds and Accuracy Requirements for FPND'in the Assess-

a ment of Environmental Aspects.

Lindberg, L. I A E A - 2 1 3 , PP .33 -39 „ " <*> jf A V A I L A B I L I T Y - I A E A , V I E N N A ' ( M F O N L Y ) S W E D E N - * o . a

ii ° -- " a . ®

8270. . .< . . . ' . " Date August 1978 6 010000 112120 713000 719A00 870092 870094 % 0

Needs and Accuracy'Requirements for F P N D in the Physics Design of Power1 Reactor Cores. ,,

•> Rowlands, J.L. ° * IAEA 213, PP .41 -60 , c 0

A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) ft

' E N G L A N

8271 6 Date August 1978 Q

010000 112120 532000 870092 870094 The Importance of Fission Product Nucleai?Data in Reactor

Design and Operation; Devillers, C. 0

I A E A - 2 1 3 , P P . 6 1 - 8 9 A V A I L A B I L I T Y - I A E A , V I E N N A (MF O N L Y ) F R A N C E

8273 Date August 1978 010000 112120 230000 870092 870094 ^ A Review of FPND,Requirements for Investigation of Irra-

diated Nuclear Fuel: Burnup Measurements, Neutron Dosimetry, Nuclear Safeguards.

Maeck, W.J. (, I A E A - 2 1 3 ; PP .105-108 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L ^ ) ALCC <i

8274 , Date August 1978 u

010000 123000 112120 810000 Status of Neutron Reaction Cross Sections of Fission Prod-

ucts in the Energy Range of Resolved and Unresolved Resonances. 0

Fort, E. I A E A - 2 1 3 , PP .139-218 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) FRANCE-,

8275 Date August 1978 010000 1^2310 112120 810000 * Impact of Integral Measurements on the Capture

Cross-Section Evaluations of Individual Fission Prod-uct Isotopes.

Gruppelaar,',H.; Dekker, J .W.M. I A E A - 2 1 3 , PP.219-277 0

A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) N E T H E R

c>P

8276 Date August 1978' 010000 111210 122310 810000 Status of Fast Neutron Reaction Cross Section of Fission

Products. r J

Iijima, S. I A E A - 2 1 3 , PP .279-350 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) J A P A N ^

8272. . .c. . s> Date August 1978 010000 112120 230000'870092 870094 Needs and Accuracy Requirements for F P N D in the

O u t - o f - P i l e Fuel Cycle. McKay, H.A.C. I A E A - 2 1 3 , P P . 9 1 - 1 0 4

Cs

8277 Date August 1978 010000 112120 870092 870094 Status of Fission Product Yield Data. Cuninghame, J.G. IAEA-213 , PP .351-419 A V/ i lLABILIT Y - IAEA, V I E N N A ( M F O N L Y ) E N G L A N

\l

0

0 " !j "» 8406 Date July 1978

010000 111110 111210 Proceedings of the Second Fusion - Fission Energy-Sys tems '

Review Meeting. Volume I. Bogart , S.L. (Ed. )

; | C 0 N F - 7 7 1 1 2 5 - P 1 A V A I L A B I L I T Y - D E P . ' , N T I S D O E

8422 ' I Date August 1978 010000 112120 532000 795137 870092 » Integral Determinat ion of Fission Product Inventory

j'J Decay Power. Schenter , R.E.; England, T .R . I A E A - 2 1 3 , VOL.11, P P . 6 7 7 - 7 4 1 AVAIL-ABILITYr- IAEA ( M F ONLY,) H A N F O R

''-"A' • "I

8407. . : Da te July 1978 010000 1-11110 111210 Proceedings of the Second Fusion Fission Energy Systems

Review; Meeting. Volume II. Bogart , S .L! (Ed. ) C O N F - 7 7 1 1 5 5 - i P ? ^ = = = = = = r . A V A I L A B I L I T Y - D E P . , N T I S D O E ' " «

8413 Da te M a y 1978 010000 421200 410000 424000 D O E - G r a r i d Junction Logging Model Data-Synopsis. Mathews , M.A.; Koizumi, C.J.; Evans, H.B. G J B X - 7 6 ( 7 8 ) =

A V A I L A B I L I T Y - D E P . , N T I S B E N D I X

8434 '. Da te November 1978 010000 220000 222000 223000 230000 0

Radiat ion Exposure of the U K Population. Taylor, F.E.; Webb,"G.A.M. N R P B - R 7 7 o A V A I L A B I L I T Y - H M S O ° E N G L A N °

8471 Date November 1978 010000 11L110 1112.10 717100 Laser Fusion Hybrids - Technical , Economic and Prol ifera-

t i o n Considerations. O Moses, ^G. A.; Conn, R.W.; A b d e l - K h a l i k , S . I . " ' U W F D M - 2 7 2 0 A V A I L A B I L I T Y - F U S I O N , R E S E A R C H P R O G R A M ,

N U C L E A R E N G I N E E R I N G DEPT. , U N I V E R S I T Y O F WISCONSIN,"MADISOIM, W I S C O N S I N 53706

U - W I o

V a

8418 . Da te August 1978 010000 112120 123000 870092 870094 Prediction of Unmeasured Fission Yields by Nuclear Theory

or Systematics. <> ^ Denschlag, J .O. I A E A - 2 1 3 , VOL.11, P P . 4 2 1 - 4 8 5 A V A I L A B I L I T Y - I A E A ( M F O N L Y ) G E R M A N

8419 Da te August 1978 010000 112120 870092 870094 Status of Decay Da ta of Fission Products . Blachot, J . I A E A - 2 1 3 , VOL.11, PP.487-56.5 A V A I L A B I L I T Y - I A E A ( M F O N L Y ) F R A N C E

% 8420 Date Augus t 1978

010000 111120 870092 Sta tus of Delayed Neut ron Data . Ruds tam, G. I A E A - 213,-;VOL.II, P P . 5 6 7 - 6 2 6 0

A V A I L A B I L I T Y - I A E A ( M F O N L Y ) S W E D E N

9

Q

8494 Date October 1, 1978 010000 121100 810000 " ;S>

An Index to t he Li terature on Microscopic Neu t ron ;Da ta . . . IAEA

C I N D A 78 - S U P P L . 5 T O C I N D A 7 6 / 7 7 A V A I L A B I L I T Y - I N T E R N A T I O N A L ATOMIC"

E N E R G Y A G E N C Y , V I E N N A I A E A

8505 Date 1978 i> 010000 220000 420000 Instrumentat ion and Monitoring Methods for Radia t ion '

Protection. , 4

N C R P o '-> N C R P - 5 7 *

a A V A I L A B I L I T Y - N C R P ^ P U B L I C A T I O N S , P.O. B O X H

30175, W A S H I N G T O N , D.C. 20014 N C R P

8512 v Date December 1978 010000 220000 O n D^ose-Response and S tandard Setting. Weinberg, A . M . O R A U / I E A - 78 - 21 (0) A V A I L A B I L I T Y - N T I S

Ik,

12 9 •» tj.

O A R A U

8522 Date October 12, 1978 010000 329000 430000 On Some Statistical Problems Inherent in Radioac-

t ive-Source Detection. Barnett, C.S. U C R L - 5 2 5 8 8 A V A I L A B I L I T Y - N T I S LALL

8561 Date 1977 010000 111210 717000 Proceedings of the Seventh Symposium on Engineering

Problems of Fusion Research. Vol.1. Lubcll, M.S.; Whitmire. C . J r . (Eds.) CONF-771029 ,VOL.1 A V A I L A B I L I T Y - I E E E S E R V I C E C E N T E R , S I N G L E

P U B L I C A T I O N SALES DEPT., 445 H O E S LANE, P ISCATAWAY, N.J. 08854

O A R N L


Problems of Fusion Research. Vol.11. ,. Lubell, M.S.; Whitmire, C.,Jr. (Eds.)

C O N F - 7 7 1 0 2 9 , VOL.11 A V A I L A B I L I T Y - I E E E S E R V I C E C E N T E R , S I N G L E

P U B L I C A T I O N SALES DEPT., 445 H O E S LANE, P I S C A T A W A Y , N.J. 08854

O A R N L

8576 Date November 1978 020000 010000 122100 122310 713000 810000 Nuclear Data Needs for Fast Breeder Reactor Shielding. Oblow, E.M.; Perey, F.G. C O N F - 7 8 1 1 1 7 - 5 A V A I L A B I L I T Y - D E P . , N T I S O A R N L

8584 Date 1977 010000 111110 421140 Proceedings of the First A S T M - E U R A T O M Symposium

on Reactor Dosimetry. Held at Petten(Holland), Sep t .22-26 , 1975.

Commission of the European Communities E U R - 5 6 6 7 E / F , P T . I ; CONF-750935 ,PT . I A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L PUBLICA-

T I O N S O F T H E E U R O P E A N C O M M U N I T I E S , BOITE P O S T A L 1003 - L U X E M B O U R G $24.00

N E T H E R

8585 Date 1977 010000 111110 210000 421140 430000 713000 717000

719A00 719B00 795112 810000 Neutron Environmental Characterization Requirements for

Reactor Materials Development and Surveillance Pro-grams.

McElroy, W.N.; Bennett, R.A.; Johnson, D.L. E U R - 5 6 6 7 E / F , P T . I , P P . 1 - 2 6 ; CONF-750935 ,PT . I ,

PP. 1 - 2 6 A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L PUBLICA-

T I O N S OF T H E E U R O P E A N C O M M U N I T I E S , BOITE POSTAL 1003 - L U X E M B O U R G

W E E

8586 Date 1977 010000 111110 210000 421140 713000 719A00 810000 Dosimetry Methods for Structural Material Irradiation in

the European Countries. Farinelli, U. E U R - 5 6 6 7 E / F . P T . I , PP .27-40 ; CONF-750935 ,PT . I ,

P P . 2 7 - 4 0 A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L PUBLICA-

T I O N S O F T H E E U R O P E A N C O M M U N I T I E S , BOITE POSTAL 1003 - L U X E M B O U R G

I T A L Y

8590 P . Date 1977 111110 010000 020000 421140 Standardization of Neutron Measurements on Nuclear

Reactors in the USSR. Vasilyev, R.D.; Grigoryev, E.I.; Doropheev, G.A.; Jarina,

V:P. E U R - 5 6 6 7 E / F , P T . I , PP .74-83 ; CONF-750935 ,PT . I ,

P P . 7 4 - 8 3 A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L PUBLICA-

T I O N S OF T H E E U R O P E A N C O M M U N I T I E S , BOITE P O S T A L 1003 - L U X E M B O U R G

R U S S I A

8596 Date 1977 010000 111110 430000 795112 795233 Review of Unfolding Methods for Neutron Flux Dosimetry. Stallmann, F.W.; Kam, F.B.K. EUR - 5667 E/F ,PT.I , PP.221-232;

CONF-750935 ,PT . I , PP .221 -232 A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L PUBLICA-

T I O N S OF T H E E U R O P E A N C O M M U N I T I E S , BOITE P O S T A L 1003 - L U X E M B O U R G

U - T N

(8597 Date 1977 • 010000 111110 421140 430000 795108 795112 795233

Review of Activation Methods for the Determination of Neutron Flux Density Spectra.

13 D

Zijp, W.L. E U R - 5667E/F.PT.I , PP .233-300 ;

CONF-750935 ,PT . I , P P . 2 3 3 - 3 0 0 , A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L PUBLICA-

T I O N S O F T H E E U R O P E A N C O M M U N I T I E S , BOITE P O S T A L 1003 - L U X E M B O U R G

N E T H E R

8767 Date January 1979 010000 713000 717100 717500 Status and Prospects of Advanced Fissile Fuel Breeders. Kostofif, R .N. C O N F - 7 9 0 1 0 3 A V A I L A B I L I T Y - N T I S S7.25 D O E

8600 Date 1977 010000 111110 421140 430000 795108 795112 795233 Unfolding Codes for Neutron Spectra Evaluation Possibili-

ties and Limitations. Dierckx, R.; Sangiust, V. E U R - 5 6 6 7 E / F , P T . I , PP .322-350 ;

C O N F - 7 5 0 9 3 5 , P T . I , P P . 3 2 2 - 3 5 0 <i AVAILABILITY - O F F I C E F O R O F F I C I A L PUBLICA-

T I O N S O F T H E E U R O P E A N C O M M U N I T I E S , BOITE P O S T A L 1003 - L U X E M B O U R G

I T A L Y

(i 8650 Date February 1979

010000 122310 312000 A Review of the Theory and Application of Sensitivity and

Uncertainty Analysis. Proceedings of a Semi-na r -Workshop , Oak Ridge, Tennessee, August 2 2 - 2 4 , 1978.

Weisbin, C.R.; Roussin, R.W.; Hendrickson, H.R.; Bryant, E.W. (Eds.)

O R N L / R S I C - 4 2 A V A I L A B I L I T Y - N T I S $13.00 O A R N L

8669 Date February 1979 010000 020000 122310 810000 Expectations for E N D F / B - V Covariance Files: Coverage,

Strength and Limitations. Perey, F.G. O R N L / R S I C - 4 2 , P P . 3 1 1 - 3 1 8 A V A I L A B I L I T Y - N T I S O A R N L

8710 ,. Date 1978 010000 ,111110 32A000 329000 312000 551110 552210

713000 719B00 793000 794000 795254 795320 810000 Methods fo r 'U .S . Shielding Calculations: Applicat ions ' '^

F F T F and C R B R Designs. ,, Engle, W.W.,Jr . ; Mynatt , F.R.; Disney, R.K. C O N F - 7 8 1 1 1 7 - 3 A V A I L A B I L I T Y - D E P , N T I S O A R N L o °

8780 Date January 1979 010000 220000 Doses in Radiation Accidents Investigated by Chromosome

Aberration Analysis. IX. A Review of Cases Investigat-ed: 1973.

Lloyd, D.C.; Purrott , R.J.; Prosser, J.S.; White, A.D.; Dol-phin, G.W.; Reeder, E.J.; Martin, L.C.; Priseman, S.J.; Gray, S.A.

N R P B - R 8 3 A V A I L A B I L I T Y - H M S O E N G L A N

8790 Date April 1979 010000 111210 717100 810000 An Optimization of the Fission-Fusion Hybrid Concept. Saltmarsh, M.J.; Grimes, W.R.; Santoro, R.T. O R N L / P P A - 7 9 / 3 A V A I L A B I L I T Y - O A K R I D G E N A T I O N A L LABO-

R A T O R Y , OAK RIDGE, T E N N E S S E E O A R N L

8791 f . . Date February 1979 010000 111110 223000 719A00 721100 722100 Radiation Streaming in Power Reactors. Lahti, G.P.; Lee, R.R.; Courtney, J.C. (Eds.) O R N L / R S I C - 4 3 ; A N S / S D - 7 9 / 1 6 A V A I L A B I L I T Y - N T I S $9.25 O R A N L

8792. . Date February 1979 010000 111110 223000 32A0Q0 521110 522110 610000

719AOO 722100 853100 861000 Neutron Flux Determination in the Reactor Cavities of

LWRs. Rahn, F.; Till, H. O R N L / R S I C - 4 3 , P P . 1 - 2 1 ; A N S / S D - 7 9 / 1 6 , P P . 1 - 2 1 A V A I L A B I L I T Y - N T I S EPRI

8830 Date March 1978 111210 010000 210000 717000 810000 Radiation Considerations for Superconducting Fusion Mag-

nets. Abdou, M.A. J. N U C L . MATER. , 7 2 ( 1 - 2 ) , 147-167

14

A R G O N N

8837 Date September 1978 010000 122100 810000 Nuclea r Da ta for Reactor Design, Operat ion and Safety. Rowlands, J .L. C O N F - 7 8 0 9 2 1 , P P . 7 - 2 7 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 P A R I S C E D E X 16, F R A N C E E N G L A N

8838 Date September 1978 010000 122100 122200 810000 Nuclea r Da ta for Reactor Shielding. Butler, J . C O N F - 7 8 0 9 2 1 , P P . 2 8 - 6 0 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,


8839 Date September 1978 010000 122100 810000 N o n - P r o l i f e r a t i o n and Nuclear Data . Sowerby, M.G. C O N F - 7 8 0 9 2 1 , P P . 6 1 - 7 5 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,


' 8840 Date September 1978 010000 122100 122310 870006 870092 Covariance Matr ices of Experimental Data . Percy, F .G. C O N F - 7 8 0 9 2 1 , P P . 1 0 4 - 1 1 5 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 P A R I S C E D E X 16, F R A N C E O A R N L

884 1 Date September 1978 010000 122100 122310 810000 Correla ted Uncer ta int ies in Integral Da ta . McCracken , A.K. C O N F - 7 8 0 9 2 1 , P P . 1 1 6 - 1 3 5 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,


884 2 Date September 1978 010000 122200 112400 112500 112600 810000 Photon Product ion in Neutron Induccd Reactions, van Heerden, I.J. C O N F - 7 8 0 9 2 1 , P P . 1 6 0 - 1 8 0

A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L , 75775 P A R I S C E D E X 16, F R A N C E

S A F R I C vi

8843 Date September 1978 010000 122310 713000 887000 Determinat ion of Transact in ide Nuc lea r Da ta Required

Accuracy for B u r n - u p Calculation in Fast Reactors . Usachev, L.N. ; Bobkov, Yu.G. ; Kolesov, V.E.; Krivtsov, A.S. C O N F - 780921, PP . 181 - 1 8 6 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 P A R I S C E D E X 16, F R A N C E R U S S I A

8844 Date September 1978 010000 122200 112710 810000 The U K Chemical Nuclear Da ta Files: An Evaluated Set of

Radioact ive Decay Da ta for Rcactor Applications. Davies, B.S.J.; Crouch, E.A.C.; James, M.F. ; Nichols, A.L.;

• Parkinson, J .R.; Tobias, A.; Vallis, D.G. C O N F - 7 8 0 9 2 1 , P P . 2 0 9 - 2 1 4

. A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L , 75775 P A R I S C E D E X 16, F R A N C E

E N G L A N

8845 Date Sep tember 1978 010000 112710 122200 810000 Bibliotheque de Donnees Nucleaires non Neutroniques des

Isotopes Radioactifs , Produits de Fission et Noyaux Lourds.

Blachot, J.; Fiche, Ch. C O N F - 7 8 0 9 2 1 , P P . 2 1 5 - 2 2 2 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 P A R I S C E D E X 16, F R A N C E F R A N C E

8846 Date September 1978 010000 122100 870090 870092 870094 Cross -Sec t ions of the M a j o r Transact inium Isotopes in the

Resonance Region. Keyworth, G.A.; Moore, M.S . _ s> C O N F - 7 8 0 9 2 1 , P P . 2 4 1 - 2 6 7 •• A V A I L A B I L I T Y - O E C D , 2, R U E " A N D R E - P A S C A L ,

75775 P A R I S C E D E X 16, F R A N C E L O A S L

8847 Date September 1978 010000 122100 861000 862000 Resonance Cross Sections for S t ruc tura l Mater ia l . Frohner , F .H. C O N F - 7 8 G 9 2 1 , P P . 2 6 8 - 2 8 7 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 P A R I S C E D E X 16, F R A N C E

J, 15

G E R M A N

8848 Date September 1978 010000 121100 112500 u Neutron Radiative Capture Cross-Sect ion Calculations. Benzi, V. C O N F - 7 8 0 9 2 1 , P P . 2 8 8 - 3 0 5 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 P A R I S C E D E X 16, F R A N C E ITALY

8849 Date September 1978 010000 123000 Recent Developments in the Theory of the Nuclear Level

Density. Jensen, A.S. C O N F - 7 8 0 9 2 1 , P P . 3 7 8 - 3 9 5 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 P A R I S CEDEX 16, F R A N C E D E N M A R

8853 Date September 1978 010000 111220 870095 '•"' Neutron Production f rom ( a l p h a , ^ R e a c t i o n s in Actinide

Oxides. f

Lees, E.W. C O N F - 7 8 0 9 2 1 , P P . 6 1 5 - 6 2 0 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,


Ci 8854 Date September 1978

010000 122100 122200 220000 312000 32A000 760000 795207 795254 845000 870006 870008 793000

Nuclear Data Requirements for the Calculation of Absorbed Dose and Simulation of Tissue Response in Neutron Therapy.

Pfister, G.; Hehn, G.; Mattes, M.; Friedlein, H.P. C O N F - 7 8 0 9 2 1 , PP .621-627 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 PARIS C E D E X 16, F R A N C E G E R M A N

8850 Date September 1978 010000 122100 711100 712000 810000 Fuel Handling, Reprocessing and Waste and Related

Nuclear Data Aspects. Kusters, H.; Lalovic, M.; Wiese, W.H. C O N F - 7 8 0 9 2 1 , P P . 5 1 8 - 5 5 0 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 P A R I S C E D E X 16, F R A N C E G E R M A N '

8855 Date September 1978 010000 122100 210000 760000 845000 Basic Nuclear Data for Dosimetry in Radiotherapy and ^ Radiobiology. Ricourt, A.; Chemtob, M.; Nguyen, V.D.; Parmentier, N . C O N F - 7 8 0 9 2 1 , PP .628-635 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 P A R I S C E D E X 16, F R A N C E F R A N C E

8851 Date September 1978 010000 112120 Fission Yield Data. Denschlag, H.O. C O N F - 7 8 0 9 2 1 , PP .569 -588 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 P A R I S CEDEX 16, F R A N C E G E R M A N

8856 Date September 1978 010000 111110 329000. ;424000 430000 810000 Nuclear Data in the Design of Neutron Probes for Borehole

Logging. Sanders, L.G. C O N F - 7 8 0 9 2 1 , PP .642-647 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,


8852 Date September 1978 010000 111220 870006 870012 870013 870014 Neutron Yields f rom (alpha,n) Reactions in the Light Ele-

ments. West, D.; Sherwood, A.C. C O N F - 7 8 0 9 2 1 , P P . 6 1 0 - 6 1 4 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,


8857 Date September 1978 010000 122100 210000 760000 845000 Nuclear Data for Radiotherapy with Neutrons. Cross, W.G. C O N F - 7 8 0 9 2 1 , PP .648-666 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 P A R I S C E D E X 16, F R A N C E C A N A D A

16

8858 Dale September 1978 010000 122100 210000 760000 845000 Recent Trends in Nuclear Reaction Data Needs for Nuclear

Medicine. Stocklin, G.; Qaim, S.M. C O N F - 7 8 0 9 2 1 , PP.667-687 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 P A R I S CEDEX 16, F R A N C E G E R M A N

8861 Date September 1978 010000 122310 521230 717100 810000 Neutron Data for the Hybrid Reactor Calculation. Markovskii, D.V.; Shatalov,.fj .E. C O N F - 7 8 0 9 2 1 , PP .783-791 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 P A R I S CEDEX 16, F R A N C E R U S S I A

8862 Date September 1978 010000 717500 Accelerator Breeding of Fissile Material. Taschek, R.F. , C O N F - 7 8 0 9 2 1 , PP .792-808 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 P A R I S C E D E X 16, F R A N C E L O A S L

8864 Date September 1978 010000 122100 810000 Nuclear Data for Safeguards. Fuketa, T. C O N F - 7 8 0 9 2 1 , PP .922-940 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 P A R I S CEDEX 16, F R A N C E J A P A N

A V A I L A B I L I T Y - D E P . , N T I S O A R N L

8895 Date December 1978 010000 111210 122310 3A2000 717000 Cross-Section Sensitivity and Uncertainty Analysis for

Fusion Reactors (A Review). Dudziak, D.J. L A - U R - 7 9 - 1 6 8 A V A I L A B I L I T Y - L O S A L A M O S S C I E N T I F I C LAB.,

U N I V E R S I T Y O F C A L I F O R N I A , LOS ALAMOS, N E W M E X I C O 87544

LOASL

8932 Date January 1979 010000 111210 121100 210000 521130 717000 795217

795254 810000 Transmutation and Activation of Fusion Reactor Wall and

Structural Materials. Jarvis, O.N. A E R E - R - 9 2 9 8 A V A I L A B I L I T Y - H . M . S . O . E N G L A N

8936 Date May 1978 010000 111210 717000 Magnetic Fusion Program in the United States: An Over-

view and Perspective. Clarke, J.F. C .ONF-780508 ,VOL.I , P P . 1 - 1 8 A V A I L X B I L I T Y - D E P . , N T I S DOE

8869 Date September 1978 010000 122100 717000 810000 Nuclear Data for Fusion Reactors. Jarvis, O .N. C O N F - 7 8 0 9 2 1 , PP .1073-1087 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,


8937 Date May 1978 010000 111210 717000 Fusion - The Programme in the U.K. - and Other

Thoughts. Carruthers, R. CONF-780508 ,VOL.1 , PP. 19 -27 A V A I L A B I L I T Y - D E P . , N T I S E N G L A N

8876 V. . Date 1979 010000 111210 210000 717000 810000 Effects of Irradiation on the Normal Metal of a Composite

Superconductor: A Comparison of Copper and Alumi-num.

Klabunde, C.E.; Coltman, R.R.,Jr.; Williams, J .M. C O N F - 7 9 Q 1 2 5 - 2 5

8938 Date May 1978 010000 111210 717000 Development on Fusion Reactors in Japan. Mori, S. CONF-780508 ,VOL.1 , P P . 2 8 - 3 7 A V A I L A B I L I T Y - D E P . , N T I S J A P A N

17

8939 Date May 1978 010000 111210 717000 The J E T Project - Progress in Construction and Manage-

ment.-' 1,1

Bertolini, E. CONF-780508 ,VOL.1 , P P . 3 8 - 4 9 A V A I L A B I L I T Y - D E P . , N T I S E N G L A N

8940 Date May 1978 010000 111210 717000 (

Advanced Fusion Concepts P r o g r a m . ; ^ Dove, W.F. C O N F - 7 8 0 5 0 8 , V O L . I , P P . 5 1 - 5 7 A V A I L A B I L I T Y - D E P . , N T I S » DOE

8941 Date May 1978 010000 111210 717000 Alternative Fusion Concepts: Engineering and Utility Con-

siderations. Gough, W.C.; Amherd, N.A. C O N F - 7 8 0 5 0 8 , V O L . I , P P . 5 8 - 6 3 A V A I L A B I L I T Y - D E P . , N T I S DOE 1

8942 Date May 1978 010000 111210 717000 Tandem Mirror Reactor. Moir, R.W.; Barr, W.L.; Bender, D.J.; Carlson, G.A.; Dex-

ter, W.L.; Doggett, J .N.; Fink, J .H.; Hamilton, G.W.; Lee, J.D.; Logan, B.G.; Neef, W.S.,Jr.; Peterson, M.A.; Rensink, M.E.

C O N F - 7 8 0 5 0 8 , V O L . 1, P P . 6 4 - 7 3 e

A V A I L A B I L I T Y - D E P . , N T I S LALL

8943 .1'. . . . . . : Date May 1978 010000 111210 717000 The Elmo Bumpy Torus (EBT) Reactor - A Status Report. Uckan, N.A.; Bettis, E.S.; Dandl, R.A.; Hedrick, C.L.; San-

toro, R.T.; Watts , H.L.; Yeh, H.T. C O N F - 7 8 0 5 0 8 , V O L . I , P P . 7 4 - 8 2 A V A I L A B I L I T Y - D E P . , N T I S O A R N L

8945 Date May 1978 010000 111210 717000 Synfuels Production from Fusion Reactors. Fillo, J.A.; Powell, J .R.; Steinberg, M.; Salzano, F.; Benena-

ti, R.; Dang, V.; Fogelson, S.; Isaacs, H.; Kouts, H.; Kushner, M.; Lazareth, O.; Majeski, S.; Makowitz, H.; Sheehan, T.V.

C O N F - 7 8 0 5 0 8 , V O L . I , P P . 1 9 3 - 2 0 2 A V A I L A B I L I T Y - D E P . , N T I S U - N Y

8956 Date May 1978 010000 111210 210000 717000 810000 Materials Program for Magnetic Fusion Energy. Zwilsky, K.M.; Cohen, M.M.; Finfgeld, C.R.; Reuther , T.C. C O N F - 7 8 0 5 0 8 , V O L . I , P P . 5 4 9 - 5 5 3 A V A I L A B I L I T Y - D E P . , N T I S DOE

8964 Date June 1979 010000 112120 122100 719A00 Symposium Summary: Nuclear Data Problems for Thermal

Reactor Applications. Rose, P.F.; Pearlstein, S.; Ozer, O. E P R I - N P - 1 0 9 8 - S Y A V A I L A B I L I T Y - N A T I O N A L N U C L E A R D A T A

C E N T E R , B R O O K H A V E N N A T I O N A L LABORA-T O R Y , U P T O N , N E W Y O R K 11973

BROOKH

9003 Date 1979 010000 420000 Radiation Detection and,Measurements. Knoll, G.F. BOOK A V A I L A B I L I T Y - W I L E Y PUB. U - M I o

9008 Date June 1979 010000 121100 310000 An Index to the Literature on Microscopic Neutron Data. IAEA C I N D A - 7 9 (1977-1979) A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C

E N E R G Y A G E N C Y , V I E N N A IAEA

8944 Date May 1978 010000 111210 717000 The Reversed-Field Multiple Mirror Concept. Steinhauer, L.; Grossmann, W.; Seyler, C.E. C O N F - 7 8 0 5 0 8 , V O L . I , P P . 8 3 - 8 9 A V A I L A B I L I T Y - D E P . , N T I S M A S N y,

9009 Date May 1979 010000 121100 310000 An Index to the Literature on Microscopic Neutron Data. 1 Vol.1. Z Less than or Equal to 50. IAEA C I N D A - A (1935-1976) VOL.I

t 18

A V A I L A B I L I T Y - I N T E R N A T I O N A L ATOMIC ENERGY AGENCY, VIENNA

IAEA

9010 Date May 1979 010000 121100 310000 An Index to the Literature on Microscopic Neutron Data.

Vol.2. Z Greater than or Equal to 51. IAEA C I N D A - A (1935-1976) VOL.2 A V A I L A B I L I T Y - I N T E R N A T I O N A L ATOMIC

ENERGY AGENCY, VIENNA IAEA

9014.K Date April 1979 010000 123000 High Energy Physics. The Ultimate Structure of Matter and

Energy. DOE D O E / E R - 0 0 2 7 AVAILABILITY-DIVISION , O F HIGH ENERGY

PHYSICS, OFFICE OF ENERGY RESEARCH, DOE, WASHINGTON, D.C. ,

DOE

9022 Date April 1979 010000 329000 A Relativity Primer for Particle Transport. A LASL Mono-

graph. j Everett, C.J.; Cashwell, E.D. L A - 7 7 9 2 - M S AVAILABILITY-LOS ALAMOS SCIENTIFIC LABO-

RATORY, N E W MEXICO LOASL

9063 Date June 1 - 1 5 , 1979 010000 420000 Detectors in Nuclear Science. Part II. Bromley, D.A. (Ed.) NUCL. INSTRUM. METHODS, 162(1-3), 371-738 U - C T

9131 Date 1979 010000 713000 Physics Problems of Fast Reactor Shielding. Farinelli, U.; Nicks, R. ATOMIC ENERGY REV., 17(1), 129-179 " ITALY

9140 Date July-August 1979 010000 222000 An Analysis of N R C Methods for Estimating the Effects of

Dry Deposition in Environmental Radiological Assess-ments.

Miller, C.W.; Hoffman, F.O. NUCL. SAFETY, 20(4), 458-467 O A R N L

9165 Date April 15, 1979 010000 220000 Quantitative Concepts and Dosimetry in Radiobiology. Wyckoff, H.O. (Ch.) ICRU - 30 AVAILABILITY-ICRU PUBLICATIONS, P.O. BOX

30165, WASHINGTON, D.C. 20014 ICRU

9166 Date May 1, 1979 010000 121100 121200 420000 Average Energy Required to Produce an Ion Pair. Wyckoff, H.O. I C R U - 3 1 AVAILABILITY-ICRU PUBLICATIONS, P.O. BOX


9190 Date November 1978 010000 020000 111110 719AOO Sources of Neutronics Data Involving Thorium of 2 3 3 - U

and Light Water Moderation. Davenport, L.C. P N L - 2 9 1 7 AVAILABILITY-PACIFIC N O R T H W E S T LABORA-

TORY, RICHLAND, W A S H I N G T O N PANL

9129 Date June 1979 010000 020000 122310 329000 719A00 870090 870092 Integral Testing of Thorium and U233 Data for Thermal

Reactors (AWBA Development Program). Hardy, J.,Jr.; Ullo, J.J.; Steen, N.M. WAPD - TM -1449 AVAI LABILITY - BETTIS ATOMIC POWER LABO-

RATORY', WEST MIFFLIN, PA. !

BETTIS

9231 Date April 24, 1979 010000 020000 410000 511120 551120 Nuclear Criticality Experiments from 1943 to 1978, an

Annotated Bibliography: Volume 1, Main Listing. Koponen, B.L.; Wilcox, T.P.; Hampel, V.E. UCRL-52769 , VOL.l AVAILABILITY-NTIS LALL

&

19


Annotated Bibliography: Volume 2, Lookup Tables. Koponen, B.L.; Wilcox, T.P.; Hampel , V.E. U C R L - 5 2 7 6 9 , VOL.2 A V A I L A B I L I T Y - N T I S L A L L

9256 Date October 1979 010000 112120 Decay Spectra of Fission Products from U r a n i u m - 2 3 5

Thermal Fission: Comparison of Calculations with Experiments.

Stamatelatos, M.G.; England, T.R. N U C L . T E C H N O L O G Y , 45(3), 2 1 9 - 2 3 2 L O A S L

9307 Date June 1979 010000 223000 230000 810000 Fuel Handling, Reprocessing, and Waste and Related

Nuclear Data Aspects. Kusters, H.; et al. K F K - 2 8 3 3 A V A I L A B I L I T Y - K E R N F O R S C H U N G S Z E N T R U M

K A R L S R U H E , G M B H , K A R L S R U H E (F.R. G E R -M A N Y )

G E R M A N

9324 Date June 1979 010000 111210 717100 A Survey of Fusion-Fiss ion System Designs and Nuclear

Analyses. Youssef, M.Z. ; et al. U W F D M - 3 0 8 A V A I L A B I L I T Y - F U S I O N E N G I N E E R I N G P R O -

G R A M , N U C L E A R E N G I N E E R I N G DEPT. , U N I V E R S I T Y O F W I S C O N S I N , M A D I S O N WI 53706

U - W I

9386 Date August 1979 010000 111210 210000 717000 810000 A Critical Assessment of the Effects of Pulsed Irradiation on " Materials . " Ghoniem, N .M. ; Kulcinski, G.L. " U W F D M - 3 1 1 A V A I L A B I L I T Y - F U S I O N E N G I N E E R I N G P R O -

G R A M , N U C L E A R E N G I N E E R I N G DEPT. , U N I V E R S I T Y O F W I S C O N S I N , M A D I S O N , W I 53706

U - W I

9388 Date October 1979 010000 111210 711100 717100 Hybrids for Direct Enrichment and Se l f -Pro tec ted Fissile

Fuel Protection. Conn, R.W.; Kantrowitz, F.; Vogelsang, W.F. U W F D M - 3 1 6 A V A I L A B I L I T Y - F U S I O N E N G I N E E R I N G P R O -

G R A M , N U C L E A R E N G I N E E R I N G DEPT. , U N I V E R S I T Y O F W I S C O N S I N , M A D I S O N , W I 53706

U - W I

9389 Date October 1979 010000 111210 717100 810000 869999 A Brief Summary of Different Tri t ium Sources for a Triti-

umless Hybrid Reactor. Moses, G.A. U W F D M - 3 1 7 A V A I L A B I L I T Y - F U S I O N E N G I N E E R I N G P R O -

G R A M , N U C L E A R E N G I N E E R I N G DEPT. , U N I V E R S I T Y O F W I S C O N S I N , M A D I S O N , WI 53706

U - W I

9432 Date October 1979 010000 122100 810000 W R E N D A 79/80 . World Request List for Nuclear Data . Muir, D.W. I N D C ( S E C ) - 7 3 / U R S F ''' A V A I L A B I L I T Y - I A E A N U C L E A R D A T A S E C T I O N ,

K A R N T N E R R I N G 11, A - lojio V I E N N A IAEA "

9454 Date November 1979 010000 111210 14 MeV d,t Sources. Barschall, H .H. U W F D M - 3 3 1 A V A I L A B I L I T Y - F U S I O N E N G I N E E R I N G P R O -

G R A M , N U C L E A R E N G I N E E R I N G DEPT.', U N I V E R S I T Y O F W I S C O N S I N , M A D I S O N W I 53706

U - W I

9482 Date 1979 010000 111210 210000 717000 Tokamak Reactors and Structural Materials. Conn, R.W. C O N F - 7 9 0 1 2 5 , PT.A, P P . 9 - 1 6 ; J. N U C L E A R

MATER. , 85 AND;S6, AV A I L A B I L I T Y - ^ N O R T H - H O L L A N D P U B L I S H -

I N G C O M P A N Y - A M S T E R D A M U - W I

20

9483 Date 1979 010000 111210 717000 717100 810000 Mirror Fusion Reactor Design. N&r, W.S.,Jr.; Carlson, G.A. CONF-790125 , PT.A, PP.17-28; J. NUCLEAR

MATER., 85 A N D 86, A V A I L A B I L I T Y - N O R T H - H O L L A N D PUBLISH-

ING C O M P A N Y - AMSTERDAM LALL

9546 Date December 1979 010000 1U210 717100 810000 Summary of the Fusion-Fission Hybrid Fuel Cycle Analy-

sis (Tritiumless Hybrids?). Moses, G.A. (Comp.) U W F D M - 3 3 7 AVAI L A B I L I T Y - F U S I O N ENGINEERING PRO-

GRAM, D E P A R T M E N T OF NUCLEAR ENGINEERING, UNIV. OF WISCONSIN, MADI-SON, WI/;53706

U - W I

9484 Date 1979 010000 111210 717100 810000 Materials Implications of Fusion-Fission Reactor Designs. Schultz, K.R. CONF-790125 , PT.A, PP.29-36; J. NUCLEAR


ING COMPANY - AMSTERDAM GEAC

9568. Date'1978 010000*020000 220000 SI Units in Radiation Protection. Jain, V.K.; Soman, S.D. BARC-964 AVAILABILITY-DEP.; ' NTIS (U.S. SALES ONLY),

PC A 0 3 / M F A01 INDIA

9485 Date 1979 010000 111210 210000 717000 810000 The Material Implications of Design and System Studies for

Inertial Confinement Fusion Systems. Maniscalco, J.A.; Berwald, D.H.; Meier, W.R. CONF-790125 , PT.A, PP.37-46; J . NUCLEAR


ING C O M P A N Y - AMSTERDAM LALL

9486 Date 1979 010000 111210 111220 210000 717000 810000 Irradiation Sources for Fusion Materials Development. Holmes, J.J.; Straalsund, J.L. CONF-790125 , PT.A, PP.447-451; J. NUCLEAR

MATER., 85 A N D 86, AVAILABILITY - N O R T H - HOLLAND PUBLISH-

ING COMPANY - AMSTERDAM H A N F O R

9488 Date 1979 010000 111220 210000 410000 717000 The Fusion Materials Irradiation Test Facility at Hanford. Pottmeyer, E.W.,Jr. CONF-790125 , PT.A, PP.463-465; J. N U C L E A R

MATER., 85 A N D 86, A V A I L A B I L I T Y - N O R T H - HOLLAND PUBLISH-

ING C O M P A N Y - AMSTERDAM H A N F O R

9569 Date October 1979 010000 121100 810000 An Index to the Literature on Microscopic Neutron Data. IAEA CINDA 79 S U P P L E M E N T A V A I L A B I L I T Y - I N T E R N A T I O N A L ATOMIC

ENERGY AGENCY, V I E N N A " IAEA

9617 Date March 1978 010000 230000 Determination of a Radioactive Waste Classification Sys-

tem. Cohen, J.J.; King, W.C. U C R L - 5 2 5 3 5 A V A I L A B I L I T Y - C A L I F O R N I A UNIV., LIVER-

MQRE, L A W R E N C E LIVERMORE LAB. LALL

9641 Date October 1978 010000 717500 Accelerator Breeder Concept. Bartholomew, G.A.; Fraser, J.S.; Garvey, P.M. AECL-6363 AVAILABILITY-DEP. , NTIS (U.S. SALES ONLY),

PC A 0 3 / M F A01 CANADA

9642 Date February 1979 010000 220000 222000 223000 Nuclear Risks. Newcombe, H.B.

21

A E C L - 6 4 7 7 A V A I L A B I L I T Y - D E P . , N T I S (U.S. S A L E S ONLY) ,

P C A 0 3 / M F A01 C A N A D A

0 9743 Date 1979

010000 111110 310000 32AOOO 325000 Modern Coarse-Mesh Methods - A Development of the

'70's. Doming, J.J. CONF-790402,VOL-I , P P . 3 - 1 - - 3 - 3 1 AVAILABILITY - H C - - A N S V I R G I N I A SECTION,

P.O. BOX 1260, L Y N C H B U R G , VA. 24505; M F — N T I S

U - I L

9758 Date 1979 010000 111110 329000 795187 A Comprehensive Survey of Continuous Energy

Three-Dimensional Monte Carlo Criticality Codes. Steinberg, H.A. CONF-790402,VOL.11, P P . 7 - 1 - - 7 - 8 AVAILABILITY - H C - - A N S V I R G I N I A SECTION,

P.O. BOX 1260, L Y N C H B U R G , VA. 24505; M F - - N T I S

^ M A A G "0

9780 x Date December 1979 010000 111210 122100 717000 810000 Nuclear Data Requirements of the Magnetic Fusion Power

Program of the United States of America. (Introductory Paper N o . l )

Head, C.R. I A E A - T E C D O C - 2 2 3 , P P . 1 - 7 A V A I L A B I L I T Y - M F O N L Y - INIS M I C R O F I C H E

C L E A R I N G H O U S E , IAEA, W A G R A M E R -STRASSE 5, P.O. BOX 100, A - 1 4 0 0 VIENNA, A U S T R I A

D O E

9781 Date December 1979 O'lflgOO 111210 122100 717000 810000 Nuclear Data Requirements for Fusion Reactor Design - °

Neutronics Design, Blanket Neutronics and Tritium Breeding. (Review Paper N o . A l )

Constantine, G. I A E A - T E C D O C - 2 2 3 , P P . 1 1 - 2 9 ' ^ A V A I L A B I L I T Y - M F O N L Y - I N I S M I C R O F I C H E

C L E A R I N G H O U S E , IAEA, W A G R A M E R -STRASSE 5, P.O. BOX 100, A - 1 4 0 0 VIENNA, A U S T R I A

E N G L A N

9782 Date December 1979 010000 111210 210000 717000 810000 J) Review of Nuclear Heating in Fusion Reactors. (Review

Paper No.A2) Seki, Y. I A E A - T E C D O C - 2 2 3 , PP .31-45 A V A I L A B I L I T Y - M F ONLY - INIS M I C R O F I C H E

C L E A R I N G H O U S E , IAEA, W A G R A M E R -S T R A S S E 5, P.O. BOX 100, A - 1 4 0 0 V I E N N A , A U S T R I A

JAPAN

9783 Date December 1979 010000 111210 717000 810000 -Nuclear Data Requirements for Transmutation and Activa-

tion of Reactor Wall and Structural Materials. (Review Paper No.A3) ,t ,, "

Jarvis, O.N. I A E A - T E C D O C - 2 2 3 , PP .47 -74 A V A I L A B I L I T Y - M F ONLY - INIS M I C R O F I C H E

C L E A R I N G H O U S E , IAEA, W A G R A M E R -ST RA SSE 5, P.O. BOX 100, A - 1 4 0 0 V I E N N A , A U S T R I A

E N G L A N

9784 Date December 1979 010000 111210 122100 210000 717000 810000 Nuclear Data Needs for Radiation Damage Studies Rele-

vant to Fusion Reactor Technology. (Review Paper No.A4)

,Qaim, S.M. I A E A - T E C D O C - 2 2 3 , PP .75 -89 A V A I L A B I L I T Y - M F ONLY - INIS M I C R O F I C H E

C L E A R I N G H O U S E , IAEA, W A G R A M E R -S T R A S S E 5, P.O. BOX 100, A - 1 4 0 0 V I E N N A , A U S T R I A

G E R M A N

9785 Date December 1979 010000 111210 122100 122200 717000 810000 Nuclear Data Requirements for Fusion Reactor Shielding.

(Review Paper No.A5) Abdou, M.A. I A E A - T E C D O C - 2 2 3 , PP.91 - 110 A V A I L A B I L I T Y - M F ONLY - I N I S M I C R O F I C H E

C L E A R I N G H O U S E ; IAEA, W A G R A M E R -ST RA SSE 5, P.O. BOX 100, A - 1 4 0 0 V I E N N A , A U S T R I A

U - G A

9786 Date December 197? 010000 111210 717100 810000 122100 ^ s Neutron Data' for Hybrid Reactor Calculations. (Review

Paper N0.A6)

22

Markovskii, D.V.; Shatalov, G.E. I A E A - T E C D O C - 2 2 3 , PP .111-118 A V A I L A B I L I T Y - M F O N L Y - I N I S M I C R O F I C H E

C L E A R I N G H O U S E , IAEA, W A G R A M E R -STRASSE 5, P.O. BOX 100, A - 1 4 0 0 VIENNA, AUSTRIA

RUSSIA

9787 Date December 1979 010000 111210 312000 32AOOO 717000 810000 Cross-Section Sensitivity and Uncertainty Analysis for

Fusion Reactors - A Review. (Review Paper No .Bl ) 11 Dudziak, D.J. I A E A - T E C D O C - 2 2 3 , PP .121-138 ' ' A V A I L A B I L I T Y - M F O N L Y - I N I S M I C R O F I C H E

C L E A R I N G H O U S E , IAEA, W A G R A M E R -STR ASSE 5, P.O. BOX 100, A-.l^OO VIENNA, AUSTRIA

LOASL

9788 Date December 1979 010000 111210 122100 123000 717000 810000 Theoretical Approach to Nuclear Data Required For Fusion

Reactor Calculations. (Review Paper No.B2) Seeliger, D. I A E A - T E C D O C - 2 2 3 , PP .139-152 ^ A V A I L A B I L I T Y - M F O N L Y - I N I S M i C R O F I C H E

C L E A R I N G H O U S E , IAEA, W A G R A M E R -STRASSE 5, P.O. BOX 100, A - 1 4 0 0 s VIENNA, AUSTRIA

G E R M A N

9789 Date December 1979 010000 111210 122100 122200 717000 717100 810000 Evaluated Files of Nuclear Cross Sections for Fusion Reac-

tor Calculations. (Review Paper No.B3) Bhat, M.R. I A E A - T E C D O C - 2 2 3 , PP .153-183 A V A I L A B I L I T Y - M F O N L Y - I N I S M I C R O F I C H E

C L E A R I N G H O U S E , IAEA, W A G R A M E R -STRASSE 5, P.O. BOX 100, A - 1 4 0 0 VIENNA, AUSTRIA

BROOKH

9790 Date December 1979 010000 122100 717000 810000 a u Neutron Reaction Data in the MeV Range. (Review Paper

No.B4) Liskien, H. I A E A - T E C D O C - 2 2 3 , PP .185-197 A V A I L A B I L I T Y - M F O N L Y - I N I S M I C R O F I C H E

0 C L E A R I N G H O U S E , IAEA, W A G R A M E R -£ STRASSE" 5, P.O. BOX 100, A - 1 4 0 0 VIENNA,

A U S T R I A

BELGIU

9791 Date December 1979 010000 111210 122100 717000 810000 Status of 1 4 - M e V Neutron Cross Section Data. (Review

Paper N0.B6) Csikai, J. I A E A - T E C D O C - 2 2 3 , PP.199-222 A V A I L A B I L I T Y - M F O N L Y - I N I S M I C R O F I C H E

C L E A R I N G H O U S E , " IAEA, W A G R A M E R -STRASSE 5, P.O. BOX 100, A - 1 4 0 0 V I E N N A , AUSTRIA

H U N G A R

9800 Date November 1979 010000 123000 750000 Cross Sections for Electron and Photon Processes Required

by Electron-Transport Calculations. Peek, J .M. S A N D - 7 9 - 0 7 7 2 A V A I L A B I L I T Y - D E P . , NTIS, PC A 0 6 / M F A01 S A N D I A

9829 Date November 1978 010000 020000 112120 112760 Brief Description of the E N D F / B - V Format Adopted for

Use in the U K Decay and Fission Product Yield Data Files.1

Tobias, A. C E G B - R D / B / N - 4 4 2 3 A V A I L A B I L I T Y - D E P . , N T I S (U.S. SALES ONLY) ,

PC A 0 3 / M F A01 E N G L A N

(•

1. 0 0

9935 Date January 1980 010000 717100 ^ Fusion-Fission Energy Systems Evaluation. ~~ Teofifo, V.L.; Aase, D.T.; Bickford, W.E.; Leonard, B.R.,Jr.

McCormick, N.J.; McGrath, R.T.; Morrison, J.E. Perry, R.T.; Ribe, F.L.; Rockwood, A.D.; Schulte, S.C. Willingham, C.E.; Woodruff, G.L.

P N L - 3 1 1 6 AVAILABILITY - N T I S P A N L

9978 f Date May 1980 010000 329000 32A000 521130 810000 The Status of Monte Carlo at Los Alamos. Thompson, W.L.; Cashwell, E.D.; Godfrey, T.N.K.; Sch-

randt, R.G.; Deutsch, O.L.; Bootli, T.E. L A - 8 3 5 3 - M S ; O R N L / R S I C - 4 4 , PP .231-246 A V A I L A B I L I T Y - N T I S $5.25 LOASL

23

9985 Date August 1980 010000 329000 n A Review of the Theory and Application of Monte Carlo

Methods - Proceedings of a Seminar-Workshop, Oak Ridge, Tennessee, April 2 1 - 2 3 , 1980.

Trubey, D.K.; McGill, B.L. (Eds.) O R N L / R S I C - 4 4 A V A I L A B I L I T Y - N T I S , P C A 1 6 / M F A01 O A R N L

° 9987 ,< J. . . . Date ^August 1980 ,010000 329000 VIM - A Continuous Energy Monte Carlo Code a t ANL. Blomquist, R.N.; Lell, R.M.; Gelbard, E.M. O R N L / R S I C - 4 4 , P P . 3 1 - 4 6 V1 „ A V A I L A B I L I T Y - N T I S , P C A 1 6 / M F A01 A R G O N N

"9988 Date August 1980 010000 312000 329000 521130 810000 <g> Monte Carlo Perturbation Theory in Neutron Transport

Calculations. Hall, M.C.G. O R N L / R S I C - 4 4 , P P . 4 7 - 6 2 A V A I L A B I L I T Y - N T I S , P C A 1 6 / M F A01 E N G L A N

9989 Date August 1980 010000 122310 329000 521130 795372 795254 Study of Perturbations L]sing Correlated Monte Carlo

Method. Dejonghe, G.; Gonnord, J.; Nimal, J.C. O R N L / R S I C - 4 4 , P P . 6 3 - 9 3 A V A I L A B I L I T Y - N T I S , P C A 1 6 / M F A01 F R A N C E

9992 Date August 1980 010000 122110 329000 712000 K E N O V - The Newest K E N O Monte Carlo Criticality

Program. Landers, N.F.; Petrie, L.M. O R N L / R S I C - 4 4 , PP .121-128 A V A I L A B I L I T Y - N T I S , P C A 1 6 / M F A01 O A R N L

9994 Date August 1980 010000 329000 795187 Nuclear Data Treatment for S A M - C E Monte Carlo Cal-

culations. Lichtenstein, H.; Troubetzkoy, E.S.; Beer, M. O R N L / R S I C - 4 4 , PP .137 -142 A V A I L A B I L I T Y - N T I S , P C A 1 6 / M F A01 MAAG

9995 Date August 1980 010000 329000 795187 Monte Carlo Methodology as Implemented in S A M - F . Troubetzkoy, E.S.; Steinberg, H.A. O R N L / R S I C - 4 4 , PP .143-150 A V A I L A B I L I T Y - N T I S , P C A 1 6 / M F A01 MAAG

9996 Date August 1980 010000 329000 721100 719AOO 795187 Radiation Streaming with S A M - C E . De Gangi, N.; Cohen, M.O.; Waluschka, E.; Steinberg, H.A. O R N L / R S I C - 4 4 , PP .151-155 A V A I L A B I L I T Y - N T I S , P C A 1 6 / M F A01 MAAG <>

9998 Date August 1980," 010000 312000 329000717000810000 The Recursive Monte Carlo Method for Deep-Penetrat ion

Problems. Goldstein, M.; Greenspan, E. 0

O R N L / R S I C - 4 4 , PP .169-187 A V A I L A B I L I T Y - N T I S , P C A 1 6 / M F A01 O A R N L

9999 Date August 1980 010000 329000 719A00 795376 The Monte Carlo Lattice Program KIM. Cupini, E.; De Matteis, A.; Simonini, R. O R N L / R S I C - 4 4 , PP .189-196 A V A I L A B I L I T Y - N T I S , PC A-16/MF A01 ITALY /

10003 Date August 1980 010000 329000 Geometry in MCNP. Godfrey, T.N.K. O R N L / R S I C - 4 4 , PP .247-252 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 LOASL

10004 Date August 1980 010000 329000 Flux at a Point in MCNP. Cashwell, E.D.; Schrandt, R.G. O R N L / R S I C - 4 4 , PP .253-265 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 LOASL ''

. 10005 Date August 1980 010000 329000,721100 853100 870011 Deep-Penetration Calculations.

0

24

Thompson, W.L.; Deutsch, O.L.; Booth, T.E. ORNL/RSIC-44 , PP.267-294 A V A I L A B I L I T Y - N T I S , PC A16 /MF A01 LOASL

ii O

10007 Date August 1980 010000 329000 79.5203 MORSE: Current Status of the Two Oak Ridge Versions. Emmett, M.B.; West, J.T.,III « ORNL /RS IC-44 , PP.305-312 A V A I L A B I L I T Y - N T I S , PC A16/MF A01

O, OARNL

'C/ fc 10008 Date August 1980

010000 329000 795372 Overview on TRIPOLI 2. Gonnord, J:; Baur, A.; Bourdet, L.; Dejonghe, G.; Monnier,

A.; Nirhal, J.C.; Vergnaud, T. ORNL/RSIC-44 , PP.313-328 A V A I L A B I L I T Y - N T I S , PC A16 /MF A01 FRANCE

Standards and Benchmark Problems

CATEGORY NUMBER 020000 o

6293 .J l jP&ie October 1977 111110 020000 329000 7 1 9 A 0 % ^ f ' ^ Improvement of Reference Nuclear Data for Commercial

Power Reactor Analysis and Design. ^ Levitt, L.; Magurno, B.; Rose, P. EPRI -NP-556 A V A I L A B I L I T Y - E L E C T R I C POWER RESEARCH

INSTITUTE, 3412 HILLVIEW AVENUE, PALO ALTO, C A L I F O R N I A 94304

EPRI

6380 Date Dec. 1977 010000 020000 312000 A Review of Progress in the N E A / I A E A Collaborative Pro-

gram of Sensitivity Studies and Shielding Benchmarks. Butler, J. CONF-770401 , PP.120-131

/ A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE ; J DR., P R I N C E T O N , NJ 08540

ENGLAN

10009 Date August 1980 010000 311000 329000 721100 853100 795203 795276 Variance Reduction Techniques Using Adjoint Monte Carlo

Method and Monte Carlo - Monte Carlo Coupling in Deep Penetration Problem.

Ueki, K. ORNL/RSIC-44 , PP.329-344 A V A I L A B I L I T Y - N T I S , PC A16 /MF A01 JAPAN "

6416 Date Dec. 1977 020000 010000, Radiation Protection and Shielding Standards. Vallario, E.J.; Trubey, D.K. CONF-770401, PP.448-456 'c A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE'

DR., PRINCETON, NJ 08540 DOE

6417 Date Dec. 1977 "020000 220000 Shielding Standards—A Case History. Battat, M.E. CONF-770401, PP.457-462 u


LOASL

641 S T" Date Dec. 1977 020000 122100 Activities of the Shielding Subcommittee of the ENDF/B

Cross Section Evaluation Working Group. Roussin, R.W. CONF-770401, PP.463-471 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 O A R N L (i

10057 ! Date Nlay 1980 " 010000 122100 887000 f j <> Transactinium Isotope Nuclear Data - 1979. Proceedings

of the Second Advisory Group Meeting on Transac-tinium Isotope Nuclear Data Organized by the IAEA and held in Cadarache, 2 - 5 May 1979.

IAEA IAEA-TECDOC-232 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE,- IAEA, WAGRAMERSTRASSE 5, P.O. BOX 100, A-1400 V IENNA, AUSTRIA

IAEA «

S*

25

' 6419 Date Dec. 1977 020000 122110 The Role of "Standard" Fine-Group Cross Section

Libraries in Shielding Analysis. Weisbin, C.R.; Roussin, R.W.; Oblow, E.M.; Cullen, D.E.;

White, J.E.; Wright, R-Q-CONF-770401, PP.472-481 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6544 Date December 1977 " 111110 020000 329000 719AOO 820000 870092 ' Monte Carlo Analyses to TRX Slightly Enriched-H,/sub

2/ O Critical Experiments with E N D F / B - I V and Related Data Sets. (AWBA Development Program).,

Hardy, J.,Jr. W A P D - T M - 1 3 0 7 A V A I L A B I L I T Y - WESTINGHOUSE ELECTRIC '

CORPORATION,'BETTIS ATOMIC POWER DIVI-SION

BETTIS

6420 Date Dec. 1977 020000 122110 Generation and Testing of Shielding Data Libraries for Fis-

sion and Fusion Technology. Caglioti, E.; Mattes, M.; Nicks, R.; Penkuhn, H.; Hehn, G.;

Herrnberger, V. CONF-770401, PP.482-493 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 I T A L Y

6462 Date Dec. 1977 020000 111110 421140.551120 795254 795222 861000

870011 Two-Dimensional Shielding Benchmarks for Sodium and

Iron at YAYOI . Oka, Y.; An,S.; Kasai, S.; Sakata, S.; Miyasaka, S.; Koya-

ma, X.; Hyodo, T. ' 0

CONF-770401; PP.833-840 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 JAPAN

6510 Date 1976 020000 111110 111210 111220 122100 122200 810000

845000 Basic Physical Data for Neutron Dosimetry. Broerse, J.J. (Ed.) EUR-5629 A V A I L A B I L I T Y - I N I S NETHER

6586 Date 1976 020000 122100 870092 <v The Status of U -235 Fission as a Cross Section Standard. Carlson, C.W.; Czirr, J.B. A N L - 7 6 - 9 0 , PP.258-269 t ;

A V A I L A B I L I T X - N T I S , ' L A L L ' „ T ] "

s r> . 6591 .^i '-pafe i 976

010000 020000 122100' * r> o . a . Requirements on Experiment Reporting to Meet Evaluation Needs.

Peelle, R.W. ( l 0,, A N L - 7 6 - 9 0 , PP.421-430 ; S

A V A I L A B I L I T Y - N T I S « OARNL

{<

6611 . . . Date February 1978 020000 111110 329000 551120^795209 795254 870092

870094 885000 t Analysis of Somef'-Iramum Oxide and Mixed-Oxide Lat-

tice Measurements. Sher, R.; Fiarman, S. , 0

EPRI -NP-691 A V A I L A B I L I T Y - D E P A R T M E N T OF-: M E C H A N I -

CAL ENGINEERING, STANFQRD UNIVERSITY, STANFORD, CALIFORNIA 94305

EPRI 0 ''

6513 Date October 1976 020000 511120

..Review of Microscopic Integral Cross Section Data in Fun-damental Reactor" Dosimetry Benchmark Neutron Fields.


HEDL - S A -1148(DR AFT); CONF-761127-5 A V A I L A B I L I T Y - N T I S $4.00 HANFOR ;

6615 . Date August 1977 020000 122100 SOKRATOR Manual. Format' of the Recommended

Nuclear Data Library for Reactor Calculations."' Kolesov, V.E.; Nikolaev, M.N. o INDC(CCP) -97 /L SPECIAL A V A I L A B I L I T Y - I A E A NUCLEAR DATA SECTION,

KARNTNER JUNG 11, A-1010 V I E N N A IAEA

26

n

6799 Date June 1978 020000 421140 421130 32A000 861000 511120 Benchmark Shielding Experiments for Testing Iron and

Steel Data. McCombie, C.; Gmur, K.; Jermann, M.; Richmond, R.; Sch-

mocker, U.; Seth, S. CONF-780401, PP.53-62 A V A I L A B I L I T Y - N T I S SWITZ ,

6827 Date 1978 010000 020000 111110 111220 410000 Fast Neutron Standards at the PTB. Wagner, S.R. IAEA-208 , VOL.11, PP.15-27 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE G E R M A N

6St>0.'. . ; Date 1978 •,111110 oioooe 4 10000 421J30 421140 511120 C I Spectra! Characterization of the N1SUS Neutron Field. Williams, J.Q.; Hann&fu A.H.M.A. > IAEA-208 , VQL.I1, PP,63-76 " > A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE E N G L A N O

,' 6834, Date 1978 111110 020000 410000 421140 511120 The Coupled Fast Reactivity Measurements Facility . (CFRMF). Rogers, J.W.; Harker, Y.D.; Millsap, D.A. I A E A - 2 0 8 , VOL.11, PP.117-176 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE EDGERT

U 6842 Date 1978

010000 020000 111110 421140 511120 /. Measurement and Evaluation of Threshold Reaction Cross

Sections in Standard Neutron Fields. Kimura, I.; Kobayashi, K.; Hayashi, Shu A.; Yamamoto, S.;

Gotoh, H.; Yagi, H. I A E A - 2 0 8 , VOL.11, PP.265-290 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE J A P A N

6887 Date March 1977 020000 220000 610000 Neutron and Gamma-Ray F lux- to -Dose-Rate Fac-

tors.

Battat, M.E. ANSI /ANS-6 .1 .1 -1977 A V A I L A B I L I T Y - A M E R I C A N N U C L E A R SOCIETY,

555 N O R T H KENSINGTON, AVE., L A G R A N G E PARK, I L L I N O I S 60525 $12.00

A M N S

6893 Date 1977 020000 220000 430000 " Radiation Protection Instrumentation Test and Calibration. Sclby, J.M.; Larson, H.V.; Bartlett, W.T.; Mulhern, O.R.;

Fleming, D.M. CONF-771209-12; I A E A - S M - 2 2 2 / 0 6 A V A I L A B I L I T Y - D E P . , NTIS B A N W

6938 Date Apr i l 1978 020000 222000 223000 Environmental Radiation Protection Standards: An Appre-

ciation. •Richings, L.D.G.; Morley, F.; Kelly, G.N. NRPB-R71 A V A I L A B I L I T Y - H M S O E N G L A N

7062 Date January 1977 010000 020000 Development of Radiation Shielding Standards in USA. Trubey, D.K. NBS SPEC. PUB. 461, PP. 74-78 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

WASHINGTON, D.C. 20402 O A R N L

7131 Date March 1977 020000 111110 122310 312000 32A000 810000 Compilation of Sensitivity Profiles for Several CSEWG Fast

Reactor Benchmarks. Marable, J.H.; Lucius, J.L.; Weisbin, C.R. ORNL-5262 ; ENDF-234 A V A I L A B I L I T Y - E R D A , TIC, P.O. BOX 62, O A K

RIDGE, TENN. 37830 O A R N L

8198 Date September 1978 020000 422110 719A00 870092 870094 Clean Critical Experiment Benchmarks for Plutonium Recy-

cle in LWRs. Smith, R.I.; Konzek, G.J. EPRI -NP-196 , VOL.2 A V A I L A B I L I T Y - B A T T E L L E PACIFIC NORTH-

WEST LABORATORIES, R I C H L A N D , W A S H I N G T O N 99352

27

B A N W

8247 Date November 1978 020000 410000 421160 Neutron Flux Monitoring and Data Analysis for Neutron

Standard Reaction Cross Sections. Wasson, O.A.; Schrack, R.A.; Lamaze, G.P. NUCL. SCL ENG., 68(2), 170-182 NABS

8424 Date October 1978 020000 325000 521130 713000 810000 Comparison of Calculations of Standard Fast Reactors

(Using the Baker Model). Voropaev, A.I.; Van'kov, A.A.; Tsybulya, A.M. INDC(CCP) - 125/LV A V A I L A B I L I T Y - I A E A N U C L E A R DATA SECTION,

K A R N T N E R R I N G 11, A -1010 V I E N N A U - W I

8517 Date February 1979 020000 111210 122310 312000 32AOOO 551110 552110

795276 717000 721100 793000 794000 861000 853100 Cross Section Sensitivity Analysis of a Proposed Neutron

Streaming Experiment with a Two-Dimensional Model.

Seki, Y.; Santoro, R.T.; Oblow, E.M.; Barnes,'J.M.; Lucius, , J.L.

O R N L / T M - 6 5 8 8 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8576 Date November 1978 020000 010000 122100 122310 713000 810000 Nuclear Data Needs for Fast Breeder Reactor Shielding. Oblow, E.M.; Perey, F.G. CONF-781117-5 A V A I L A B I L I T Y - D E P . , NTIS O A R N L

8590 Date 1977 111110 010000 020000 421140 Standardization of Neutron Measurements on Nuclear

Reactors in the USSR. Vasilyev, R.D.; Grigoryev, E.I.; Doropheev, G.A.; Jarina,

V.P. EUR-5667E/F.PT.I , PP.74-83; CONF-750935.PT.I,

PP.74-83 A V A I L A B I L I T Y - OFFICE FOR OFF IC IAL PUBLICA-

T IONS OF T H E EUROPEAN COMMUNIT IES , BOITE POSTAL 1003 - L U X E M B O U R G

RUSSIA

/ '( 8592 V. • "7_

111110 020000 421110 713000 J f Neutron Spectrometry Data in LMFBR^ . and

Standard Neutron Fields. <v/' •:•*' De Leeuw-Gierts, G.;De Leeuw, S.; H&lmick," H.H.; Rog-

ers, J.W. ) l EUR-5667E/F,PT.I , PP.99-118; C(ONlv-750935,PT.I,

PP.99-118 ' \ A V A I L A B I L I T Y - O F F I C E FOR OFFICI/f .L PUBLICA-

TIONS OF T H E EUROPEAN C O M M U N I T I E S , BOITE POSTAL 1003 - L U X E M B O U R G

BELGIU

8635 Date 1977 020000 l l l 110 421140 551120 795209 810000 The Tapiro Fast Source Reactor as a Benchmark to Test

Activation Detector Cross Sections. Martini, M.; Belli, M.; Sirito, M.F. EUR-5667E/F,PT.I I , PP.259-276;

CONF-750935,PT.II, PP.259-276 A V A I L A B I L I T Y - OFFICE FOR O F F I C I A L PUBLICA-

TIONS OF T H E EUROPEAN C O M M U N I T I E S , BOITE POSTAL 1003 - LUXEMBOURG

I T A L Y

8636 » Date 1977 111 110 020000 32AOOO 421140 511120 713000 810000 Fast Neutron Spectrum and Dosimetry Studies in the Cou-

pled Fast Reactivity Measurements Facility. Rogers, J.W.; Harker, Y.D.; Millsap, D.A. EUR - 5 667 E/ F,PT. 11, PP.277-295;

CONF-750935,PT.II, PP.277 - 295 A V A I L A B I L I T Y - O F F I C E FOR OFF IC IAL PUBLICA-

TIONS OF T H E EUROPEAN COMMUNIT IES , BOITE POSTAL 1003 - LUXEMBOURG

AERO J E

8669 Date February 1979 010000 020000^122310 810000 Expectations for E N D F / B - V Covariance Files: Coverage,

Strength and Limitations. Perey, F.G. ORNL /RS IC -42 , PP.311-318 A V A I L A B I L I T Y - NT IS O A R N L

8709 - / /—f^r.v^; . . Date 1978 020000 111110 32A000 329000 551120 552220 713000

795254 795320 795203 810000 U.S. Integral and Benchmark Experiments. Maienschein, F.C. CONF-781117-2 A V A I L A B I L I T Y - D E P . , NTIS O A R N L

28

8754 Date Apri l 1979 020000 310000 Three Basic Neutron-Transport Problems in Spherical

Geometry. (Tech. Note) Siewert, C.E.; Grandjcan, P. NUCL. SCL ENG., 70(1), 96-98 FRANCE

8978 Date February 14, 1979 020000 114000 220000 845000 New Radiobiological Findings Bearing on the 1977 ICRP

Recommendations. Dobson, R.L. UCRL-81774; CONF-790316-1 A V A I L A B I L I T Y - D E P . , NTIS L A L L

9034 Date December 1978 020000 220000 430000 Some Theoretical Aspects of Electron and Photon Dosime-

try. Seltzer, S.M.; Hubbell, J.H.; Berger, M.J. STI/PUB-471(VOL.2),PP.3-43;

CONF-771209-P2,PP.3-43; A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C

ENERGY AGENCY', V I E N N A (AUSTRIA ) NABS

9035 Date December 1978 020000 423210 Practical, Accurate Methods for Measuring the m -Values

of Ionizing Gases. Moriuchi, Y.; Katoh, A.; Takata, N.; Tanaka, R.; Tamura,

N. STI/PUB-471(VOL.2),PP.45-63;

CONF-771209-P2.PP.45-63; A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C

ENERGY AGENCY, V I E N N A (AUSTRIA ) JAPAN

9037 Date December 1978 020000 220000 423210 High-Energy Radiation Dosimetry: C sub lambda, C sub

E and Solid-Cavity Theory. Gregene, A.O. STI /PUB-471(VOL.2) ,PP.73-80;

CONF-771209-P2,PP.73-80; '' A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C

ENERGY AGENCY, V I E N N A (AUSTRIA) N I G E R I

u 9038 Date December 1978 020000 112720 Calibration of Dose Meters in Terms of Absorbed Dose in

Water for 60-Co Gamma-Radiation, Hohlfeld, K.; Reich, H. STI /PUB-471(VOL.2) ,PP.81-89;


ENERGY AGENCY, V I E N N A (AUSTRIA) G E R M A N

9039 Date December 1978 020000 220000 423210 430000 Wall Effects in Gamma-Ray Dosimetry. Jarrett, R.D.; Brynjolfsson, A.; Wang, C.P. STI/PUB-471(VOL.2),PP,91 -102;

CONF - 771209 - P2,PP,91-102; A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C

ENERGY AGENCY, V I E N N A (AUSTRIA) A R M Y

9042 Date December 1978 020000 112710 220000 Standardized Radioactive Decay Data Sets for Use in Radi-

ation Dosimetry. Kocher, D.C.; Ewbank, W.B.; Martin, M.J. ST I /PUB-471 (VOL.2),PP. 139 -145;

CONF-771209-P2,PP, 139-145; A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C

ENERGY AGENCY, V I E N N A (AUSTRIA) O A R N L

9036 Date December 1978 020000 423210 Dependence of the W-Va lue on the Atomic Number of

Heavy Ions. Varma, M.N.; Baum, J.W. STI /PUB-471( VOL.2),PP.65-71;


ENERGY AGENCY, V I E N N A (AUSTRIA) BROOKH

9043 Date December 1978 020000 112710 The Radioactivity Standards Programme of the National

Bureau of Standards. Mann, W.B. STI /PUB -471 (VOL.2),PP. 147 -154;


ENERGY AGENCY, V I E N N A (AUSTRIA) NABS

29

II 9046 Date December 1978

020000 220000 430000 Quelques Ameliorations en Spectrometrie Gamma a Basse

Activite. Baltar,.J.; Caboret, J. STI /PUB - 471 (VOL. 2),PP. 189-198;

C O N F - 771209 -P2,PP. 189 -198; A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C

ENERGY AGENCY, V I E N N A (AUSTRIA) CANADA

9107 Date June 1979 111110 020000 32AOOO 325000 521130 795134 795266

713000 793000 794000 SPECTRA-IV, Benchmark Spectra Based on L I B - I V . Kidman, R.B. L A - 7 8 6 1 - M S A V A I L A B I L I T Y - N T I S LOASL


Reactors ( A W B A Development Program). Hardy, J.,Jr.; Ullo, J.J.; Steen, N.M. W A P D - T M - 1 4 4 9 A V A I L A B I L I T Y - B E T T I S A T O M I C POWER LABO-

RATORY, WEST MIFFL IN , PA. BETTIS

9179 Data August 1979 020000 220000 222000 The Estimation of Derived Limits.

r Harrison, N.T.; Bryant, P.M.; Clarke, R.H.; Morley, F. NRPB-DL1 A V A I L A B I L I T Y - H M S O ENGLAN

9190 Date November 1978 010000 020000 111110 719A00 Sources of Neutronics Data Involving Thorium of 233-U

and Light Water Moderation. Davenport, L.C. PNL-2917 A V A I L A B I L I T Y - P A C I F I C NORTHWEST LABORA-

TORY, R I C H L A N D , WASHINGTON PANL

9196 Date December 1978 020000 220000 430000 Dissemination en France des Unites des Grandeurs Utilisees

en Metrologie des Rayonnements Ionisants. Guiho, J.-P.; Simoen, J. -P.

STI /PUB-471 (VOL. 1), PP.3-19; CONF-771209-P1, PP.3-19;

A V A I L A B I L I T Y - IAEA FRANCE

9197 Date December 1978 020000 220000 430000 Etudes Dosimetriques Menees au L M R I dans le Domaine

des References Primaires et des Procedures de Transfert. Simoen, J . -P. STI /PUB-471 (VOL. 1), PP.21-32;

CONF-771209-P1, PP.21-32; A V A I L A B I L I T Y - I A E A FRANCE

9198 Date December 1978 020000 220000 430000 Current Work in the Field of Standardization in Dosimetry

of Photons and Electrons in the Federal Republic of Ger-many.

Reich, H. STI /PUB-471 (VOL.1), PP.3 3-52;

CONF-771209-P1, PP.33-52; A V A I L A B I L I T Y - I A E A GERMAN

9199 Date December 1978 020000 220000 430000

ii A Primary Standard for Determination of Absorbed Dose in Water for X-Rays Generated at Potentials of 7.5 to 30 kV.

Bohm, J.; Hohlfeld, K.; Reich, H. STI /PUB-471(VOL. 1), PP.53-63;

CONF-771209-P1, PP.53-63; A V A I L A B I L I T Y - I A E A G E R M A N

9200 Date December 1978 020000 220000 430000 Traceability in Ionizing Radiation Measurements Systems. Cavallo, L.; Ehrlich, M.; Hutchingson, J.M.R. STI /PUB-471(VOL. 1), PP.65-87;

CONF-771209-P1, PP.65-87; A V A I L A B I L I T Y - I A E A NABS

9201 Date December 1978 020000 220000 430000 Dosimetry Standards for Industrial Radiation Processing. McLaughlin, W.L. STI /PUB-471 (VOL. 1), PP.89-106;

CONF-771209-P1, PP.89-106; ( / A V A I L A B I L I T Y - I A E A

o 30

N A B S

9202 Date December 1978 020000 220000 430000 Primary and Secondary Standards of Dosimetry: Calibra-

tion Methods in Hungary. Zsdanszky, K. o ST I /PUB-47KVOL .1 ) , PP.107-117;

CONF-771209-P1, PP.107-117; A V A I L A B I L I T Y - I A E A H U N G A R

9203 Date December 1978 020000 220000 430000 Standardization in Radiation Dosimetry in the United King-

dom. Jennings, W.A. ST I /PUB-471 (VOL.1), PP.119-131;

CONF-771209 -P I , PP.119-131; A V A I L A B I L I T Y - I A E A E N G L A N

9204 Date December 1978 020000 220000 430000 Activities of the British Calibration Service in the Radiologi-

cal Field. Rossiter, M.J. ST I /PUB-471 (VOL.1), PP.133- 138;

CONF-771209-P1, PP.133- 138; , A V A I L A B I L I T Y - I A E A

E N G L A N

° 9205 Date December 1978 020000 220000 430000 Current Work on Dosimetry Standards in Japan. Moriuchi, Y. STI /PUB -471 (VOL. 1), PP.139-158;

CONF-771209-P1, PP.139-158; A V A I L A B I L I T Y - I A E A JAPAN

9206 Date December 1978 020000 220000 430000 Medical Dosimetry Standards Programme of the National

Bureau of Standards. Loevinger, R. ST I /PUB-471 (VOL. 1), PP.159-174;

C O N F - 7 7 1 2 0 9 - P I , PP.159-174; A V A I L A B I L I T Y - I A E A NABS

9207 Date December 1978 020000 220000 430000 The Secondary Standard Dosimetry Laboratory - - A

Necessary Link in the Dissemination Chain. Julius, H.W.; van der Lugt, G. ST I /PUB-471 (VOL. 1), PP!189-192;

CONF-771209-P1, PP.189-192; A V A I L A B I L I T Y - I A E A NETHER

9208 Date December 1978 020000 220000 430000 f j ' Evaluation of the Need for Radiotherapy Calibrations in the

United States of America. Lanzl; L.H.; Rozenfeld, M. ST I /PUB-47KVOL.1 ) , PP.193-197;

CONF-771209-P1, PP.193-197; A V A I L A B I L I T Y - I A E A U - I L

9209 Date December 1978 020000 220000 430000 The Austrian Dosimetry Laboratory: A National Standard

and Routine Calibration Centre. Duftschmid, K.E. ST I /PUB-471 (VOL . l ) , PP.199-212;

CONF-771209-P1, PP.199-212; A V A I L A B I L I T Y - I A E A AUSTRI

9210 Date December 1978 020000 220000 430000 Exposure Intercomparison with Ionization Chambers -

Based on Three Intercompared Check Sources. Nette, P.; Reis, D.; Eckerl, H.; Drexlcr, G.; Pychlau, P. ST I /PUB-471 (VOL. 1), PP.213-218;

CONF-771209-P1, PP.213 —218; A V A I L A B I L I T Y - I A E A B R A Z I L

921 1 Date December 1978 020000 220000 430000 The Regional Calibration Laboratory at the M.D. Anderson

Hospital. Humphries, L.J.; Shaiek, R.J. ST I /PUB-471(VOL. l ) , PP.219-227;

CONF-771209-P1, PP.219-227; A V A I L A B I L I T Y - I A E A U - T X

921 2 Date DecembVr 1978 020000 220000 430000 Primary Dosimetric 'Standards 'at the Memorial

Sloan-Kettering Cancer Center.

31

Holt, J.G.; McDonald, J.C.; Buffa, A.;fPerry, D.; Ma, I.; Laughlin, J.S.--1

STI/PUB -471 (VOL. 1), PP.229-240; CONF-771209-P1, PP.229-240;

AVAILABILITY-IAEA SLOAN

921 3 Date December 1978 020000 220000 410000 430000 The Organization and Operation of the Regional Calibration

Laboratory at Victoreen, Cleveland. Simon, W.E. STI/PUB-471(VOL. 1,),., PP.241 -249;

CONF-771209-P1, PP.241-249; AVAILABILITY - IAEA VICTOR

921 4 Date December 1978 020000 220000 430000 The Role of the Secondary Standards Dosimetry Laboratory

in a Nuclear Power Utility. Clarke, R.W.; Thompson, I.M.G. : STI/PUB -471 (VOL. 1), PP.251-263;

CONF-771209-P1, PP.251 -263; AVAILABILITY - IAEA ENGLAN

921 5 Date December 1978 020000 220000 430000 Organization of a Secondary Standard Dosimetry Labora-

tory for the Indian Region. Subrahmanian, G.; Sundararao, I.S. STI/PUB-471 (VOL. 1), * PP.265-272;

CONF-771209-P1, PP.265-272; AVAILABILITY-IAEA INDIA

921 6 Date December 1978 020000 112720 220000 430000 < Evaluation of Dosimetric Accuracy and Uniformity for

1 60-Co Radiation Therapy. Sundararao, I.S.; Naik, S.B.; Pushpandpangadan, K.D.;

Vadiwala, R.; Subrahmanian, G. STI/PUB - 471 (VOL. 1), PP.273-280;

CONF-771209-PI, PP.273-280; AVAILABILITY-IAEA INDIA

AVAILABILITY-IAEA ICRU

9218 '.% . . . . . . Date December 1978 020000 220000 43000^ Implications of Dosimetry Intercompa-isons for Standard-

ization in Neutron Dosimetry for Biological and Medical Applications. V<

Broerse, J.J.; Burger, G.; Coppola, M. STI/PUB-47KVOL.1), PP.291-304;

CONF-771209-PI, PP.291-304; AVAILABILITY - IAEA NETHER

9219 Date Decemberx1978 020000 113100 220000 430000 The Need for Repeated Intercomparisons and Standardiza-

tion of X-Ray Dosimetry for the Co-Ordination of Late-Effects Research in Europe.

Zoetelief, J.; Broerse, J.J.; Puite, K.J. STI/PUB-471 (VOL.1), PP.305-317;

CONF-771209-PI, PP.305-317; AVAILABILITY-IAEA NETHER

922 0 Date December 1978 020000 220000 430000 Evaluation of the 1977 IAEA Pilot Study of Postal Dose

Intercomparison (TLD) for Orthovoltage X-Ray Ther-apy.

Bjarngard, B.E.; Ruden, B.-I.; Eisenlohr, H.H.; Girzi-x! kowsky, R.; Haider, J.

STI/PUB-471 (VOL.1), PP.319-333; CONF-771209-PI, PP.319-333;

AVAILABILITY-IAEA U-MA °

922 1 Date December 1978 020000 220000 430000 Dosimetric Primary and Secondary Standardization within

the European Communities. Oberhofer, M. STI/PUB-471(VOL.l), PP.335-340;

CONF-771209-P1, PP.335-340; AVAILABILITY-IAEA ITALY

9217 Date December 1978 020000 220000 The Role of ICRU in International Radiation Standards. Wyckoff, H.O. STI/PUB-471 (VOL.1), PP.283-289;

CONF-771209-PI, PP.283-289;

9222 Date December 1978 020000 220000 430000 International Standard Reference Radiations and Their

Application to the Type Testing of Dosimetric Appara-tus.

Thompson, I.M.G.

32

STI /PUB-471 (VOL.1), PP.343-365; CONF-771209-P1, PP.343-365;

A V A l L A B I L IT Y -1AE A E N G L A N

9223 Date December 1978 020000 111110 430000 870098 NBS Standard Reference Neutron Fields for Personnel

Dosimetry Calibration. Schwartz, R.B.; Grundl, J.A. STI /PUB-471 (VOL. 1), , PP.367-376;

CONF-771209-PI , PP.367-376; A V A I L A B I L I T Y - I A E A NABS

9224. Date December 1978 020000 226060 430000 Use of a Phantom in Personnel Dosimetry Photon Calibra-

tions. Bartlett, W.T.; Holland, J.P.; Hooker, C.D.; Mulhern, O.R.;

Fleming, D.M. STI /PUB-471 (VOL.1), PP.465-474;

CONF-771209-P1, PP.465-474; A V A I L A B I L I T Y - I A E A BANW

9225 Date December 1978 020000 111110 220000 430000 Personnel Dosimetry Intercomparison Studies at the ORNL

Health Physics Research Reactor. Dickson, H.W.; Gilley, L.W. STI /PUB-471 (VOL. I ) , PP.491-509;

CONF-771209-P1, PP.491-509; A V A I L A B I L I T Y - IAEA O A R N L

9227 Date December 1978 020000 220000 430000 Accuracy and Precision in Calibration of Low-Level Radi-

ation Monitors. Ackers, J.G. STI /PUB - 471 (VOL. 1), PP.527-532;


9231 Date Apri l 24, 1979 010000 020000 410000 511120 551120 Nuclear Criticality Experiments from 1943 to 1978, an

Annotated Bibliography: Volume 1, Main Listing. Koponen, B.L.; Wilcox, T.P.; Hampel, V.E. UCRL-52769, VOL. I A V A I L A B I L I T Y - N T I S

L A L L


Annotated Bibliography: Volume 2, Lookup Tables. Koponen, B.L.; Wilcox, T.P.; Hampel, V.E. UCRL-52769, VOL.2 A V A I L A B I L I T Y - N T I S L A L L

9272 Date May 1979 020000 887000 Review of Integral Data on Higher Transactinides. Harker, Y.D.; Anderl, R.A.; Turk, E.H. BNL-50991,PP.327-348; CONF-781174,PP.327-348 AV A I L A B I L I T Y - N T I S EDGERT

9273 Date May 1979 020000 870094 Integral Experiments Performed at CEA to Improve the Pu

Higher Isotope Nuclear Data: "PLUTO Programme". Chaudat, J.P.; Hammer, Ph.; Mart in-Deidier, L. BNL-50991,PP.349-365; CONF-781174,PP.349-365 A V A I L A B I L I T Y - N T I S FRANCE

9528 Date November 1979 020000 113100 220000 845000 Confirmation of Conversion Factors Relating Exposure and

Dose-Equivalent Index Presented in A N S I N13.11. Yoder, R.C.; Bartlett, W.T.; Courtney, J.W.; Hooker, C.D.;

Holland, J.A.; Hogan, B.T. NUREG/CR-1057 ; PNL-3219 A V A I L A B I L I T Y - D E P . , NTIS, PC A 0 5 / M F A01 P A N L

9568 Date 1978 010000 020000 220000 SI Units in Radiation Protection. Jain, V.K.; Soman, S.D. BARC-964 A V A I L A B I L I T Y - D E P . , NTIS (U.S. SALES ONLY) ,

PC A 0 3 / M F A01 I N D I A

9752 Date 1979 020000 r< Panel on Recent Developments in Standards Activities in

Computer Technology. Olhoeft, J.E.

33

CONF-790402,VOL.11, P P . 5 A - 1 - - 5 A - 7 A V A I L A B I L I T Y - H C - - A N S V IRGINIA SECTION,

P.O. BOX 1260, LYNCHBURG, VA. 24505; M F - - N T I S

WEE

9753 Date 1979 , 1 020000

Development of a Standard for the Validation and Verifica-tion of Calculational Procedures.

Ozer, O. CONF-790402,VOL.11, P P . 5 A - 9 - - 5 A - 1 2 A V A I L A B I L I T Y - H C - - A N S V IRGINIA SECTION,

P.O. BOX 1260, LYNCHBURG, VA. 24505; M F — N T I S

EPRI

9754 Date 1979 020000 Guidelines for Considering User Needs> in Computer Pro-

gram Development (ANS 10.5). Main, G.C. C O N F - 790402,VOL.11, PP.5 A - 1 3 — 5 A -19 A V A I L A B I L I T Y - H C - - A N S VIRGINIA SECTION,


BOEING

Kopp, L.I. CONF - 790402, VOL.11, PP.5 A - 37 - - 5 A - 40 A V A I L A B I L I T Y - H C - - ANS V IRGINIA SECTION,

P.O. BOX 1260, LYNCHBURG, VA. 24505; M F - - NTIS

NURC

9798 Date May 1980 020000 220000 Cost-Benefit Effects of Conversion to SI Units in Health

Physics. Eichholz, G.G.; Poston, J.W.; Fair, M.F.; Auxier, J.A. NUREG/CR-1419; O R N L / N U R E G - 6 8 A V A I L A B I L I T Y - N T I S ; GPO SALES PROGRAM,

DIV. OF TECHNICAL ' INFORMATION A N D DOCUMENT CONTROL, U.S. NUCLEAR REGU-LATORY COMMISSION, WASHINGTON, D.C. 20555

OARNL

9827 Date July 1979 020000 122100 122200 810000 ENDF/B Summary Documentation. Kinsey, R. (Comp.) BNL-NCS-17541(ED.3); ENDF-201(ED.3) AVAILABIL ITY-DEP. , NTIS, PC A22/MF A01 BROOKH

975 5 Date 1979 020000 Standards Activities Within X3 - the Computers and Infor-

mation Processing Community. Butler, M.K. CONF-790402,VOL.11, P P . 5 A - 2 1 - - 5 A - 3 0 A V A I L A B I L I T Y - H C - - A N S VIRGINIA SECTION,


ARGONN

975 6 ' Date 1979 020000 FORTRAN - Past, Present, and Future. Marshall, N.H. CONF- 790402,VOL.11, PP.5 A - 31 - - 5 A - 36 A V A I L A B I L I T Y - H C - - A N S VIRGINIA SECTION,


EDGERT

975 7 Date 1979 020000 Recommended Programming Practices to Facilitate the Por-

tability of Scientific Computer Programs.


Use in the UK Decay and Fission Product Yield Data Files.

Tobias, A. CEGB-RD/B/N-4423 AVAILABIL ITY-DEP. , NTIS (U.S. SALES ONLY),

PC A03/MF A01 ENGcAN

9839 Date January 16, 1980 020000 Shielding Benchmark Problems (I I ) . Tanaka, S.; Sasamoto, N.; Oka, Y.; Shin, K.; Tada, K.;

Nakazawa, M.; Nakamura, T.; Harima, Y.; Hirayama, H.; Furuta, Y.; Miura, T.; Yamauchi, M.; Yamano, N.; Hyodo, T.

JAERI -M-8686 ;,t A V A I L A B I L I T Y - D I V I S I O N OF TECHNICAL

INFORMATIONS JAPAN ATOMIC ^ENERGY RESEARCH INSTITUTE, T O K A I - M U R A , N A K A - G U N , I B A R A K I - K E N , JAPAN .;

JAPAN %

34

9997 Date August 1980 020000 329000 521130 795187 810000 TRX and UO/sub 2/ Benchmark Criticality Calculations

with S A M - C E . Beer, M.; Troubetzkoy, E.S.; Lichtenstein, H.; Rose, P.F. O R N L / R S I C - 4 4 , PP.157-167 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 M A A G

Neutron Cross Sections for Reactor Dosimetry - Review Papers. Summary Report.

Vlasov, M.F. (Ed.) IAEA-208, VOL.1, PP.1-49 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE IAEA

Sources'- Neutron - Fission or Reactor - Prompt

CATEGORY N U M B E R 111110

6510 Date 1976 020000 111110 111210 111220 122100 122200 810000


6583 Date 1976 010000 111110 121100 870092 870094 Theory of Nuclear Fission: A Review. Mosel, U. A N L - 7 6 - 9 0 , PP.3-30 A V A I L A B I L I T Y - N T I S G E R M A N

6590 Date 1976 111110 121100 870092 870094 What Happens to the Fission Process Above the 2nd- and

3rd- Chance Fission Threshold? Stewart, L.; Howerton, R.J. A N L - 7 6 - 9 0 , PP.398-414 A V A I L A B I L I T Y - N T I S ° L A L L

6761 Date May 1978 111110 122100 870090 Review and Combination of Experimental Results for Neu-

/ tron Emission per Fission of 232-Th. Gwin, R. O R N L / T M - 6 2 4 5 ; ENDF-262 A V A I L A B I L I T Y - N T I S $4.00 O A R N L

6808 Date 1978 010000 111110 122200 210000 421140 430000 511120

810000 $ * O ti

6809. Date 1978 010000 111110 410000 122200 511120 421140 770000

430000 Benchmark Neutron Fields for Reactor Dosimetry. Grundl, J.; Eisenhauer, C. IAEA-208, VOL.1, PP.53-104 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE

i

6813 Date 1978 010000 111110 870092 870098 A Review on Standard Fission Neutron Spectra of 235 -U

and 252-Cf. a

Knitter, H.H. IAEA-208, VOL.1, PP.183-195 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE BELGIU

o 6827 Date 1978 010000 020000 111110 111220 410000 Fast Neutron Standards at the PTB. Wagner, S.R. IAEA-208 , VOL.11, PP.15-27 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE G E R M A N

6831 Date 1978 111110410000 421130 421140 511120 Spectrum Characterization and Threshold Reaction Rate

Measurements in the Neutron Field of VIPER. McTaggart, M.H. (Ed.) IAEA-208, VOL.11, PP.77-88 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE E N G L A N

6832 Date 1978 111110 421130 421140 410000 511120 Several Studies~bf Neutron Standard Field in the Fast

Source Reactor " Y A Y O I " . Sekiguchi, A.; Nakazawa, M.; Kosako, T.; Wakabayashi,

H.; Akiyama, M. IAEA-208, VOL.11, PP.89-106

A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -HOUSE

J A P A N

6850 , Date 1978 111110 421130 421140 430000 On the Possibility of Unfolding Simultaneously Data from

Mult iple Foil, Proton Recoil and Other Neutron Spec-trometers by the S A N D - I I Type Unfolding Codes.

Najzer, M . I A E A - 2 0 8 , VOL.11, PP.411 -422 A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE Y U G O S L

A V A I L A B I L I T Y - U N I V E R S I T Y OF C A L I F O R N I A , LOS A L A M O S ' S C I E N T I F I C L A B O R A T O R Y , P.O. BOX 1663, LOS A L A M O S , N . M . 87545

L O A S L

8798 Date February 1979 111110 223000 329000 721100 721200 722100 620000

719AOO 422110 Reactor Cavity St reaming—The Problem and Engineer-

ing Solutions. Iott i , R.C.; Yang, T.L. ORNL/RSIC-43 ,PP.76-109 ;

A N S / S D -79/16,PP.76-109 A V A I L A B I L I T Y - N T I S EBASCO

6864 , Date March 1978 > 111110 410000 421140 713000 770000 810000 Fission Product arid Reactor. Dosimetry Studies at Coupled

Fast Reactivity Measurements Facility. Harker, Y.D.; Rogers, J.W.; Millsap, D.A. TREE-1259 ; E N D F - 2 6 6 A V A I L A B I L I T Y - N T I S $4.50 (i / / ^

DOE

8380 Date September 1978 111110 421130 423210 Measurement oj^the Neutron Leakage Spectrum and Dose

from the Viper Reactor. Delafield, H.J.; Holt, P.D.; Mullender, M.L. ; Kemshall,

C.D. H E A L T H P H Y S , 35(3), 471-480 ~ E N G L A N

8642 Date 1977 111110 421140 Neutron Flux Density Spectra of Interest to Reactor Neu-

tron Metrology. Zi jp, W.L.; Nolthenius, H.J.; Rieflfe, H.Ch. EUR-5667E/F .PT. I I , PP.468-683;

CONF-750935,PT. I I , PP.468-683 A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L PUBLICA-


N E T H E R

8730 . . Date March 1979 111110 870092 870094 870096 Summary of Fission Spectrum Workshop. Held at the

National Neutron Cross Section Center, Brookhaven National Laboratory.

Stewart, L. (Ch.) L A - 7 7 3 9 - C ; E N D F - 2 7 8

' 8 8 8 0 ' Date 1979 111110 330000 713000 Application of Integral Transport Theory with Linearly

Anisotropic Scattering to the Calculation of the Neutron Distribution in Finite Plate Arrays of Fast Reactors.

Boehme, R. D O E - T R - 7 1 ; K F K - 2 5 0 1 ( I N G E R M A N ) A V A I L A B I L I T Y - U S D O E T E C H N I C A L I N F O R M A -

T I O N CENTER, O A K RIDGE, T E N N . G E R M A N

9045 Date December 1978 111110 111220 422140 795254 Mul t i -Technique Characterization of Neutron Fields from

Moderated 252 -C f and 238-PuBe Sources. Griffith, R.V.; Slaughter, D.R.; Patterson, H.W.; Beach,

J.L.; Frank, E.G.; Rueppel, D.W.; Fisher, J.C. STI /PUB-471(VOL.2) ,PP.167-188;


ENERGY A G E N C Y , V I E N N A ( A U S T R I A ) L A L L

9107 Date June 1979 111110 020000 32AOOO 325000 521130 795134 795266

713000 793000 794000 S P E C T R A - I V , Benchmark Spectra Based on L I B - I V . Kidman, R.B. L A - 7 8 6 1 - M S A V A I L A B I L I T Y - N T I S L O A S L

9121 Date 1978 111110 111210 Compendium of Neutron Spectra in Crit ical i ty Accident

Dosimetry. Ing, H.; Makra, S.

36

TECH. REPORTS SERIES NO. 180 Rudstam, G. A V A I L A B I L I T Y - I N T E R N A T I O N A L ATOMIC IAEA-213, VOL.11, PP.567-626

ENERGY AGENCY, V IENNA $17.00 A V A I L A B I L I T Y - I A E A ' ( M F ONLY) CANADA '' SWEDEN

9122 Date May 1979 111110 421110 430000 713000 Neutron Spectrum Measurements in CFRMF 6Li Spec-

trometry. De Leeuw-Gierts, G.; De Leeuw, S.; Rogers, J.W.; John-

son, L.O. TfREE-1358; BLG-525 AVAILABILITY-NTIS $4.50 IDNEL


Dosimetry Calibration. ' (1

Schwartz, R.B.; Grundl, J.A. I \\ STI/PUB-471 (VOLT), PP.367-376;


9328 Date February 1979 111110 112110 420000 421200 511120 512120 810000 Measurements of the Free Field Radiation Environment at

the APRD Reactor. Schanzler, L.; Buchholz, F.W.; Ka i iM .H . ; Heimbach, C.R.;

Harrison, R.C. W W D NR.27 AVAILABIL ITY-WEHRWISSENSCHAFTLICHE

DIENSTSTELLE DER BUNDESWEHR FUR o ABC-SCHUTZ, D 3042 MUNSTER, GERMANY GERMAN

Sources - Neutron - Fission - Delayed


8140 Date September 1, 1978 010000 111120 420000 424000 A Review of the Delayed Fission Neutron Technique. Binney, S.E.; Scherpelz, R.I. NUCL. INSTRUM. METHODS, 154(3), 413-431 U - O R

8420 Date August 1978 010000 111120 870092 Status of Delayed Neutron Data.

8918 Date May 1979 111120 870092 Calculated Time-Dependent Delayed Neutron Group

Yields for Thermal - Neutron Fission of Uranium - 235. Alexander, D.R.; Peng, Y.K. NUCL. SCL ENG., 70(2), 184-191 U - N B

Sources - Neutron - Fission - Weapon


8526 Date 1978 -111130 The . Effect of Pu-240 on Neutron Lifetime in Nuclear

Explosives. Sahin, S. ° ANN. NUCL. ENERGY, 5(2), 55-58 TURKEY

Sources - Neutron - Reaction - 14 MeV & D,T Fusion


64241 Date Dec. 1977 111210 710000 Shield Analyses for Intense 2.2pJ(14-MeV) Neutron

Sources. ,, Battat, M.E.; Dudziak, D.J. CONF-770401, PP.520-526 AVAILABIL ITY-SCIENCE PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 LOASL

6510 Date 1976 020000 111110 111210 111220 122100 122200 810000


37

6623 Date 1977 111210 210000 32A000 795266 717000 810000 521130 Neutron Spectra Characteristics for the Intense Neutron

Source, INS. Battat, M.; Dierckx, R.; Emigh,~C.R. LA-UR-77-1054; CONF-770523-2 AVAILABILITY-DEP., NTIS LOAS1T

6635 Date January 1978 111210 111220 210000 717000 870023 870029 870041 Exploratory Experiments Comparing Damage Effects of

High-Energy Neutrons and Fission-Reactor Neu-trons in Metal.

Mitchell, J.B. UCRL-52,388 AVAILABILITY-LAWRENCE LIVERMORE LAB.,

CALIFORNIA UNIV. LALL

67;31 Date August 15, 1977 010000 11V!210 111220 High Energy and High Intensity Neutron Sources. Ullmaier, H. (Ed.) NUCL. INSTRUM. METHODS, 145(1), 1-218 GERMAN

UWFDM-250 AVAILABILITY-FUSION RESEARCH PROGRAM,

NUCLEAR ENGINEERING DEPT., UNIVERSITY OF WISCONSIN, MADISON, WISCONSIN 53706

U-WI

8428 Date October 1978 ^ 111210 329000 32AOOO 422110 511120 870003 C81000 Tritium Production in a Sphere of 6-LiD Irradiated by

14-MeV Neutrons. Hemmendinger, A.; Ragan, C.E.; Shunk, E.R.; Ellis, A.N.;

Anaya, J.M.; Wallace, J.M. LA-7310 ^ AVAILABILITY-NTIS LOASL


Problems of Fusion Research. Vol.1. Lubell, M.S.; Whitmire, C.,Jr. (Eds.) a CONF-771029,VOL.I AVAILABILITY-IEEE SERVICE CENTERfSINGLE

PUBLICATION SALES DEPT., 445 HOES LANE, PISCATAWAY, N.J. 08854

OARNL

6769 Date March 1978 010000 111210 111220 210000 717000 810000 Intense Sources of Fast Neutrons. Barschall, H.H.

; UWFDM-231 AVAILABILITY-FUSION RESEARCH PROGRAM,


U-WI


Problems of Fusion Research. Vol.11. Lubell, M.S.; Whitmire, C.,Jr. (Eds.) CONF-771029,VOL.11 AVAILABILITY-IEEE SERVICE CENTER, SINGLE


OARNL

7089 Date March 1977 111210 717000 ORNL Fusion Power Demonstration Study: Interim Report. Steiner, D.; Bettis, E.S.; Huxford, T.J.; McAfee, W.J.;

McCoy, H.E.; Mense, A.T.; Reid, R.L.; Scott, J.L.; 'Shannon, T.E.; Stoddart, W.C.T.; Watts, H.L.; Wells, W.M.; Werner, R.W.; Wiffen, F.W.

ORNL/TM-5813 AVAILABILITY-NTIS $5.50 OARNL

8564 Date 1977 111210 329000 531000 532000 717000 795203 £ Nuclear Heat Deposition in Cryosorption Pumps of a Fusion

Reactor. Iida, H.; Ide, T.; Seki, Y. CONF-£71029,VOL.11, PP.1658-1662 f \ AVAILABILITY-IEEE SERVICE CENTER',.SINGLE


JAPAN

8043 Date June 1978 111210 210000 717000 810000 The Newest Frontier in Radiation Damage Research -

Laser Fusion Reactors. Kulcinski, G.L. 0

? Ui 8567 Date 1977

111210 223000 521130 522130 717000 795217 795254 793000 810000

Structure Activation in an Experimental Power Reactor.

38

Smith, R.D.; Parish, T.A. CONF-771029,VOL.11, PP.1718-1722 AVAILABILITY-IEEE SERVICE CENTER, SINGLE

PUBLICATION SALES DEPT.. 445 HOES LANE, PISCATAWAY, N.J. 08853

U-TX

8727 Date 1977 111210 329000 717000 795203 810000 Three-Dimensional Analysis of the Effects of Penetrations

on Radiation Shielding of a Tokamak Fusion Reactor. Ide, T. JAERI-M-7360 AVAILABILITY-JAPAN ATOMIC ENERGY

RESEARCH INSTITUTE, TOKAI, JAPAN JAPAN

8810 Date February 1979 111210 717000 Maximum Neutron Yields in Experimental Fusion Devices. Jassby, D.L. PPPL-1515 „ AVAILABILITY-NTIS U-NJ

8860 Date September 1978 111210 551110 717100 870092 810000 Neutronic Studies of a 233-U Fusion Breeder. Hansen, L.F.; Maniscalco, J.A. CONF-780921, PP.772-777 'XVAILABILITY-OECD, 2, RUE ANDRE-PASCAL,

75775 PARIS CEDEX 16, FRANCE LALL

8867 Date September 1978 111210 122310 32AOOO 521130 795254 717100 810000

870092 o Reproduction of the Weale Experiment Results with Modi-

fied ENDF/B-IV U-238 Data. Segev, M.; Krumbein, A. CONF-780921, PP.1028-1032 AVAILABILITY-OECD, 2, RUE ANDRE-PASCAL,

IO775CPARIS CEDEX 16, FRANCE ISRAEL

8868 Date September 1978 111210 810000 Analysis of Neutrons Emitted from 14 MeV» Neutron

Induced Reactions. Pcarlstein, S. CONF-780921, PP.1059-1065 AVAILABILITY-OECD, 2, RUE ANDRE-PASCAL,

75775 PARIS CEDEX 16, FRANCE

BROOKH

8908 Date May 26, 1978 111210 329000 717000 717100 810000 Nuclear Design of the LLL-GA U/sub 3/Si Blanket. Lee, J.D. | UCRL-80588; CONF-780508-27 AVAILABILITY-DEP., NTIS LALL

8926 Date May 1979 111210 32A000 511110 717000 Feasibility Study to Produce First Wall Fusion Reactor

Spectra Around a 14-MeV Neutron Point Source. Battat, M.E.; Dierckx, L.A.; Emigh, C.R. NUCL. TECHNOLOGY, 43(3), 338-348 LOASL o

8932 Date January 1979 010000 111210 121100 210000 521130 717000 795217


Structural Materials. Jarvis, O.N. AERE-R-9298 AVAILABILTTY-H.M.S.O. ° ENGLAN

8936 : Date May 1978 010000 M1210 717000 Magnetic Fusion Program in the United States: An Over-

view and Perspective. Clarke, J.F. CONF-780508,VOL. 1, PP.1 -18, AVAILABILITY-DEP., NTIS /O DOE

893(7 K Date May 1978 010000 111210 717000 Fusion - The Programme in the U.K. - and Other

Thoughts. Carruthers, R. t!

CONF-780508,VOL. 1, PP.19-27 AVAILABILITY-DEP., NTIS ENGLAN

8938 Date May 1978 010000 111210 717000 Development on Fusion Reactors in Japan. Mori, S. CONF-780508,VOL.I, PP.28-37 AVAILABILITY-DEP., NTIS

39 c.

JAPAN

8939 '.'Date May 1978 010000 111210 717000 The JET Project - Progress in Construction and Manage-

ment. Bertolini, E. " CONF-780508,VOL. 1, PP.38-49 AVAILABILITY, \ DEP., NTIS ENGLAN \r

8940. Date* May 1978 010000 111210 717000 Advanced Fusion Concepts Program. Dove, W.F. CONF-780508,VOL. 1, PP.51-57 AVAILABILITY-DEP., NTIS DOE

0

(f%

8941 Date May 1978 010000 111210 717000 , " Alternative Fusion Concepts: Engineering and Utility Con-

siderations. Gough, W.C.; Amherd, N.A. » CONF-780508,VOL.1, PP.58-63 AVAILABILITY-DEP.,NTIS ° >•> <-DOE

8942 Date May 1978 010000 111210 717000 Tandem Mirror Reactor. u 0 Moir,' R.W.; Barr, W.L.; Bender, D.J.; Carlson, G.A.; Dex-

ter, W.L.; Doggett, J.N.; Fink, J.H.; Hamilton, G.W.; Lee, J.D.; Logan, B.G.; Neef; W.S.,Jr.; Peterson, M.A.; Rensink, M.E.

CONF -780508,VOL. 1, PP.64-73 AVAILABILITY-DEP., NTIS L ALL °

8943 Date May 1978 010000 111210 717000^ The Elmo Bumpy Torus (EBT) Reactor - A Status Report. Uckan, N.A.; Bettis, E.S.; Dandl, R.A.; Hedrick, C.L.; San-

toro, R.T.; Watts, H.L.j Yeh, H.T. CONF-780508,VOL.1, PP.74-82 AVAILABILITY-DEP., NTIS OARNL

8944 Date May 1978 010000 111210 717000 r The Reversed-Field Multiple Mirror Concept. Steinhauer, L.; Grossmann, W.; Seyler, C.E.

CONF-780508.VOL.1, PP.83-89 AVAILABILITY-DEP., NTIS MASN

8945 Date tilay 1978 010000 111210,717000 Synfuels Production from Fusion Reactors. ° Fillo, J.A.; Powell, J.R.; Steinberg, M.; Salzano, F.; Benena-

ti, R.; Dang, V.; Fogelson, S.; Isaacs, H.; Kouts, H.; Kushner, M.; Lazareth, O.; Maieski, S.; Makowitz, H.;

0 Sheehan, T.V. o CONF-780508,VOL. 1, PP.193-202 AVAILABILITY-DEP., NTIS U - N Y

^ u 8950 Date May 1978

111210 122310 32AOOO 521130 522130 620000 717000 A Minimum-Thickness Blanket/Shield with Optimum

Tritium Breeding and Shielding Effectiveness. Gerstl, S.A.W. CONF-780508,VOL. 1, PP.269-278 AVAILABILITY-DEP., NTIS LOASL

8951 V : . Date May 1978 111210 210000 717000 870006 870014 An Assessment of Carbon and Silicon Carbide as First Wall,

Materials in Inertial Confinement Fusion Reactors. Hopkins, G.R.; Price, R.J.; Bullock, R.E.; Dalessandro, J. A.;

Hovingh, J. Q CONF-780508,VOL.l, PP.324-333 0 AVAILABILITY-DEP., NTIS GEAC '

ft (3

8952 Date MayT978 111210 210000 717000 EWLTB - A Mathematical Mcdel to Calculate the Life-

time of the Fusion Reactor First Wall. » Daenner, W.; Raeder, J. CONF-780508,VOL.l, PP.347-356 ' AVAILABILITY-DEP., NTIS GERMAN o

/ 0 8956 Date May 1978 .

010000 111210 210000 717000 810000 v„ Materials Program for Magnetic Fusion Energy. « Zwilsky, K.M.; Cohen, M.M.; Finfpeld, G.R.-Reuther, T.C CONF - 780508,VOL. 1, PP.549-553 v^i" AVAILABILITY-DEP., NTIS > DOE

40

8960 Date May 1978 111210 717000 810000 "NUMAK" An Attractive Medium Field, Medium Size,

Conceptual Tokamak Reactor. Conn, R.W.; Kulcinski, G.L.; Maynard, C.W. CONF-780508,VOL.2, PP.1049-1059 AVAILABILITY-NTIS ' U-WI

8979 Date January 15, 1979 111210 717000 887000 Actinide Cross Section Data and Inertial Confinement

Fusion for Long Term Waste Disposal. Meldner, H. UCRL-82177; CONF-781174-6 AVAILABILITY-DEP., NTIS LALL

8999 Date July 1979 111210 329000 The Particle Spectrum to be Expected from a D - T Plasma.

(Tech. Note) Liskien, H. NUCL. SCL ENG., 71(1), 5?-59 BELGIU

9016 Date January 1979 111210 122310 717000 Estimated Target Accuracies for Neutronic Responses in

Fusion Reactors. Verschuur, K.A. ECN-79-012 AVAILABILITY-STICHTING ENERGIEONDER-

ZOEK CENTRUM NEDERLAND (ECN), POSTBUS 1, 1755 ZG PETTEN (NH)

NETHER

9121 Date 1978 111110 111210 Compendium of Neutron Spectra in Criticality Accident

Dosimetry. Ing, H.; Makra, S. TECH. REPORTS SERIES NO. 180 AVAILABILITY - INTERNATIONAL ATOMIC

ENERGY AGENCY, VIENNA $17.00 CANADA

9252 Date October 1979 111210 122310 112400 112500 329000 421130 421200 Neutron and Gamma-Ray Spectra from 232-Th,

235-U, 238-U, and 239-Pu after Bombardment with 14-MeV Neutrons.

Hansen, L.F.; Wong, C.; Komoto, T.T.; Pohl, B.A.; Gold-berg, E.; Howerton, R.J.; Webster, W.M.

NUCL. SCI. ENG., 72(1), 35-51 LALL

9421. 1' Date 1977 111210 620000 710000 717000 810000 Neutral Beam System for an Ignition Tokamak. Fasolo, J.; Fuja, R.; Jung, J.; Moenich, J.; Norem, J.; Praeg,

W.; Stevens, H. CONF-771029-177 AVAILABILITY-NTIS, PC A02/MF A01 ARGONN

9427 Date August 1979 111210 111220 210000 717000 810000 Fusion Technology Development. Coffman, F.E.(Dir.) DOE/ET-Ol 16/1 AVAILABILITY-U.S. DOE, OFFICE OF FUSION

ENERGY, DIVISION OF DEVELOPMENT AND TECHNOLOGY, WASHINGTON, D.C. 20545

DOE

9454 -Date November 1979 010000 111210 14 MeV d,t Sources. Barschall, H.H. UWFDM-331 AVAILABILITY-FUSION ENGINEERING PRO-

GRAM, NUCLEAR ENGINEERING DEPT., UNIVERSITY OF WISCONSIN, MADISON WI 53706

U - W I

„ 0 9486 Date 1979 010000 111210 111220 210000 717000 810000 Irradiation Sources for Fusion Materials Development. Holmes, J.J.; Straalsund, J.L. CONF-790125, PT.A, PP.447-451; J. NUCLEAR

MATER., 85 AND 86, AVAILABILITY-NORTH-HOLLAND PUBLISH-

ING COMPANY - AMSTERDAM HANFOR

9780 Date December 1979 010000 111210 122100 717000 810000 Nuclear Data Requirements of the Magnetic Fusion Power

Program of the United States of America. (Introductory Paper No. 1)

Head, C.R. IAEA-TECDOC-223, PP.1-7 AVAILABILITY-MF ONLY - INIS MICROFICHE

CLEARINGHOUSE, IAEA, WAGRAMER-STRASSE 5, P.O. BOX 100, A-1400 VIENNA, AUSTRIA

<11

DOE

9786 Date December 1979 010000 111210 717100 810000 122100 Neutron Data for Hybrid Reactor Calculations. (Review

Paper NoA6) Markovskii, D.V.; Shatalov, G.E. IAEA-TECDOC-223, PP.111 -118 AVAILABILITY-MF ONLY - INIS MICROFICHE


RUSSIA

9787 Date December 1979 010000 111210 312000 32A000 717000 810000 Cross-Section Sensitivity and Uncertainty Analysis for

Fusion Reactors - A Review. (Review Paper No.Bl) Dudziak, D.J. IAEA-TECDOC-223, PP.121-138 AVAILABILITY-MF ONLY - INIS MICROFICHE


LOASL

9788. Date December 1979 010000 111210 122100 123000 717000 810000 Theoretical Approach to Nuclear Data Required for Fusion

Reactor Calculations. (Review Paper No.B2) Seeliger, D. IAEA-TECDOC-223, PP.139-152 AVAILABILITY-MF ONLY - INIS MICROFICHE


GERMAN

9791 Date December 1979 010000 111210 122100 717000 810000 Status of 14-MeV Neutron Cross Section Data. (Review

Paper N0.B6) Csikai, J. IAEA -TECDOC - 223, PP. 199 - 222 0

AVAILABILITY-MF ONLY - INIS MICROFICHE CLEARINGHOUSE, IAEA, WAGRAMER-STRASSE 5, P.O. BOX 100, A-1400 VIENNA, AUSTRIA

HUNGAR

10154 Date September 1980 111210 717000 Neutron Flux Measurements Around PLT.

o Zank, G.; et al. PPPL-1696 AVAILABILITY-PRINCETON UNIVERSITY, NEW

JERSEY, PLASMA PHYSICS LABORATORY U - N J

10155 Date August 1980 111210 717000 Neutron Spectra from Beam-Heated Fusion Plasmas. SchefTel, J.; et al. TRITA-PFU-80-09 AVAILABILITY-ROYAL INSTITUTE OF TECH-

NOLOGY, STOCKHOLM, SWEDEN, PLASMA PHYSICS AND FUSION RESEARCH

SWEDEN

Sources - Neutron - React ion - Spectra l

C A T E G O R Y N U M B E R 111220

6510 Date 1976 020000 111110 111210 111220 122100 122200 810000

845000 Basic Physical Data for Neutron Dosimetry. Broerse, J.J. (Ed.) EUR-5629 AVAILABILITY-INIS NETHER

a

6533 Date February 1978 111220 113100 220000 632300 717000 Health Physics Aspects of Nuclear Radiations from Deute-

rium Beam Injectors. Kim, J. ORNL/TM-6189 AVAILABILITY-NTIS $4.50 OARNL

6599 Date 1977 010000 111220 717500 810000 A Brief History of the MTA Project. Van Atta, C.M. CONF-770107, PP.9-29 AVAILABILITY-NTIS LALL

6600 Date 1977 010000 111220 717500 810000 Linear Accelerator Breeder for Energy Security. Steinberg, M. CONF-770107, PP.41-68

42

AVAILABILITY-NTIS BROOKH

6601 Date 1977 010000 111220 717500 810000 High Current Linear Accelerators and Nuclear Power. TunniclifTe, P.R. \ CONF-770107, PP.69-84 AVAILABILITY-NTIS CANADA \\

6602 :> Date 1977 010000 111220 717500 810000 Analysis of Accelerator Breeder Concepts with LMFBR,

GCFR, and Molten Salt-Type Blankets. Mynatt, F.R. CONF-770107, PP.85-106 AVAILABILITY-NTIS, OARNL



Mitchell, J.B. UCRL-52,388 AVAILABILITY-LAWRENCE LIVERMORE LAB.,

CALIFORNIA UNIV. LALL

6731 Date August 15, 1977 010000 111210 111220 High Energy and High Intensity Neutron Sources. Ullrnaier, H. (Ed.) NUCL. INSTRUM. METHODS, 145(1), 1-218 GERMAN

6769 Date March 1978 010000 111210 111220 210000 717000 810000 Intense Sources of Fast Neutrons. Barschall, H.H. UWFDM-231 AVAILABILITY-FUSION RESEARCH PROGRAM,


U - W I

6827 010000 020000 111110 111220 410000 Fast Neutron Standards at the PTB. Wagner, S.R.

Date 1978

IAEA-208, VOL.11, PP.15-27 AVAILABILITY-INIS MICROFICHE CLEARING-

HOUSE GERMAN

7095 Date September 1976 111220 122310 329000 511110 795203 870008 Analysis of a Neutron Scattering and Gamma-Ray Pro-

duction Integral Experiment on Oxygen for Neutron Energies from 1 to 15 MeV.

Cramer, S.N.; Oblow, E.M. ORNL/TM-5535 AVAILABILITY-NTIS $4.50 OARNL

8022 Date May 1978 111220 220000 329000 760000 795161 Calculation of Dosimetry Parameters for Fast Neutron

Radiotherapy. Wells, A.H. LA-7288-T AVAILABILITY-NTIS $13.25 LOASL

8485 Date September 1978 111220 122100 421140 717000 795112 810000 210000 Extrapolated Neutron Activation Cross Sections for Dosim-

etry to 44 MeV. Greenwood, L.R. ANL/FPP/TM-115 AVAILABILITY-NTIS $4.50 ARGONN

8752 Date April 1979 111220 Diagnostic Neutron Spectra from Deuterons on Several

Materials. Lefevre, H.W.; Davis, J.C.; Anderson, J.D. NUCL. SCI. ENG., 70(1), 60-65 LALL

8808 Date April 1979 111220 122100 810000 Status of ENDF/B-V Neutron Emission Spectra Induced

by 14-MeV Neutrons. Hetrick, D.M.; Larson, D.C.; Fu, C.Y. ORNL/TM-6637; ENDF-280 AVAILABILITY-NTIS $4.50 OARNL

43

8852 Date September 1978 010000 111220 870006 870012 870013 870014 Neutron Yields from (alpha,n) Reactions in the Light Ele-

ments. West, D.; Sherwood, A.C. CONF-780921, PP.610-614 AVAILABILITY-OECD, 2, RUE ANDRE-PASCAL,

75775 PARIS CEDEX 16, FRANCE ENGLAN

8853 Date September 1978 010000 111220 870095 Neutron Production from (alpha,n) Reactions in Actinide

Oxides. Lees, E.W. CONF-780921, PP.615-620 AVAILABILITY-OECD, 2, RUE ANDRE-PASCAL,


8863 Date September 1978 111220 410000 The Rutherford Laboratory Spallation Neutron Source. Manning, G. CONF-780921, PP.829-847 AVAILABILITY-OECD, 2, RUE ANDRE-PASCAL,


8901. Date May 1979 111220:717500 870090 870092 870094 Concept Evaluation of a Nuclear Design for Electronuclear

Fuel Production: Evaluation of ORNL's Proposed TMF-ENFP.

Burns, T.J.; Bartinc, D.E.; Renier, J.P. ORNL/TM-6828 AVAILABILITY-NTIS $4.50 OARNL

8986 Date May 1979 111220 750000 Leakage Neutrons Produced by 10 MeV Medical Accelera-

tors. McGinley, P.H.; Fenn, J.O.; White, T.A.,Jr. HEALTH PHYS, 36(5), 635-637 U-GA

8994 Date April 1, 1979 111220 329000 Monte Carlo Calculation of d-Be Neutron Yields. Cristenson, D.; McNaughton, M.W.; Jungerman, J.A. NUCL. INSTRUM. METHODS, 160(3), 499-502 U-CA

8996 Date July 1979 111220 Neutron Yields from Alpha-Particle Bombardment. Bair, J.K.; del Campo, J.G. NUCL. SCI. ENG, 71(1), 18-28 OARNL

9002 Date July 1979 111220 113100 717000 D-D Neutron and X-Ray Yields from High-Power Deu-

terium Beam Injectors. Kim, J. NUCL. TECHNOLOGY, 44(2), 315-321 OARNL

9045 Date December 1978 111110 111220 422140 795254 Multi-Technique Characterization of Neutron Fields from

Moderated 252-Cf and 238-PuBe Sources. Griffith, R.V.; Slaughter, D.R.; Patterson, H.W.; Beach,

J.L.; Frank, E.G.; Rueppel, D.W.; Fisher, J.C. STI/PUB - 471 (VOL. 2),PP. 167 -188;

CONF-771209-P2,PP. 167-188; ° AVAILABILITY-INTERNATIONAL ATOMIC

ENERGY AGENCY, VIENNA (AUSTRIA) LALL

9188 Date October 1979 111220 421130 423135 423120 511120 717000 D-D Neutron Measurements on a 40-kV, 60-A Neutral

Beam Test Facility. Kim, J.; Mihalczo, J.T. ORNL/TM-7016 AVAILABILITY-NTIS OARNL

9286 Date 1978 111220 Neutron Production with Van de GraafT Accelerators and

Flux Measurements in the Energy Range 0.1 - 20 MeV.

Grenier, G. EUR - 5848,PP.291-301; CONF- 770597,PP.291 - 301 AVAILABILITY-OFFICE FOR OFFICIAL PUBLICA-

TIONS OF THE EUROPEAN COMMUNITIES, BOITE POSTALE 1003 - LUXEMBOURG ISBN 92-825-0256-2

FRANCE

9287 Date 1978 0 111220 760000

Comparison of High Energy Neutron Sources for Radiation Therapy.

44

Grant, W.H.; Almond, P.R.; Otte, V.A.; Anderson, M.D.; Smathers, J.B.

EUR-5848,PP.303-314; CONF-770597.PP.303-314 AVAILABILITY-OFFICE FOR OFFICIAL PUBLICA-


U-TX

9291 Date 1978 111220 220000 760000 Radiation Quality Studies in Mixed Neutron-Gamma

Fields. Menzel, H.G.; Waker, A.J.; Griilmaier, R.; Bihy, L.; Hart-

mann, G. EUR-5848,PP.481 -497; CONF-770597,PP.481 -497 AVAILABILITY-OFFICE FOR OFFICIAL PUBLICA-


GERMAN

9427 Date August 1979 111210 111220 210000 717000 810000 Fusion Technology Development. Coffman, F.E.(Dir.) DOE/ET-Ol 16/1 AVAILABILITY-U.S. DOE, OFFICE OF FUSION

ENERGY, DIVISION OF DEVELOPMENT AND TECHNOLOGY, WASHINGTON, D.C. 20545

DOE

Pottmeyer, E.W.,Jr. CONF-790125, PT.A, PP.463-465; J. NUCLEAR



9489 Date 1979 111220 210000 717000 Measurements and Calculations of Neutron Spectra from 35

MeV Deuterons on Thick Lithium for the FMIT Facili-ty-

Johnson, D.L.; Mann, F.M.; Watson, J.W.; Ullmann, J.; Wyckoff, W.G.

CONF-790125, PT.A, PP.467-471; J. NUCLEAR MATER., 85 AND 86,

AVAILABILITY-NORTH-HOLLAND PUBLISH-ING COMPANY - AMSTERDAM

HANFOR

9490 Date 1979 111220 122100 521230 717000 810000 Integral Tests of Nuclear Activation Cross Sections for

Be(d,n) Sources, E /sub d / = 14- -40 MeV. Greenwood, L.R.; Heinrich, R.R. CONF-790125, PT.A, PP.473-477; J. NUCLEAR

MATER., 85 AND 86, AVAILABILITY-NORTH - HOLLAND PUBLISH-

ING COMPANY - AMSTERDAM ARGONN

9443 Date 1977 111220 210000 717000 810000 Jet Target Intense Neutron Source. Meier, K.L. LA-UR-77-2398; CONF-771029-38 AVAILABILITY-NTIS PC A02/MF A01 LOASL

9486 Date 1979 010000 111210 111220 210000 717000 810000 Irradiation Sources for Fusion Materials Development. Holmes, J.J.; Straalsund, J.L. CONF-790125, PT.A, PP.447-451; J. NUCLEAR



9488 Date 1979 010000 111220 210000 410000 717000 The Fusion Materials Irradiation Test Facility at Hanford.

9493 Date 1979 111220 210000 717000 810000 Spatial Variations of Damage Parameters in FMIT and

Their Implications. Schiffgens, J.O.; Simons, R.L.; Mann, F.M.; Carter, L.L. CONF-790125, PT.A, PP.491-495; J. NUCLEAR

MATER., 85 AND 86, AVAILABILITY -NORTH - HOLLAND PUBLISH-


9894 Date February 1980 111220 329000 Slow Neutron Leakage Spectra from Spallation Neutron

Sources. Das, S.G.; Carpenter, J.M.; Prael, R.E. ANL-80-27 AVAILABILITY-NTIS, PC A05/MF A01 ARGONN

45

Sources - Neutron - Reaction - Photoneutron (in shield)


8962 Date April 1979 111110 111600 210000 521230 719A00 795254 861000

793000 Measurement and Analysis of Gamma Ray Induced Con-

tamination of Neutron Dosimetry Procedures Used for Reactor Pressure Vessel Applications. '

Simmons, G.L. EPRI-NP-1056 AVAILABILITY - SCIENCE APPLICATIONS,

INCORPORATED, 1200 PROSPECT ST., LA JOLLA, CALIFORNIA 92038

SCA

9124 Date June 1979 111600 810000 \ \ Atlas of Photoneutron Cross Sections Obtained With Mon-

oenergetic Photons. Supplement. \ . Berman, B.L. \ UCRL - 78482 - SUPPLEMENT (PREPRINT) AVAILABILITY-LAWRENCE LIVERMORE LABO-

RATORY, UNIVERSITY OF CALIFORNIA, LIVERMORE, CALIFORNIA 94550

LALL

Sources - Neutron - Mixed Oxide Fuels and Spent Fuel


MacDonald, H.F.; Nair, S. NUCL. TECHNOLOGY, 42(3), 353-ENGLAN

361

Sources - Gamma-Ray - Discrete Energies (calculation)

C A T E G O R Y N U M B E R 112B00 o

8215 Date September 1978 112B00 121200 329000 820000 A Monte Carlo Code (PHOEL) for Generating Initial Ener-

gies of Photoelectrons and Compton Electrons Produced by Photons in Water.

' Turner, J.E.; Modolo, J.T.; Sordi, G.M.A.A.; Hamm, R.N.; Wright, H.A.

ORNL/TM-6515 AVAILABILITY-NTIS $4.00 OARNL

9126 Date 1979 U2B00 121200 810000 Energy and Angular Distribution of Secondary Particles in

the Detection Media After the Interaction of Ionizing Radiation. Part One.

Okta, L.; Petr, I. UVVVR-6 AVAILABILITY-INSTITUTE FOR RESEARCH,

PRODUCTION AND USES OF RADIOISOTOPES, PRAGUE 7, PRISTAVNI 24, CZECHOSLOVAKIA

CZECHO

6466 Date Dec. 1977 111700 719B00 795203 887000 Calculations of Neutron Radiation Levels from HTGR

Spent Fuel. Sund, R.K.; Engholm, B.A.; Su, S. w CONF-770401, PP.865-872 AVAILABILITY-SCIENCE PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 GEAC

8757. Date March 1979 111700 112940 223000 230000 Radiological Implications of Plutonium Recycle and the Use

of Thorium Fuels in Thermal Power Reactor Operations. (Tech. Note)

Sources - Gamma-Ray - Fission - Prompt



the APRD Reactor. Schanzler, L.; Buchholz, F.W.; Kazi, A.H.; Heimbach, C.R.;

Harrison, R.C. WWD NR.27 AVAILABILITY - WEHRWISSENSCH AFTLICH E

> DIENSTSTELLE DER BUNDESWEHR FUR ABC-SCHUTZ, D 3042 MUNSTER, GERMANY

GERMAN

46

Sources - Gamma-Ray - Fission-Product-Decay (including yields)


6343 Date Sept.-Oct. 1977 010000 112120 532000 A Review of Short-Term Fission-Product-Decay Power. Bjerke, M.A.; Holm, J.S.; Shay, M.R.; Spinrad, B.I. NUCL. SAFETY, 18(5), 596-616 OARNL

< , 6410 Date Dec. 1977 112120 223000 719C00 The Contribution of Fission Products to Radiation Fields in

a Pressurized Heavy Water Reactor. Neil, B.C.J. CONF-770401, PP.401-408 AVAILABILITY-SCIENCE PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 CANADA

6412 Date Dec. 1977 112120 887000 Prediction of Fission Product and Actinide Levels in Irradi-

ated Fuel and Cladding. Burstall, R.F.; Thornton, D.E.J. CONF-770401, PP.416-424 AVAILABILITY-SCIENCE PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 ENGLAN

6469 Date Dec. 1977 112120 423250 532000 719A00 Spatial Distribution of Fission Product Energy. Johnson, W.R.; Bass, R.B.; Littig, G.A.; Robinson, F.L.;

Bracke, T.P. CONF-770401, PP.889-896CV AVAILABILITY-SCIENCE PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 0 U-VA

6514 Date September 1977 111110 112120 713000 870093 Fast Reactor Fission Yields for 237-Np. Maeck, W.J.; Emel, W.A.; Erikson, A.L.; Delmore, J.E.;

Meteer, J.W. ICP-1050-3 AVAILABILITY-DEP., NTIS ALCC

6608 Date February 1978 112120 532000 795137 795217 The Calculation of the Decay Heat of Fission Products from

Exact Relations. Final Report (Research Project 230). Volume 2.

Grossman, L.M.; Stein, M. EPRI-NP-616, VOL.2 AVAILABILITY-UNIVERSITY OF CALIFORNIA,

BERKELEY, CALIFORNIA EPRI

6638 Date 1977 112120 121100 870092 New Possibilities of Calculating Independent Fission Prod-

uct Yields. Valenta, V. ZJE-207 AVAI LABILITY-SKODA WORKS, NUCLEAR

POWER CONSTRUCTION DIVISION, INFOR-MATION CENTRE, PLZEN, CZECHOSLOVAKIA

CZECH O '

6650 Date April 1978 112120 Modeling the Effect of Fission Product Capture on Reactor

Decay Power. (Tech. Note) Spinrad, B.I.; Tripathi, A. NUCL. SCI. ENG., 66(1), 140-141 U-OR

6674 ,. . Date November 1976 122100 112120 713000 Intercomparison of Recent Evaluations for the Capture

Cross Sections of Some Fission-Product Nuclides. Gruppelaar, H.; Janssen, A.J.; Dekker, J.W.M. ECN-12 AVAILABILITY-STICHTING ENERGIEONDER-

ZOEK CENTRUM NEDERLAND, PETTEN NETHER

6696 Date April 1978 111110 112120 221000 532000 422200 430000 794000

870094 Fission-Product Energy Release for Times Following Ther-

mal - Neutron Fission of 239 - Pu Between 2 and 14000 Seconds.

Dickens, J.K.; Emery, J.F.; Love, T.A.; McConnell, J.W.; Northcutt, K.J.; Peelle, R.W.; Weaver, H.

ORNL/NUREG-34 AVAILABILITY-NTIS S6.00 OARNL

47

, 6743 Date May 1977 010000 112120 The Status of Fission Product Yield Data (FPND) in 1977. ( } Cuninghame, J.G. A E R E - R - 8 7 5 3 A V A I L A B I L I T Y - H . M . S . O , PRICE POUND2.50 E N G L A N

6747 Date February 1978 112120 532000 870092 A Calorimetric Measurement of Decay Heat from 2 3 5 - U

Fission Products from 10 to 10**5 Seconds. Schrock, V.E.; Grossman, L.M. ; Prussin, S.G.; Sockalingam,

K.C.; Nuh, F.; Fan, C - K . ; Cho, N.Z.; Oh, S.J. E P R I - N P - 6 1 6 , V O L . l A V A I L A B I L I T Y - U N I V E R S I T Y OF C A L I F O R N I A ,

BERKELEY, CAL IF . 94720 EPRI

6750 Date March 1978 112120 870092 Nuclear Physics Constants of Gamma - Emitt ing Isotopes in

the Technological Environment of Reactors. Nesterov, B.V. I N D C ( C C P ) - 1 1 0 / L N P A V A I L A B I L I T Y - I A E A " I A E A

6817 Date 1978 010000 112120 713000 Status of Fission Product Yields Required for Fast Reactor

Dosimetry. Lammer, G.; Lammer, M. I A E A - 2 0 8 , VOL. I , PP.301-318 A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE B E L G I U

6841 Date 1978 112120 421200 512220 870092 870098 Fission Product Yield Ratios for Uranium-235 Fission by

Thermal and Cal i fornium-252 Neutrons. Debertin, K. I A E A - 2 0 8 , VOL.11, PP.261 -263 A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE G E R M A N

6858 o. Date June 1978 112120 112730 532000° 719A00 870092 Fission Product Source Terms for the, L W R

Loss-of-Coolant Accident: Summary Report. Lorenz, R.A.; Collins, J.L.; Malinauskas, A.P.

NUREG/CR-0091 ; O R N L / N U R E G / T M - 2 0 6 A V A I L A B I L I T Y - N T I S O A R N L

6874 Date June 1978 112120 A General Correlation for Independent Fission Product

Yield Uncertainties. (Tech. Note) Spinrad, B.I.; Wu, C.H. NUCL. SCI. ENG., 66(3), 421-424 U - O R

6903 Date December 1976 112120 329000 532000 719A00 795187 Analysis of Post LOCA Gamma Ray Effects in Representa-

tive Light Water Reactors. Volume 1. Final Report. Steinberg, H.; Lichtenstein, H.; Cohen, M.O. E P R I - N P - 4 2 5 ( V O L . l ) A V A I L A B I L I T Y - N T I S M A A G

6904 Date Apr i l 1978 112120 532000 719A00 Spatial Distribution of Fission Product Gamma-Ray

Energy Deposition in Light Water Reactor Fuel Ele-ments. Final Report.

Bass, R.B.; Johnson, W.R. E P R I - N P - 6 7 2 , V O L U M E 1 A V A I L A B I L I T Y - U N I V E R S I T Y OF V I R G I N I A ,

SCHOOL OF E N G I N E E R I N G A N D APPLIED SCI-ENCE, C H A R L O T T E S V I L L E , VA. 22901

U - V A «

6941 Date August 1978 112120 Final Progress Report - Fission Product Beta and Gamma

Energy Release - Progress Report for January-May 1978.

Dickens, J.K.; Emery, J.F.; Freestone, R.M.; Love,'T.A.; McConnell, J.W.; Northcutt, K.J.; Peelle, R.W.

NUREG/CR-0197 ; O R N L / N U R E G / T M - 2 2 3 A V A I L A B I L I T Y - N T I S O A R N L

6944 Date May 1978 111110 112120 210000 421200 719BOO 810000 Distribution of Fission Products in Peach Bottom H T G R

Fuel Element F03-01. Dyer,'F.F.; Wichner, R.P.; Mart in, W.J.; Fairchild, L .L . O R N L / T M - 5 9 9 6 A V A I L A B I L I T Y - N T I S $10.75 O A R N L

48 o

6983 Date August 1978 112120 The Use of Nuclear Systematics to Estimate Gamma Spec-

tra. Holter, G.D. N U C L . T E C H N O L O G Y , 39(3), 266-274 U - O R

Fission-Product Energy Release for Times Following Ther-mal -Neut ron Fission of 241 - P u Between 2 and 14000 Seconds.


N U R E G / C R - 0 1 7 1 ; O R N L / N U R E G - 4 7 A V A I L A B I L I T Y - N T I S O A R N L

7032 Date September 1976 111210 112120 230000 32AOOO 795217 795254 717000

870006 810000 Neutronic Performance of Graphite Fusion Reactor Blan-

kets Containing S r - 9 0 and 1-129. Parish, T.A.; Davidson, J.W.; Draper, E.L.,Jr. CONF-760935-P3 , PP. 873-882 A V A I L A B I L I T Y - N T I S U - T X

7046 Date October 1977 112120 421200 430000 870092 Fission -Product Energy Release for Times Following Ther-

ma l -Neut ron Fission of 2 3 5 - U Between 2 and 14000 Seconds.


O R N L / N U R E G - 1 4 A V A I L A B I L I T Y - N T I S $8.00 O A R N L

7049 Date August 1977 111110 112120 713000 870094 Fast Reactor Fission Yields for 239-Pu and 241 -Pu . Maeck, W.J. ICP-1050-11 A V A I L A B I L I T Y - A L L I E D C H E M I C A L CORPORA-

T I O N , I D A H O C H E M I C A L PROGRAMS A L C C ,

8030 Date August 1978 112120 610000 Delayed Beta- and Gamma-Ray Production Due to Ther-

ma l -Neut ron Fission of 2 3 5 - U , Spectral Distributions for Times after Fission Between 2 and 14000 Sec: Tabular and Graphical Data.

Dickens, J.K.; Love, T.A.; McConnell, J.W.; Emery, J.F.; Northcutt, K.J.; Peelle, R.W.; Weaver, H.

N U R E G / C R - 0 1 6 2 ; O R N L / N U R E G - 39 A V A I L A B I L I T Y - N T I S O A R N L

8031 Date August 1978 112120 610000 870094

8118 Date August 1978 112120 532000 870092 870094 Integral Decay-Heat Measurements and Comparisons to

E N D F / B - I V and V. England, T.R.; Schenter, R.E.; Schmittroth, F. N U R E G / C R - 0 3 0 5 ; L A - 7 4 2 2 - M S A V A I L A B I L I T Y - L O S A L A M O S SCIENTIF IC LAB.,

P.O. BOX 1663, LOS A L A M O S , N E W M E X I C O 87545

LOASL

r'-:-w 8206 Date September 1978 ' fcM2120 532000 795309 870090 870092 870094

The Application of a Library of Processed E N D F / B - I V Fission-Product Aggregate Decay Data in the Calcula-tion of Decay-Energy Spectra.

LaBauve, R.J.; England, T.R.; George, D.C.; Stamatelatos, M.G.

L A - 7 4 8 3 - M S A V A I L A B I L I T Y - N T I S L O A S L

0 826 8 Date August 1978

010000 112120 870092 870094 Review of Existing Compilations and Evaluations of FPND. Lammer, G. I A E A - 2 1 3 , PP.5-32 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) IAEA

826 9 Date August 1978 010000 112120 222000 870092 870094 Needs and Accuracy Requirements for FPND in the Assess-

ment of Environmental Aspects. Lindberg, L. I A E A - 2 1 3 , PP.33-39 " A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) SWEDEN

8270 Date August 1978 010000 112120 713000 719A00 870092 870094 Needs and Accuracy Requirements for FPND in the Physics

Design of Power Reactor Cores, Rowlands, J.L.

49

IAEA 213, PP.41-60 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F ONLY) E N G L A N

8271 Date August 1978 010000 112120 532000 870092 870094 The Importance of Fission Product Nuclear Data in Reactor

Design and Operation. Devillers, C. IAEA-213, PP.61-89 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) FRANCE ''

8272 Date August 1978 010000 112120 230000 870092 870094 Needs and Accuracy Requirements for FPND in the

Out -o f -P i le Fuel Cycle. McKay, H.A.C. IAEA-213, PP.91-104 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F ONLY) E N G L A N

8273 Date August 1978 010000 112120 230000 870092 870094 A Review of FPND Requirements for Investigation of Irra-


Maeck, W.J. IAEA-213 , PP.105-108 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) ALCC

8277 Date August 1978 010000 112120 870092 870094 0

Status of Fission Product Yield Data. Cuninghame, J.G. IAEA-213 , PP.351-419 „ A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) E N G L A N

8418 Date Augustr\978 6 010000 112120 123000 870092 870094

Prediction of Unmeasured Fission Yields by Nuclear Theory or Systematics.

Denschlag, J.O. IAEA-213 , VOL.11, PP.421-485 A V A I L A B I L I T Y - I A E A ( M F O N L Y ) G E R M A N

8419 Date August 1978 010000 112120 870092 870094 Status of Decay Data of Fission Products.

Blachot, J. IAEA-213, VOL.11, PP.487-565 A V A I L A B I L I T Y - I A E A ( M F O N L Y ) FRANCE

8422 Date August 1978 010000 112120 532000 795137 870092 Integral Determination of Fission Product Inventory and

Decay Powers Schenter, R.E.; England, T.R. IAEA-213,?VOLiI I , PP.677-741 A V A I L A B I L I T Y - I A E A ( M F O N L Y ) HANFOR

8455 Date October 1978 112120 719B00 Distribution of Fission Products in Peach Bottom HTGR

Fuel Element E01-01. Wichner, R.P.; Dyer, F.F.; Martin, W.J.; Fairchild, L.L. O R N L / T M - 6 3 5 3 A V A I L A B I L I T Y - N T I S O A R N L

8502 Date January 1979, 112120 510000 512220 870092 870094 Fission Product Gamma Spectra. Jurney, E.T.; Bendt, P.J.; England, T.R. L A - 7 6 2 0 - M S A V A I L A B I L I T Y - N T I S LOASL

8510 " Date September 1978 112120 423240 532000 870092 870094 & Calometric Fission Product Decay Heat Measurements for

239-Pu, 233-U, and 235-U. Yarnell, J.L.; Bendt, P.J. ° NUREG/CR-0349; LA-7452 A V A I L A B I L I T Y - NTIS LOASL

8511 Date July 1978 111110 112120 122310 532000 870092 887000 The Effects of the Depletion and Buildup of Fissile Nuclides

and of 238 -U Fast Fissions on Fission Product Decay Power.

Trapp, T.J.,Jr. NUREG/CR-0404; OSU-NE-7806 ; THESIS A V A I L A B I L I T Y - N T I S U - O R

50

8516 Date February 1979 112120 122110 123000 532000 795217

'Updated Decay and Photon Libraries for the ORIGEN Code.

CrofT, A.G.; Haese, R.L.; Gove, N.B. O R N L / T M - 6 0 5 5 A V A I L A B I L I T Y - N T I S $6.50 O A R N L

8578 Date 1978 112120 112930 719A00 Release of Fission Products during Controlled

Loss-of-Coolant Accidents and Hypothetical Core Meltdown Accidents.

Albrecht, H.; Malinauskas, A.P. C O N F - 7 8 1 1 4 7 - 1 A V A I L A B I L I T Y - D E P . , NT IS G E R M A N

8645 Date December 1978 112120 713000 719A00 795309 870092 870094 Radiation Source Terms in L W R and L M F B R Spent Fuel

Final Report. Tech. Services Agreement 78-156. Stamatelatos, M.G. E P R I - N P - 9 4 8 A V A I L A B I L I T Y - S C I E N C E APPL ICAT IONS, INC.,

L A JOLLA, C A L I F O R N I A SCA

8657 Date February 1979 111110 112120 122310 532000 719A00 870092 870094 Fission Product Decay Power and Uncertainties After Real-

istic Reactor Operating Histories. Trapp, T.J.; Spinrad, B.I. 0

O R N L / R S I C - 4 2 , PP.105-118 A V A I L A B I L I T Y - N T I S P A N L

8678 Date March 1979 112120 32A000 552110 795217 719A00 795320 861000 Calculated, Two-Dimensional Dose Rates from a PWR

Fuel Assembly. CrofT, A.G.; Hermann, O.W.; Alexander, C.W. O R N L / T M - 6 7 5 4 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8724 Date February 1979 112120 870094 Fast Reactor Fission Yields 240-Pu and 242-Pu. Maeck, W.J.; Eggleston, R.L.; Erickson, A.L.; Tromp, R.L. I C P - 1050- IV A V A I L A B I L I T Y - N T I S $5.25

I D N E L

8740 Date August 1978 112120 222000 719A00 887000 Magnox Fuel Inventories: Experiment and Calculation

Using a Point Source Model. Nair , S. ".S R D / B / N - 4 3 4 9 A V A I L A B I L I T Y - C E N T R A L E L E C T R I C I T Y GEN-

E R A T I N G BOARD, H E A D Q U A R T E R S SERVICES, REPROGRAPHIC SECTION, COUR-T E N A Y HOUSE, 18 W A R W I C K L A N E , L O N D O N ECAP 4EB

E N G L A N

8851 Date September 1978 010000 112120 Fission Yield Data. Denschlag, H.O. CONF-780921, PP.569-588 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, F R A N C E G E R M A N

8871 Date September 1978 122100 122200 112120 An Evaluated Fission Product Data Library for Super Phe-

nix Project. Darrouzet, M.; Fabbri, F.; Fort, E.; Krebs, J.; Langlet, J.;

Mar t in-Deid ier , L.; Montaguti, A.; Menapace, E.; Motta, M.; Panini, G.C.; Reffo, G.; Ribon, P.; Thuong, T.Q.; Vaccari, M.; Ventura, A .

CONF-780921, PP.1146-1150 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, F R A N C E F R A N C E

8917 Date May 1979 112120 870094 Fission Yields for Thermal-Neutron Fission of Plutoni-

u m - 2 4 l ! Dickens, J.K. N U C L . SCI. ENG., 70(2), 177-183 O A R N L

»

8925 Date June 1979 112120 Reactor Fuel Burnup Calculations in the LASER Code.

(Tech. Note) Chang, Y.Y.; Loyalka, S.K.; Tjmmons, D.H. N U C L . SCI. ENG., 70(3), 313-315 U - M O

51 O


Reactor Applications. Rose, P.F.; Pearlstein, S.; Ozer, O. E P R I - N P - 1098-SY A V A I L A B I L I T Y - N A T I O N A L N U C L E A R D A T A

CENTER, B R O O K H A V E N N A T I O N A L L A B O R A -TORY, UPTON, N E W Y O R K 11973

BROOKH \>.

9024 Date May 1979 112120 532000 870092 Nuclear Data Library of Fission Products for Decay Power

Calculation. Tasaka, K. N U R E G / C R - 0 7 0 5 ; TREE-1325 A V A I L A B I L I T Y - E G A N D G I D A H O , INC., I D A H O EDGERT

9143 Date September 1979 112120 Comparison of Calculations and Measurements of Fission

Product Decay Heat for Uranium-235 and Plutoni-um-239 for Cooling Times Greater than 50,000. (Tech. Note)

Shure, K.; Wallace, O.J.; Connor, J.C. N U C L . SCI. ENG., 71(3), 327-330 BETTIS

9256 Date October 1979 010000 112120 Decay Spectra of Fission Products from Uranium-235

Thermal Fission: Comparison of Calculations with Experiments. 0

Stamatelatos, M.G.; England, T.R. N U C L . T E C H N O L O G Y , 45(3), 219-232 L O A S L

9450 Date January 1980 112120 870094 Delayed Beta- and Gamma-Ray Production Due to Ther-

mal-Neutron Fission of 239-Pu: Tabular and Graphical Spectral Distributions for Times after Fission Between 2 and 14000 Sec.

Dickens, J.K.; England, T.R.; Love, T.A.; McConnell, J.W.; Emery, J.F.; Northcutt, K.J.; Peelle, R.W.


9467 Date Mid-December 1979 112120 112930 719A00 Fission Product Source Terms for the Light'Water Reactor

Loss-of-Coolant Accident. Lorenz, R.A.; Collins, J.L.; Malinauskas, A.P. N U C L . T E C H N O L O G Y , 46(3), 404-410 O A R N L o

9503 Date September 1979 112120 870092 870094 Measurements of 239-Pu and 2 3 5 - U Fission Product

Decay Power from 1 to 10**5 Seconds. Friesenhahn, S.J.; Lurie, N .A. E P R I - N P - 9 9 8 0

A V A I L A B I L I T Y - I R T CORPORATION, 7650 CON-V O Y COURT, S A N DIEGO, CA 92111

I R T

O 9592 Date 1978

112120 719BOO Metall ic Fission Product Releases from HTR-Spher ical

Fuel Elements. '' Helmbold, M.; Amian, W.; Stoever, D.; Hecker, R. I N I S - M F - ^ 9 5 5 ; CONF-781022 -93 A V A I L A B I L I T Y - D E P . , N T I S (U.S. SALES O N L Y ) ,

PC A 0 2 / M F A01 G E R M A N

9593 Date 1978 112120 719AOO Release of Fission and Activation Products During L W R

Core Meltdown. Albrecht, H.; Matschoss, V.; Wi ld, H . I N I S - M F - 4 9 5 6 A V A I L A B I L I T Y - D E P . , N T I S (U.S. SALES O N L Y ) ,


9725 Date January 1980 112120 870094 Fission Product Yields for Thermal-Neutron Fission of

Plutonium--239. Dickens, J.K.; McConnell, J.W. N U C L . SCI. ENG., 73(1), 42 -55 O A R N L

9819 Date May 1980 112120 870092 j . Fission-Product Energy Release foiVTimes Following Ther-

mal -Neut ron Fission of 235-LkBetween 2 and 14 000 s.

Dickens, J.K.; Love, T.A.; McConnell, J.W.; Peelle, R.W. N U C L . SCI. ENG., 74(2), 106-129

52

O A R N L Sources - Gamma-Ray - Bremsstrahlung


Use in the U K Decay and Fission Product Yield Data Files.

Tobias, A . C E G B - R D / B / N - 4 4 2 3 « A V A I L A B I L I T Y - D E P . , NT IS (U.S. SALES O N L Y ) ,



6868 Date May 1978 112200 329000 863000 870013 870082 Shielding Study of Bremsstrahlung in Bulk Media with Elec-

trons. Part I: Monte Carlo Calculations of Th ick-Target Bremsstrahlung Spectrum.

Shin, K.; Hayashda, Y.; Nakamura, T . N U C L . I N S T R U M . M E T H O D S , 151(1,2), 271-276 J A P A N

9832 Date May 1979 112120 122100 810000 Tables of R C N - 2 Fission-Product Cross Section Evalua-

tion. Volume 3. ( N d and Pm Isotopes). Gruppelaar, H. E C N - 6 5 A V A I L A B I L I T Y - D E P . , N T I S (U.S. SALES O N L Y ) ,

PC A 0 8 / M F A01 N E T H E R

6951 Date March 23, 1978 112200 810000 870092 Beta-Induced External Bremsstrahlung from Spent-Fuel

Fission Products. Stamatelatos, M.G. S A I - 7 8 - 6 0 0 - L J A V A I L A B I L I T Y - S C I E N C E A P P L I C A T I O N S , P.O.

BOX 2351, 1200 PROSPECT STREET, L A JOLLA, C A L I F O R N I A 92037

SCA

9845 Date March 1980 112120 532000 719A00 793000 T M I - 2 Decay Power: L A S L Fission-ProducDand Acti-

nide Decay Power Calculations for the President's Commission on the Accident at Three Mi le Island.

England, T.R.; Wilson, W.B. L A - 8 0 4 1 - M S , REVISED A V A I L A B I L I T Y - N T I S L O A S L

9979 Date May 1980 112120 122210 793000 810000 PEFPYD - A Library of Aggregate Fission-Product

Decay Data Derived from E N D F / B - I V . LaBauve, R.J.; George, D.C. L A - 8 3 6 5 - M S A V A I L A B I L I T Y - N T I S $4.00 L O A S L

10011 Date July 1980 112120 112760 532000 795217 810000 887000 A User's Manual for the O R I G E N 2 Computer Code. CrofT, A.G. O R N L / T M - 7 1 7 5 A V A I L A B I L I T Y - N T I S , PC A 0 9 / M F A01 O A R N L

7060 Date January 1977 112200 810000 Intermediate Energy Approximation of B - H Formula for

the Bremsstrahlung Cross Sections. Gopala, K.; Sanjeevaiah, B. NBS SPEC. PUB. 461, PP. 60-63 A V A I L A B I L I T Y - S U P T . OF D O C U M E N T S , GPO,


Sources - Gamma-Ray - Neutron-Inelastic-Scattering


6996 , Date 1978 112400 610000 Atlas of Gamma-Ray Spectra from the Inelastic Scattering

of Reactor Fast Neutrons. Demidov, A .M. BOOK ( I N RUSSIAN A N D E N G L I S H ) O A V A I L A B I L I T Y - M O S C O W , A T O M I Z D A T RUSSIA

8842 Date September 1978 010000 122200 112400 112500 112600 810000 Photon Production in Neutron Induced Reactions.

53

van Heerden, I.J. C O N F - 7 8 0 9 2 1 , P P . 1 6 0 - 1 8 0 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 P A R I S CEDEX 16, F R A N C E S A F R I C "

8881 Date 1979 111110 112400 112500 421200 522230 795065 795223

861000 870098 Measurement , and Calculation of the Gamma-F ie ld s

Induced'in Iron by 2 5 2 - C f Fission Neutrons. Jiang, S.H. 0

D O E - T R - 7 2 ; K F K - 2 4 4 4 ( IN G E R M A N ) A V A I L A B I L I T Y - U S D O E T E C H N I C A L I N F O R M A -

T I O N C E N T E R , OAK RIDGE, T E N N . G E R M A N

9252 Date October 1979 111210 122310 112400 112500 329000 421130 421200 Neutron and G a m m a - R a y Spectra from 2 3 2 - T h ,

2 3 5 - U , 2 3 8 - U , and 2 3 9 - P u after Bombardment with 1 4 - M e V Neutrons.

Hansen, L.F.; Wong, C.; Komoto, T.T.; Pohl, B.A.; Gold-r j berg, E.; Howerton, R.J.; Webster, W.M.

N U C L . SCI. ENG. , 72(1), 3 5 - 5 1 L A L L

o o

Sources - G a m m a - R a y - Neu t ron -Cap tu re O = i)


7113 Date July 1976 111110 112500 421200 H ** Capture Gamma-Rad ia t ion Yield from a Layer of Iron for

Neutrons Striking at an Angle. Degtyarev, S.F.; Repin, N.N. ; Sakovich, V.A.; Sakharov,

V.M.; Suvorov, A.P.; Tarasov, V.V. E R D A - T R - 1 2 5 , PP. 140 -144 A V A I L A B I L I T Y - N T I S R U S S I A

7114. . Date July 1976 112500 423250 o32A000 511110,512210^512220 853800

861000 - ^ Investigation of the Field of Capture G a m m a - R a d i a t i o n in

Solid Shielding. o Bolyatko, V.V.; Gorbatov, V.S.; Reytblat, V.L.; Tkachenko,

6 V.V.; Khokhlov, V.F.; Tsypin, S.G. E R D A - T R - 1 2 5 , PP. 145-151 A V A I L A B I L I T Y - N T I S

RUSSIA

8097 Date September 1978 112500 121100 870073 The Dependence of the G a m m a - R a y Spectral Shape on the

Neutron Energy Averaging Interval Size for the 181-Ta(n ,gamma) Reaction. (Tech. Note)

Stelts, M.; Browne, J.C. 0

N U C L . SCI. ENG. , 67(3) ,344-347 LALL

y

I 8842 " . . Date September ,-^978

010000 122200 112400 112500 11 Photon Production in Neutron Induced Rekctiooi: van Heerden, I.J. * C O N F - 7 8 0 9 2 1 , P P . 1 6 0 - 1 8 0 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 P A R I S C E D E X 16, F R A N C E S A F R I C

f " 8848 Date September 1978

010000 121100 112500 61 ({ Neutron Radiative Capture 'Cross-Sect ion Calculations. Benzi, V. 0

C O N F - 7 8 0 9 2 1 , PP .288-305 AVAILABILITY.^OECD, 2, R U E A N D R E - P A S C A L ,

75775 P A R I S CEDEX 16, F R A N C E ITALY

8881 Date 1979 111110 112400 112500 421200 522230 795065 795223

861000 870098 Measurement and Calculation of the G a m m a - F i e l d s

Induced in Iron by 2 5 2 - C f Fission Neutrons. Jiang, S.H. 0

D O E - T R - 7 2 ; K F K - 2 4 4 4 ( IN G E R M A N ) A V A I L A B I L I T Y - U S D O E T E C H N I C A L I N F O R M A -

T I O N C E N T E R , OAK RIDGE, T E N N . G E R M A N ,, a

o

9252 ,. Date October 1979 -111210 122310 112400 112500 329000 421130 421200 Neutron and G a m m a - R a y Spectra from c-232-Th,

2 3 5 - U , 238-U, |^and 2 3 9 - P u after Bombardment with 1 4 - M e V Neutrons, t?

Hansen, L.F.; Wong, C.; Komoto, T.T.; Pohl, B.A.; Gold-berg, E.; Howerton, R.J.; Webster, W.M. -

NUCL. SCI. ENG., 72(1), 3 5 - 5 1 v, LALL

o

54 I //

Sources - 'Gamma-Ray - Neutron-Reaction-Product (n,x7) Charged Particles


V

6309 Date June 1977 010000 112600 112710 230000 Regulation of Naturally Occurring and Accelera-



NUREG-0301 A V A I L A B I L I T Y - N T I S N U R C

6791 Date 1977 112710 610000 ,";t,. Quantum Radiations of Radioactive Nuclides. Gusev, N.G.; Dmitrev, P.P. A -BOOK : A V A I L A B I L I T Y - A T O M I Z D A T , MOSCOW ' RUSSIA

6883 Date 1976 ( ^ 112710 610000 ,> N E U T R O N A C T I V A T I O N TABLES.

Erdtmann, G. BOOK ^ A V A I L A B I L I T Y - N E W YORK, V E R L A G C H E M I E G E R M A N

8842 Date September 1978 010000 122200 112400 112500 112600 810000 Photon Production in Neutron Induced Reactions, van Heerden, I.J. CONF-780921, PP.160-180 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, FRANCE SAFRIC

Sources - Gamma-Ray - Radionuclide-Decay -General Surveys



mal Operation of L iquid-Metal-Cooled Fast Breeder Reactors.

Erdman, C.A.; Kelly, J.L.; Kirbiyik, M.; Reynolds, A.B. E P A - 5 2 0 / 3 - 7 5 - 0 1 9 A V A I L A B I L I T Y - DEPT. OF NUCLEAR ENGINEER-

ING, V I R G I N I A UNIV. , CHARLOTTESVILLE, VA.

U - V A

O 6309 Date June 1977

010000 112600 112710 230000 Regulation of Naturally Occurring and Accelera-



NUREG-0301 ^ A V A I L A B I L I T Y - N T I S N U R C

8044 Date January 1978 112710 610000 Internal Conversion Coefficients for E5 and M5 Nuclear

Transitions 30 Z 104. Band, I.M.; Trzhaskovskaya, M.B.; Listengarten, M.A. A T O M I C DATA A N D NUCL . DATA TABLES, 21(1),

1 -47 RUSSIA

G 8239 Date February - March 1978

010000 112710 610000 Internal Conversion Coefficients for all Atomic Shells ICC

Values for Z = 30-67. Rosel, F.; Fries, H.M.; Alder, K.; Pauli, H.C. A T O M I C DATA A N D NUCL. DATA TABLES,

21(2-3), 91-289 SWITZE

8506 Date 1978 112710 420000 610000 A Handbook of Radioactivity Measurements Procedures. NCRP NCRP-58 A V A I L A B I L I T Y - N C R P PUBLICATIONS, P.O. BOX

30175, WASHINGTON, D.C. 20014 NCRP

8781 Date December 1978 112930 112710 112760 222000 719A00 Calculation of Releases of Radioactive Materials in Gaseous

and Liquid Effluents from Boiling Water Reactors ( B W R - G A L E Code).

Bangart, R.L.; Bell, L.G.; Boegli, J.S.; Burke, W.C.; Lee, J.Y.; Minns, J.L.; Stoddart, P.G.; Weller, R.A.; Collins, J.T. ©

NUREG-0016 (REV. l ) A V A I L A B I L I T Y - N T I S

55

NURC A V A I L A B I L I T Y - N T I S $7.25 I D N E L

8783 Date October 1978 112710 220000 223000 711100 845000 Potential Radiation Dose to Man from Recycle of Metals

Reclaimed from a Decommissioned Nuclear Power Plant.

O'Donnell, F.R.; Cotter, S.J.; Kocher, D.C.; Etnier, E.L.; Watson, A.P.

NUREG/CR-0134 ; O R N L / N U R E G / T M - 2 1 5 A V A I L A B I L I T Y - D E P . , NT IS O A R N L

884 4 Date September 1978 010000 122200 112710 810000 The U K Chemical Nuclear Data Files: An Evaluated Set of

Radioactive Decay Data for Reactor<Applications. Davies, B.S.J.; Crouch, E.A.C.; James, M.F.; Nichols, A.L.;

Parkinson, J.R.; Tobias, A.; Vallis, D.G. CONF-780921, PP.209-214 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, FRANCE E N G L A N

884 5 Date September 1978 010000 112710 122200 810000 Bibliotheque de Donnees Nucleaires non Neutroniques des

Isotopes Radioactifs, Produits de Fission et Noyaux Lourds.

Blachot, J.; Fiche', Ch. CONF-780921, PP.215-222 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

„ 75775 PARIS CEDEX 16, FRANCE FRANCE

8911 Date 1978 112710 122200 421140 810000 Gamma-Ray Spectra of Neutron-Irradiated Activation

Detectors. Hogel, J. ZJE-230 A V A I L A B I L I T Y - S KOD A WORKS, N U C L E A R

POWER CONSTRUCTION DEPART., I N F O R M A -T I O N CENTRE, P L Z E N - CZECHOSLOVAKIA

CZECHO

9042 .<• Date December 1978 020000 112710 220000 Standardized Radioactive Decay Data Sets for Use in Radi-

ation Dosimetry. " Kocher, D.C.; Ewbank, W.B.; Martin, M.J. STI/PUB-471(VOL.2),PP.139-145;

CON F-771209-P2,PP.139-145; A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C

ENERGY AGENCY, V I E N N A (AUSTRIA) O A R N L

9043 Date December 1978 020000 112710 The Radioactivity Standards Programme of the National

Bureau of Standards. Mann, W.B. STI/PUB-471(VOL.2))PP.147-154;

C O N F - 771209 -P2,PP. 147 -154; A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C


9100 Date February 1979 112710 610000 Gamma-Ray Catalog. Reis, U.; et al. G S I - 7 9 - 2 A V A I L A B I L I T Y - G E S E L L S C H A F T FUER SCHWER-

IONENFORSCHUNG, DARMSTADT (GERMANY, F.R.)

G E R M A N

9257 Date 1978 112710 610000 TABLE OF ISOTOPES. Seventh Edition. Lederer, C.M.; Shirley, V.S. BOOK A V A I L A B I L I T Y - J O H N W I L E Y A N D SONS, INC. L A B L

8973 Date Apr i l 1979 112710 223000 222000 719A00 Gamma Dose Measurements at Zion and Fort Calhoun Sta-

tions. Dyer, N.C.; Bunting, R.L.; Nieschmidt, E.B.; Croney, S.T.;

Kynaston, R.L.; Mclsaac, C.V.; Underwood, D.R. NUREG/CR-0755

9441 Date September 1979 112710 122100 610000 717000 793000 810000 G A M M O N Activation Library. Battat, M.E.; LaBauve, R.J.; Muir , D.W. L A - 8 0 4 0 - M S A V A I L A B I L I T Y - D E P . , NTIS, PC A 0 3 / M F A01 LOASL

56

10137 Date July 1980 112710 522120 632110 810000 Exposure Rate Conversion Factors for Radionuclides Depos-

ited on the Ground. Beck, H.L. E M L - 3 7 8 A V A I L A B I L I T Y - D O E , N E W YORK, N.Y., ENVI-

R O N M E N T A L MEASUREMENTS LABORATORY

DOE

Sources - Gamma-Ray - Radionuclide-Decay -'"Co


Sources - Gamma-Ray - Radionuclide-Decay Other (includes corrosion products)



mal Operation of L iquid-Metal -Cooled Fast Breeder Reactors.

Erdman, C.A.; Kelly, J.L.; Kirbiyik, M.; Reynolds, A.B. E P A - 5 2 0 / 3 - 7 5 - 0 1 9 A V A I L A B I L I T Y - D E P T . OF NUCLEAR ENGINEER-

ING, V I R G I N I A UNIV . , CHARLOTTESVILLE, VA.

U - V A

9185 Date August 1979 112720 512110 329000 820000 User's Manual for P H O E L - 2 , a Monte Carlo Computer

Code for Calculating Energies of Photoelectrons and Compton Electrons in Water.

Turner, J.E.; Hamm, R.N.; Wright, H.A.; Modolo, J.T.; Sordi, G.M.A.A.


Sources - Gamma-Ray - Radion^clide-Decay -'"Cs


6858 Date June 1978 112120 112730 532000 719A00 870092 Fission Product Source Terms for the LWR

Loss-of-Coolant Accident: Summary Report. Lorenz, R.A.; Collins, J.L.; Malinauskas, A.P. N U R E G / C R - 0 0 9 1 ; O R N L / N U R E G / T M - 2 0 6 A V A I L A B I L I T Y - N T I S O A R N L

10072 Date July 1980 1 12730 112930 719A00 Fission Product Source Terms for the LWR

Loss-of-Coolant Accident. Lorenz, R.A.; Collins, J.L.; Malinauskas, A.P. N U R E G / C R - 1 2 8 8 ; O R N L / N U R E G / T M - 3 2 1 A V A I L A B I L I T Y - N T I S O A R N L

6407 Date Dec. 1977 010000 112760 719AOO An Overview of the Activated Corrosion Product Reduction

Program at U.S. Power Reactors. Murphy, T.D. CONF-770401, PP.364-373; ATOMKERNENERGIE ,


DR., PRINCETON, NJ 08540 N U R C

6408 Date Dec. 1977 112760 719A00 719B00 713000 Prediction of Primary Circuit Contamination in Power

Reactors. Beslu, P.; Costa, L.; Frejaville, G.; Pepin, P. CONF-770401, PP.374-391; ATOMKERNENERGIE ,


DR., PRINCETON, NJ 08540 FRANCE

6409 Date Dec. 1977 112760 719A00 223000 EPRI Programs in Power Reactor Radiation Control. Shaw, R.A.; Uhl, D.L. CONF-770401, PP.392-400 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, N J 08540 EPRI

6411 Date Dec. 1977 112760 223000 719A00 Analysis of Dose Rates Near the Circuit of a PWR After

Shutdown. Beslu, P.; Frejaville, G.; Lalet, A.; Devillers, C.

57

CONF-770401, PP.409-415 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6946 Date May 1978 112760 112930 222000 717000 Assessment of Radiological Releases to the Environment

from a Fusion Reactor Power Plant. Shank, K.E.; Oakes, T.W.; Easterly, C.E. O R N L / T M - 6368 A V A I L A B I L I T Y - N T I S $5.25 O A R N L

6978 Date August 1978 112760 719A00 A Calculation Model for Predicting Concentrations of

Radioactive Corrosion Products in the Primary Coolant of Boiling Water Reactors.

Uchida, S.; Kikuchi, M.; Asakura, Y.; Yusa, H.; Ohsumi, K. NUCL. SCL ENG., 67(2), 247-254 JAPAN

7042 Date September 1976 010000 111210 112760 223000 210000 521130 522130


Reactors. Vogelsang, V/.F. CONF-760935-P4, PP. 1303-1318; U W F D M - 1 7 8 A V A I L A B I L I T Y - N T I S U - W I

8459 Date October 1978 111210 112760 112930 220000 223000 521130 531000

532000 795303 795254 717000 810000 32A000 Safety Aspects of Activation Products in a,Compact Toka-

mak Fusion Power Plant. Willenberg, H.J.; Bickford, W.E. PNL-2823 V

A V A I L A B I L I T Y - N T I S P A N L

8735 Date February 1979 112760 220000 795185 A Q U A M A N - A Computer Code for Calculating Dose

Commitment to Man from Aqueous Releases of Radionuclides.

Shaeffer, D.L.; Etnier, E.L. O R N L / T M - 6 6 1 8 A V A I L A B I L I T Y - NTIS O A R N L

8781 Date December 1978 112930 112710 112760 222000 719A00 Calculation of Rele ases of Radioactive Materials in Gaseous


Bangart, R.L.; Bell, L.G.; Boegli, J.S.; Burke, W.C.; Lee, J.Y.; Minns, J.L.; Stoddart, P.G.; Weller, R.A.; Collins, J.T.

NUREG-0016 (REV. l ) A V A I L A B I L I T Y - N T I S N U R C

8785 Date Apr i l 1979 112760 220000 795337 810000 845000 Dose-Rate Conversion Factors for External Exposure to

Photon and Electron Radiation from Radionuclides Occurring in Routine Releases from Nuclear Fuel Cycle Facilities.

Kocher, D.C. NUREG/CR-0494 ; O R N L / N U R E G / T M - 2 8 3 A V A I L A B I L I T Y - N T I S O A R N L

8915 Date July 1978 112760 719AOO Deposition of Iron Oxide on Heated Surfaces in Boiling

Water. Asakura, Y.; Kikuchi, M.; Uchida, S.; Yusa, H. NUCL. SCL ENG., 67(1), 1 - 7 JAPAN

9020 Drte December 1977 112760 719B00 A Review of Fission Product Plateout Investigations at Gen-

eral Atomic. Hanson, D.L. GA-A14555 A V A I L A B I L I T Y - N T I S $5.25 GEAC

9114 Date August 1979 112760 717000 795203 Dose Rates from Induced Activity in the TFTR Test Cell. Alsmiller, R.G.,Jr.; Barish, J.; Santoro, R.T.; Lillie, R.A.;

Barnes, J.M.; Ragheb, M.M.H. O R N L / T M - 6 9 0 4 A V A I L A B I L I T Y - N T I S O A R N L

9376 Date October 1979 112760 220000 610000 711100 845000 Estimates of Internal Dose Equivalent to 22 Target Organs

for Radionuclides Occurring in Routine Releases from Nuclear Fuel-Cycle Facilities. Vol.II.

58 U

Dunning, D.E.,Jr.; Bernard, S.R.; Walsh, P.J.; Killough, G.G.; Pleasant, J.C.

NUREG/CR-0150,VOL.2 ; O R N L / N U R E G / T M - 190/V2 "

A V A I L A B I L I T Y - N T I S O A R N L


Use in the U K Decay and Fission Product Yield Data Files.

Tobias, A. C E G B - R D / B / N - 4 4 2 3 A V A I L A B I L I T Y - D E P . , NTIS (U.S. SALES O N L Y ) ,


10011 Date July 1980 112120 112760 532000 795217 810000 887000 A User's Manual for the ORIGEN2 Computer Code. Croff, A.G. O R N L / T M - 7 1 7 5 A V A I L A B I L I T Y - N T I S , PC A 0 9 / M F A01 O A R N L

10074 Date July 1980 1 11110 112760 870006 795217 719BOO Carbon-14 Production in the Peach Bottom HTGR Core. Wichner, R.P.; Dyer, F.F. ORNL-5597 A V A I L A B I L I T Y - N T I S O A R N L

10080 Date August 1980 112760 230000 532000 851000 Expected Environments in High-Level Nuclear Waste and

Spent Fuel Repositories in Salt. Claiborne, H.C.; Rickertsen, L.D.; Graham, R.F. O R N L / T M - 7 2 0 1 A V A I L A B I L I T Y - N T I S , PC A 1 0 / M F A01 O A R N L

Sources - Gamma-Ray - Radionuclide-Decay - N


6405. Date Dec. 1977 1 12770 223000 719C00 Measurement and Prediction of Gamma-Ray Sources and

Dose Rates in the Vicinity of the Winfr i th SGHWR.

Miller, P.C.; Avery, A.F.; Carter, M.D.; Chestnutt, M .M. CONF-770401, PP.342-352 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 C N G L A N

Sources - Gamma-Ray - Fallout from Weapons


9539 Date October 24, 1979 112920 522120 731200 Fallout Model for System Studies. Harvey, T.F.; Serduke, F.J.D. UCRL-52,858 ! A V A I L A B I L I T Y - N T I S L A L L „

Sources - Gamma-Ray - Simulated Fallout from Weapons



mal Operation of L iquid-Meta l -Cooled Fast Breeder Reactors.

Erdman, C.A.; Kelly, J.L.; Kirbiyik, M.; Reynolds, A.B. E P A - 5 2 0 / 3 - 7 5 - 0 1 9 A V A I L A B I L I T Y - D E P T . OF N U C L E A R ENGINEER-


U - V A

6538 Date January 1977 112930 222000 220000 Influence of Plume Rise on the Consequences of Radioactive

Material Releases. Russo, A.J.; Wayland, J.R.; Ritchie, L.T. SAND-76 -0534 A V A I L A B I L I T Y - N T I S S A N D I A \

6637 Date February 1978 112930 222000 A Model to Estimate Radiation Dose Commitments to the

World Population from the Atmospheric Release of Radionuclides (LWBR Development Program).

Rider, J.L.; Beal, S.K. W A P D - T M - 1 2 7 4 A V A I L A B I L I T Y - B E T T I S A T O M I C POWER LAB.

59

BETTIS

6666 Date Apri l 1978 010000 112930 Proceedings of a Workshop on the Evaluation of Models

Used for the Environmental Assessment of Radionuclide Releases.

Hoffman, F.O. (Ch.) CONF-770901 A V A I L A B I L I T Y - N T I S $7.25 O A R N L

6940 Date May 1978 112930 610000 Definition of Loss-of-Coolant Accident Radiation

Source: Summary and Conclusions. Bonzon, L.L.; Lurie, N.A.; Houston. D.H.; Naber, J.A. NUREG/CR-0183 ; SAND78-0091 A V A I L A B I L I T Y - N T I S $9.00 S A N D I A

6945 Date March 1978 112930 222000 329000 Monte Carlo Simulation of Turbulant Atmospheric Trans-

port and Comparisons with Experimental Data. Alsmiller, F.S.; Alsmiller, R.G.,Jr.; Bertini, H.W.; Begovich,

C.L. O R N L / T M - 6 2 9 1 A V A I L A B I L I T Y - D E P . , NT IS $5.25 O A R N L

6946 Date May 1978 112760 112930 222000 717000 Assessment of Radiological Releases to the Environment

from a Fusion Reactor Power Plant., Shank, K.E.; Oakes, T.W.; Easterly, C.E. O R N L / T M - 6 3 6 8 A V A I L A B I L I T Y - N T I S $5.25 O A R N L

6997 Date 1977' 112930 222000 Point Source Modeling - S t a t e - o f - t h e - A r t Assessment

of Computer Simulation of Localized A i r Pollutant Emissions.

Fab rick, A.J. BOOK A V A I L A B I L I T Y - W E S T L A K E V ILLAGE, CALIF. ,

FORM A N D SUBSTANCE FORM r»

7091 Date February 1974 112930 220000 222000 713000 719A00 719B00 t Projections of Radioactive Wastes to be Generated by the

U.S. Nuclear Power Industry. Blomeke, J.O.; Kee, C.W.; Nichols, J.P. O R N L - T M - 3 9 6 5 A V A I L A B I L I T Y - O A K RIDGE N A T I O N A L LABO-

RATORY O A R N L

7092 y.zDale January 1975 112930 220000 222000 79518^795304 870092 870094 A Comparison of the Potential Radiological Impact of Recy-

cle 233 -U HTGR Fuel and LMFBR Plutonium Fuel Released to the Environment.

Ti l l , J.E. O R N L - T M - 4 7 6 8 A V A I L A B I L I T Y - O A K RIDGE N A T I O N A L LABO-

RATORY " O A R N L

8025 Date July 1978 112930 220000 222000 717000 810000 Application of Probabilistic Consequence Analysis to the

Assessment of Potential Radiological Hazards of Fusion Reactors.0

Sawdye, R.W.; Kazimi, M.S. M I T N E - 2 2 0 ''< « A V A I L A B I L I T Y - M A S S A C H U S E T T S INST ITUTE

OF TECHNOLOGY U - M A

8029 Date November 1978 112930 Radioactive Materials Released from Nuclear Power Plants

(1976). Decker, T.R. NUREG-0367 A V A I L A B I L I T Y - N T I S $9.00 N U R C

8048 Date June 1978 112930 222000 Methods for Calculating Population Dose from Atmospheric

Dispersion of Radioactivity. Cohen, B.L.; Jow, H.N.; Lee, I.S. H E A L T H PHYS., 34(6), 569-572 U - P A

8372 Date December 1978 112930 220000 222000 731200 Effects of Man's Residence Inside Building Structures on

Radiation Doses from Routine Releases of Radionu-clides to the Atmosphere.

60

Kocher, D.C. O R N L / T M - 6 5 2 6 A V A I L A B I L I T Y - N T I S $6.00 O A R N L

8436 Date January 1979 112930 222000 870092 Potential Radiological Impacts of Recovery of Uranium

from Wet-Process Phosphoric Acid. Davis, W., Jr.; Haywood, F.F.; Danek, J.L.; Moore, R.E.;

Wagner, E.B.; Rupp, E.M. O R N L / E P A - 2 A V A I L A B I L I T Y - N T I S $8.00 O A R N L

8459 Date October 1978 111210 112760 112930 220000 223000 521130 531000

532000 795303 795254 717000 810000 32A000 Safety Aspects of Activation Products in a Compact Toka-

mak Fusion Power Plant. Willenberg, H.J.; Bickford, W.E. PNL-2823 A V A I L A B I L I T Y - NTIS PANL

8507 Date January 1979 112930 220000 223000 713000 The Influence of the Physico-Chemical Form of the Aero-

sol on the Radiological Consequences of Notional Accidental Releases of Radioactivity from a Fast Breeder Reactor.

Kelly, G.N.; Jones, J.A.; Simmonds, J.R. NRPB-R73 A V A I L A B I L I T Y - H M S O ISBN 0 85951 082 4 ENGLAN


Loss-of-Coolant Accidents and Hypothetical Core Meltdown Accidents.

Albrecht, H.; Malinauskas, A.P. CONF-781147-1 A V A I L A B I L I T Y - D E P . , NTIS G E R M A N

8644 Date November 1978 112930 719A00 Sources of Radioiodine at Pressurized Water Reactors Final

Report (Research Project 274- 1). Pelletier, C.A.; Cline, J.E.; Barefoot, E.D.; Hemphill, R.T.;

Voilleque, P.G.; Emel, W.A. E P R I - N P - 9 3 9

A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, INC., ROCKVILLE, M A R Y L A N D , NUCLEAR ENVI-R O N M E N T A L SERVICES DIV.

SCA

8781 Date December 1978 112930 112710 112760 222000 719AOO Calculation of Releases of Radioactive Materials in Gaseous



NUREG-0016 (REV. l ) A V A I L A B I L I T Y - N T I S NURC

8821 Date 1978 112930 223000 719A00 810000 An Approach of the Skoda Works to the Forecasting and

Computing of the Radiational Situation in a Nuclear Power Plant.

Hep, J.; Valenta, V.; Veverka, O. ZJE-199 A V A I L A B I L I T Y - S K O D A WORKS, NUCLEAR

POWER CONSTRUCTION DEPARTMENT, I N F O R M A T I O N CENTRE, PLZEN - CZECHO-SLOVAKIA '

CZECHO , , {'/,

8835 Date 1978 112930 220000 222000 610000 Manual of Dose Evaluation from Atmospheric Releases. Shirvaikar, V.V.; Abrol, V. B.A.R.C./ I -503 A V A 1 L A B I L I T Y - B H A B H A ATOMIC RESEARCH

CENTRE, BOMBAY, IND IA IND IA

9018 Date April 1978 112930 632110 731200 Protective Action Evaluation. Part 1. Effectiveness of Shel-

tering as a Protective Action Against Nuclear Accidents Involving Gaseous Releases.

Anno, G.H.; Dore, M.A. EPA-520 /1 -78 -001A A V A I L A B I L I T Y - N T I S ENPA

9027 Date June 1979 112930 220000 222000 795304 A IRDOS-EPA: A Computerized Methodology for Esti-

mating Environmental Concentrations and Dose to Man from Airborne Releases of Radionuclides.

a

u 0 61

Moore, R.E.; Baes, C.F., III; McDowell-Boyer, L.M.; Watson, A.P.; Hoffman, F.O.; Pleasant, J.C.; Miller, C.W.

ORNL-5532 AVAILABILITY-DEP., NTIS OARNL

9130 Date June 1979 112930 222000 719A00 AIRWAY - A FORTRAN Computer Program to Esti-

mate Radiation Dose Commitments to Man from the Atmospheric Release of Radionuclides (LWBR Devel-opment Program).

Rider, J.L. WAPD-TM-1275 AVAILABILITY-BETTIS ATOMIC POWER LABO-

RATORY, WEST MIFFLIN, PA. BETTIS

9375 Date July 1979 112930 220000 713000 845000 The Radiological Consequences of Notional Accidental

Releases of Radioactivity from Fast Breeder Reactors: Sensitivity to the Dose-Effect Relationships Adopted for Early Biological Effects.

Kelly, G.N.; Simmonds, J.R.; Smith, H.; Stather, J.W. NRPB-R87 AVAILABILITY-HMSO ISBN 0 85951 110 3 ENGLAN

•j 946"H Date Mid-December 1979

112120 112930 719A00 Fission Product Source Terms for the Light Water Reactor

Loss-of-Coolant Accident. Lorenz, R.A.; Collins, J.L.; Malinauskas, A.P. NUCL. TECHNOLOGY, 46(3), 404-410 OARNL

946 8 Date Mid-December 1979 112930 719C00 Space-Time Neutronic Analysis of Postulated

Loss-of-Coolant Accidents in CANDU Reactors. Luxat, J.C.; Frescura, G.M. NUCL. TECHNOLOGY, 46(3), 507-516 CANADA

946 9 ! . . Date Mid-December 1979 112930 719A00 Release of Fission and Activation Products During Light

Water Reactor Core Meltdown. Albrecht, H.; Matschoss, V.; Wild, H. NUCL. TECHNOLOGY, 46(3), 559- 565 GERMAN

9526 : . . Date September 1979 112710 112120 112930 222000 A Model for Short and Medium Range Dispersion of

Radionuclides Released to the Atmosphere. Clarke, R.H. NRPB-R91 AVAILABILITY-HMSO P2.00 ENGLAN

9926 Date May 1980 112930 220000 222000 795185 A Mathematical Model for Predicting the Probability of

Acute Mortality in a Human Population Exposed to Accidentally Released Airborne Radionuclides. Final Report for Phase 1 of the Project: Early Effects of Inhaled Radionuclides.

Filipy, R.E.; Borst, F.J.; Cross, F.T.; Park, J.F.; Moss, O.R.; Roswell, R.L.; Stevens, D.L.

NUREG/CR-1261; PNL-3257 AVAILABILITY-PACIFIC NORTHWEST LAB.,

RICHLAND, WASH. PANL

10072 Date July 1980 112730 112930 719A00 Fission Product Source Terms for the LWR

Loss-of-Coolant Accident. « Lorenz, R.A.; Collins, J.L.; Malinauskas, A.P. NUREG/CR-1288; ORNL/NUREG/TM -321 AVAILABILITY-NTIS OARNL

Sources - Gamma-Ray - Mixed Oxide Fuels and Spent Fuel


8757 Date March 1979 111700 112940 223000 230000 Radiological Implications of Plutonium Recycle and the Use

of Thorium Fuels in Thermal Power Reactor Operations. (Tech. Note)'

MacDonald, H.F.; Nair, S. NUCL. TECHNOLOGY, 42(3), 353-361 ENGLAN

0

9638 Date March 1980 112940 423250 « Measurement of the Gamma Dose Rate Distribution in a

Spent Fuel Assemby with a Thermoluminescent Detec-tor. Q

Ohno, A.; Matsuura, S. u NUCL. TECHNOLOGY, 47(3), 485-493

62 0

JAPAN Low Background Radioactivity

Sources - X-Ray CATEGORY N U M B E R 114000


- 0

6533 '.* Date February 1978 111220 113100 220000 632300 717000 Health Physics Aspects of Nuclear Radiations from Deute-

r ium Beam Injectors. Kim, J. O R N L / T M - 6 1 8 9 A V A I L A B I L I T Y - N T I S S4.50 OARN ( L ,

6698 Date Apr i l 1978 113100 220000 329000 423210 423250 553120 845000 An Evaluation of the Distribution of Absorbed Dose in Child

Phantoms Exposed to Diagnostic Medical X -Rays . Chen, W.; Poston, J.W.; Warner, G.G. O R N L / T M - 5 9 3 3 '-1


6884 Date 1977 000000 113100 T H E F U N D A M E N T A L S OF X - R A Y A N D R A D I U M

PHYSICS. 6th Ed. Selman, J. BOOK A V A I L A B I L I T Y - C . C . T H O M A S , SPRINGFIELD,

I L L . U - T X 0

9002 Date July 1979 111220 113100 717000 D - D Neutron and X - R a y Yields from High-Power Deu-

terium Beam Injectors. <> Kim, J. N U C L . T E C H N O L O G Y , 44(2), 315-321 O A R N L


Dose-Equivalent Index Presented in A N S I N 1 3 . l l . Yoder, R.C.; Bartlett, W.T.; Courtney, J.W.; Hooker, C.D.;

Holland, J.A.; Hogan, B.T. N U R E G / C R - 1 0 5 7 ; P N L - 3 2 1 9 . . A V A I L A B I L I T Y - D E P . , N T I s f P C " A 0 5 / M F A01 P A N L

6703 Date May 1977 114000 731200 810000 The Ionizing Radiation in Dwellings Related to the Building

Materials. Swedjemark, G.A. SSI -1977-004 A V A I L A B I L I T Y - N T I S S W E D E N

Interactions of Radiation with Matter - Collision Processes - Neutron

o . , ,, CATEGORY N U M B E R 121100

6383 Date Dec. 1977 327000 12.1100 The Effects of Square-Wel l Cross Section Minima on the

Deep Penetration of Neutrons. Peng, W.; Goldstein, H. CONF-770401, PP.149-156 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., P R I N C E T O N , N J 08540 U - N Y

6479 Date January 1978 111500 121100 210000 794000 861000 Sensitivity of Primary Knock-on Atom Spectra and Dis-

placement per Atom Cross-Sections to Different Secondary Neutron Energy and Angular Distributions and " I n -G roup " Weighting Schemes.

Gabriel, T.A.; Bishop, B.L. O R N L / T M - 6 I O 8 A V A I L A B I L I T Y - N T I S S4.50 O A R N L

6499 Date 1976 111110 121100 122110 810000 Twenty-Seven Group Cross Section Set Derived from

E N D F / B Library. Gargi S.B. BARC-892 A V A I L A B I L I T Y - D E P . , NT IS (U.S. SALES O N L Y ) I N D I A

6501 Date December 1977 010000 121100 810000 An Index to the Literature on Microscopic Neutron Data.

63

I A E A C I N D A 76/77-SUPPL.3 A V A I L A B I L I T Y - I A E A , V I E N N A I A E A

6583 010000 111110 121100 870092 870094 Theory of Nuclear Fission: A Review. Mosel, U. A N L - 7 6 - 9 0 , PP.3-30 A V A I L A B I L I T Y - N T I S G E R M A N

Date 1976

6589 Date 1976 111110 121100 122100 123000 870092 Simulation of the Structure in U - 2 3 5 Cross Sections. James, C.D. A N L - 7 6 - 9 0 , PP.382-390 A V A I L A B I L I T Y - N T I S E N G L A N

6590 Date 1976 111110 121100 870092 870094 What Happens to the Fission Process Above the 2nd - and

3 rd - Chance Fission Threshold? Stewart, L.; Howerton, R.J. A N D ^ 7 6 - 9 0 , PP.398-414 A V A I L A B I L I T Y - N T I S n L A L L /

,6593 Date 1978 111210 121100 810000 Analysis of Neutron Emission Spectra from 14 MeV Neu-

tron Reactions. Pearlstein, S. B N L - NCS - 24066 A V A I L A B I L I T Y - N A T I O N A L N U C L E A R D A T A

CENTER, B R O O K H A V E N N A T I O N A L LABORA-T O R Y , UPTON, N E W Y O R K 11973

B R O O K H

6634 Date January 16, 1978 010000 121100 Relativistic Transformations Between Center -o f -Mass

and Laboratory Systems for Two - Body Nuclear Reac-tions.

Howerton, R.J. UCRL-50400 , VOL.5, PT.B A V A I L A B I L I T Y - N T I S L A L L

6638 Date 1977 112120 121100 870092 New Possibilities of Calculating Independent Fission Prod-,

uct Yields. Valenta, V. ZJE-207 A V A I L A B I L I T Y - S K O D A WORKS, N U C L E A R

POWER C O N S T R U C T I O N D IV IS ION, INFOR-M A T I O N CENTRE, PLZEN, C Z E C H O S L O V A K I A

CZECHO

6649 Date Apr i l 1978 121100 122110 A Mult igroup Formalism for Evaluation of Continuous

Slowing Down Theory Parameters. (Tech. Note) Parvez, A.; Becker, M. N U C L . SCL ENG., 66(1), 134-140 U - N Y

6677 Date June 1977, 111110 121100 210000 421140 861000 Importance and Status of (n, alpha)-Cross Sections^for a

Reliable Prediction of Radiation Damage in (Stainless Steel.

Goel, B. EURFNR-1465 A V A I L A B I L I T Y - N T I S G E R M A N

6697 Date March 1978 111110 121100 610000 632200 810000 794000 SUPERDAN: Computer Programs for Calculating the

Dancoff Factor of Spheres, Cylinders, and Slabs. Knight, J.R. O R N L / N U R E G / C S D / T M - 2 A V A I L A B I L I T Y - N T I S $6.00 O A R N L

6705 Date November 11, 1977 111110 121100 122100 887000 Systematic of Neutron-Induced Fission Cross Sections

over the.the Energy Range 0.1 Through 15 MeV, and at 0.0253 eV.

Behrens, J.W. y U C I D - 1 7 5 0 9 - 2 r ' A V A I L A B I L I T Y - D E P . , NT IS L A L L

6709 Date September 1976 111110 111210 121100 210000 713000 717000 861000 A Systematic Approach to the Radiation Damage Problem ;

in Fission and Fusion Reactor Structural Alloys. Bullough, R.; Eyre, B.L.; Kulcinski, G.L.

64

U W F D M - 1 8 4 A V A I L A B I L I T Y - N U C L E A R E N G I N E E R I N G ' D E P A R T M E N T , U N I V E R S I T Y OF WISCONSIN,

M A D I S O N , W I S C O N S I N U - W I

6744 Date May 1978 1U110 111210 111130 210000 121100 870019 Fusion/Fission Damage Ratios for Neutron-Induced Dis-

placement Damage in Silicon.„ Van Antwerp, W.R.; Hollandsworth, C.E.; Youngblood, J.E. A R B R L - M R - 0 2 8 3 6 A V A I L A B I L I T Y - N T I S A R M Y

6774 Date Apr i l 12, 1978 121100 Relativistic Transformations Between Center-of -Mass

and Laboratory Systems for Two-Body Nuclear Reac-tions.

Howerton, R.J. UCRL-50400 , VOL.5, PT.B, REV. l A V A I L A B I L I T Y - N T I S L A L L u

6861 Date May 1978, t

111220 121100 123000 421150 810000 SIOB: A F O R T R A N Code for Least-Squares Shape Fit-

ting Several Neutron Transmission Measurements Using the Brei t -Wigner Multi level Formula,

de Saussure, G.; Olsen, D.K.; Perez, R.B. O R N L / T M - 6 2 8 6 ; E N D F - 2 6 1 A V A I L A B I L I T Y - N T I S S6.00 O A R N L

6977 Date August 1978 111110 121100 123000 870094 870092 Improved Resonance Formulas for Cross Sections of Fissile

Elements. Segev, M. N U C L . SCL ENG., 67(2), 221-234 A R G O N N

7048 Date Apr i l 1, 1977 121100 122110 Neutron-Induced Angular and Energy Distributions:

Graphical Experimental Data. ^ Cullen, D.E.; Howerton, R.J.; MacGregor, M.H. ; Perkins,"'

S.T. U C R L - 5 0 4 0 0 (VOL.19) A V A I L A B I L I T Y - N T I S L A L L '

7055 Date January 1977 010000 121100 121200 810000 Radiation Physics and Nuclear Technology. Iyengar, P.K. NBS SPEC. PUB. 461, PP. 32-40 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


705 7 Date January 1977 111210 121100 810000 Optical Model Analysis of Non-Elast ic Interaction of 14.2

, MeV Neutrons. Pal, B.; Chatterjee, A.; Ghose, A .M. NBS SPEC. PUB. 461, PP. 44 -46 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


O o n 705 8 : . . . . Date January 1977

121100 121200 632200 Geometric Factors in Radiation Physics Measurements. Ghose, A .M. NBS SPEC. PUB. 461, PP. 47 -54 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


7067 p Date January 1977 ^ 111500 121100 329000 810000 A Random Sampling Technique for Choosing Scattering

Angles from Arbitrary Angular Distributions in Dosi-metric and Shielding Computations.

Nagarajan, P.S.; Raghavendran, C.P.; Sethulakshmi, P.; Bhatia, D.P.

NBS SPEC. PUB. 461, PP. 100-105 0 <, A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


7121 Date July 1976 111110 121100 122110 810000 Analysis of Complete Neut ron-Mat ter Interaction' Cross

Sections in Nuclear Reactor. Yegorov, Yu.A.; Pankrat'yev, Yu.V.; Tolstykh, V.D. E R D A - T R - 1 2 5 , PP. 207-216 A V A I L A B I L I T Y - N T I S RUSSIA

8127 Date July 4, 1978 111110 121100 810000 Program Linear (Version 78-1 ) : Linearize Data in the

Evaluated Nuclear Data File/Version B ( E N D F / B ) Format.

o 65

Cullen, D.E. UCRL-50400, VOL.17, PT.A, REV.l AVAILABILITY-NTIS LALL

8128 Date July 4, 1978 11;M 10 121100 810000 Program SIGMA1 (Version 78-1): Doppler Broaden Eval-

uated Cross Sections in the Evaluated Nuclear Data File/Version B (ENDF/B) Format.

Cullcn, D.E. 'A. UCRL-50400, VOL.17, PT.B, REV.l AVAILABILITY-NTIS LALL

812 9 - Date March 1977 111110 111210 111220 121100 210000 717000 810000 Description of the Response of Reactor First Walls to Pulsed

Thermonuclear Radiation (Part I). Hunter, T.O.; Kulcinski, G.L. UWFDM-196 AVAILABILITY-FUSION RESEARCH PROGRAM,


U-WI

813 0 Date October 1977 111110° 111210 111220 121100 121200 531000 532000

717000 810000 Description of the Response of Materials to Pulsed Thermo-

nuclear Radiation. Part II. Transient Energy Deposition, Temperatures, and Displacement Rate.

Hunter, T.O.; Kulcinski, G.L. UWFDM-217 AVAILABILITY-FUSION RESEARCH PROGRAM,!


U-WI

8223 Date May 18, 1978 ,111110 121100 122110 810000

^ Bondarenko Self-Shielded Cross Sections and Multiband Parameters Derived from the LLL Evaluat-ed-Nuclear-Data Library (ENDL).

Cullen, D.E. UCRL-50400, VOL.20 AVAILABILITY-NTIS LALL

8401 Date July 1978 121100 121200 122110 122210 220000 531000 532000

794000 810000 MACK-IV, A New Version of MACK: A Program to Cal-

culate Nuclear Response Functions from Data in ENDF/B Format.

Abdou, M.A.; Gohar, Y.; Wright, R.Q. ANL/FPP-77-5 AVAILABILITY-NTIS $6.00 ARGONN

8429 Date August 1978 111210 111220 121100 210000 870029 A Comparison of Initial Damage Rates Using Neutron and

Electron Irradiations. Goldstone, J.A. LA - 7424-T; THESIS AVAILABILITY-NTIS LOASL - 4

8494 Date October 1, 1978 010000 121100 810000 An Index to the Literature on Microscopic Neutron Data.

/,, IAEA CINDA 78 - SUPPL. 5 TO CINDA 76/77 AVAILABILITY-INTERNATIONAL o ATOMIC

ENERGY AGENCY, VIENNA1

IAEA

121100 8142 Date October 1978

The Probability fjTable Method and Correlated Data. Pearlstein, S. NUCL. SCI. ENG., 68(1), 10-18 BROOKH

8145 Date October 1978 111210 121100 Analysis of Neutron Emission Spectra from 14-MeV Neu-

tron Reactions. Pearlstein, S. NUCL: SCI. ENG., 68(l),55-60 BROOKH

8778 Date August 1978 121100 122100 870001 870006 870008 A Calculation of Neutron Cross-Sections for the Elements

Hydrogen, Carbon, Nitrogen and Oxygen in the Energy Range 20-50 MeV.

Dimbylow, P.J. NRPB-R78 AVAILABILITY - HMSO ENGLAN

8848 Date September 1978 010000 121100 112500 Neutron Radiative Capture Cross-Section Calculations.

, Benzi, V.

66 fj

CONF-780921, PP.288-305 AVAILABILITY-OECD, 2, RUE ANDRE-PASCAL,

75775 PARIS CEDEX 16, FRANCE ITALY - „ r M l ' ;;

1978

i Threshold

9008 Date June 1979 010000 121100 310000 An Index to the Literature on Microscopic Neutron Data. IAEA ' CINDA-79 (1977-1979) AVAILABILITY-INTERNATIONAL

$ ENERGY AGENCY, VIENNA IAEA

ATOMIC i)

AVAILABILITY-OECD, / ;<Ri4B;A^pRE-PASCALt 75775 PARIS CEDEX

GERMAN " ' """"

0

Date June 1977 /y 8888 111110 121100 210000 810000

' Damage Correlation in Theory and Practice. DorarT, D.G.; Odette, G.R.; Simons, R.L.; Mansul; L.K. H E D L - S A - 1 1 4 4 - A ; CONF-770641 - 9 AVAILABILITY-NTIS HANFOR J

o I) a * C 8902 , Date 1979

121100 122100 870012 870013 870029.870040 . ^Evaluation of the Cross-Sections for the Reactions 24-Mg

(n,p) 24 -Na , 64 -Zn (n,p) 64-Cu, 63-Cu (n,2n) 62-Cu and 9 0 - Z r (n,2n) 89-Zr . <

Tagesen, S.; Vonach, H.; Strohmaier, B. PHYSICS DATA-NR, 13-1 , ^ AVAILABILITY-ISSN 0344-8401 GERMAN

^ V 9009 Date May 1979 010000 121100 310000 An Index to the Literature on Microscopic Neutron Data. // Vol.l. Z Less than or Equal to 50. IAEA , <> C I N D A - A (1935-1976) VOL.1 " Ch^ AVAILABILITY-INTERNATIONAL ATOMIC

ENERGY AGENCY, VIENNA " „ ° IAEA

* O 9010 v.0.'. . . Date May 1979 010000 121100 310000 An Index to the Literature on Microscopic Neutron Data.

Vol.2. Z Greater than or Equal to 51.° IAEA ,y \ o , " C I N D A - A (1935-1976) VOL.2 AVAILABILITY-INTERNATIONAL

ENERGY AGENCY, VIENNA " IAEA " - 3

8906 Date October 17, 1978 121100 122100 810000 ACTL: Evaluated Neutron Activation Cross Section

Library—Evaluation Techniques and Reaction Index. Gardner, M.A.; Howerton, R.J. UCRL-50400, VOL! 18 AVAILABILITY-NTIS LALL ""

8932 Date January 1979 010000 111210 121100 210000 521130 717000 795217


Structural Materials. 3

Jarvis, O.N. '* ^ A E R E - R - 9 2 9 8 AVAILABILITY-H.M.S.O. ENGLAN 0 o

ATOMIC o

9128Date October 1978 (Rev. January 1979) 111210 121100 32A000 510000 521130 717000 795254

810000 j, Discrete Transfer Cross Section Expansion for Time Depen-

dent Neutron Transport. Beranek, F.; et al. UWFDM-304 AVAILABILITY-NUCLEAR ENGINEERING

DEPARTMENT, UNIVERSITY OF WISCONSIN, x MADISON, WI P U - W I 0

9166 . . . ? ' Date May 1, 1979 010000 121100 121200 420000 Average Energy Required to Produce an Ion Pair. Wyckoff, H.O. , 11

ICRU-31 AVAILABILITY-ICRU PUBLICATIONS, P.O. BOX


9230 Date March 17, 1979 121100 810000

67

Program SIGMAL 1 ' (Vers ion 7 9 - 1 ) : Doppler - Broaden Evaluated Cross Sections in the Livermore-Evaluated Nuclear Data Library ( E N D L ) Format.

Cullen, D.E. U C R L - 5 0 4 0 0 , VOL.21, PT.C A V A I L A B I L I T Y - N T I S L A L L

fy 9569. . . Date October 1979

010000 121100 810000 0

An Index to the Literature on Microscopic Neutron Data. I A E A C I N D A 79 S U P P L E M E N T A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C

• E N E R G Y A G E N C Y , V I E N N A I A E A

A - . 9281 y t fc" . r,Date 1978 ^

111500 121100 22000lf;8ldo00v ' f j f * *' „ ; S - • Influence of Nuclear Data on Calculations of Neutron

Energy Efepos&on.« * y Caswell, R.S.; Coyne, J.J. ' . 11

EUR - 5848,PP.29 - 43; CONF-770597.PP.29-43 ' A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L P U B L I C A -

T I O N S O F (THE E U R O P E A N C O M M U N I T I E S , B O I T E POSTALE 1003 - L U X E M B O U R G ISBN 9 2 - 8 2 5 - 0 2 5 6 - 2 i,

N A B S ^

^9940 Date October 1979 121100° 123000 Program'' R E C E N T (Version 79 -1 ) : Reconstruction of , Energy-Dependent Neutron Cross Sections from Reso-

nance Parameters in the E N D F / B Format. Cullen, D'.E. UCRL-50 ,400 , VOL.17, PT.C A V A I L A B I L I T Y - N T I S $6.00 L A L L

9282 Date 1978 121100 845000° Stopping Power Ratios for Neutrons and Alpha Particles in

Tissue Equivalent Media. Thwaites, D.I.; Watt , D.E. EUR-5848.PP.45-60; CONF-770597,PP.45-60 A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L PUBL ICA-

T I O N S OF T H E E U R O P E A N C O M M U N I T I E S , B O I T E POSTALE 1003 - L U X E M B O U R G , ISBN 9 2 - 8 2 5 - 0 2 5 6 - 2 " ..

E N G L A N % o

9487 Date 1979 <--111210 121100 210000 717000 810000 Experimental Evaluation of the Primary Damage Process -

Neutron Energy Effects. Goland, A .N. CONF-79Q125, PT.A, PP,453-461; J. N U C L E A R

M A T E R . , 85 A N D 86, A V A I L A B I L I T Y - N O R T H - H O L L A N D

I N G C O M P A N Y - A M S T E R D A M B R O O K H ; <;

PUBL ISH-

0 9491 Date 1979 111220 122100 121100 210000 717000 810000 , c

Hel ium Accumulation Fluence Dosimetry for Fusion Reac-tor-Materials Irradiations.

Kneff, D.W.; Farrar, H. , IV c C01VF-790125, PT.A, PP.479-483; J. N U C L E A R

P/IATER., 85 A N D 86, A V A I L A B I L I T Y - N O R T H - H O L L A N D PUBLISH-

I N G C O M P A N Y - A M S T E R D A M ROL 55

10054 'T Date 1977 ' ' 121100 123000

Calculation of Nuclear Reaction Ci'bss Section with the Sta-tistical Model.

, Matthes, ,W. E U R - 5 7 2 2 E

<AV A I L A B I L I T Y -- C O M M I S S I O N OF T H E EURO-P E A N 2 C O M M U N I T I E S , D I R E C T O R A T E - G E N E R A L , S C I E N T I F I C A N D T E C H N I C A L I N F O R M A T I O N A N D I N F O R M A - o

T I O N M A N A G E M E N T , B A T I M E N T J E A N M O N N E T , L U X E M B O U R G ; C A T A L O G U E N O . C K - S E - 7 7 - 0 2 6 - E N - C

I T A L Y O 0 Interactions of Radiation with Matter - Collision

Processes - Gamma-Ray and X-Ray

0 CATEGORY NUMBER 12 i200

6620 Date March 1978 ^ 112B00 121200 329000 810000 A New Method of Sampling the K le in-Nish ina Probability

Distribution for A l l Incident Photon Energies Above 1 '•' keV. ( A RevisedjComplete Account). •> Everett, C.J.; Cashwell, E.D. " L A - 7 1 8 8 - M S c - |{ A V A I L A B I L I T Y - N T I S | ° L O A S L V

6725 Date 1978 U2B00 121200 o Moment-Generated Radiative-Transfer Functions for " Relativistic Maxwellian Electrons.

68

Wienke, B.R. J. Q U A N T . SPECTROSC. RADIAT . TRANSFER, 19,

163-168 L O A S L

6775. . Date October 1977 121200 613000 Semiempirical Auger-Electron Energies for Elements 10

Z 100. Larkins, F.P. A T O M I C D A T A A N D N U C L . DATA TABLES, 20(4),

311-387 A U S T R A

6785 Date Apr i l 1, 19" s 010000 121200 Z Dependence of Elastic Scattering of amma Rays

Rechecked. Roy, S.C. N U C L . I N S T R U M . M E T H O D S , 150(2), 283-287 I N D I A v

6937 Date June 1978 121200 810000 Comments on the Analysis of Total Photoabsorption Mea-

surements in the Energy Range 10 - 150 MeV. Maximon, L.C.; Gimrri, H.A. NBSIR 78-1456 A V A I L A B I L I T Y - N A T I O N A L B U R E A U OF STAN-

DARDS, DEPT. OF C O M M E R C E , W A S H I N G T O N , D.C. 20234 $4.50

NABS

7053 Date January 1977 112B00 121200 810000 Semiempirical, Formulation of Coherent Scattering of

Gamma Rays. Roy, S.C.; Ghose, A .M. NBS SPEC. PUB. 461, PP. 17-19 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

W A S H I N G T O N , D.C. 20402 I N D I A c,

a 7054 Date January 1977 112BOO 121200 810000 Experimental Photoionization Cross Section of Gamma Ray

Photons for Low, Medium and High Z Atoms. Sinha (Goswami), B.; Chaudhuri, N. NBS SPEC. PUB. 461, PP. 20-22 A V A I L A B I L I T Y - S U P T . OF D O C U M E N T S , GPO,


o

7055 Date January 1977 010000 121100 121200 810000 Radiation Physics and Nuclear Technology. Iyengar, P.K. NBS SPEC. PUB. 461, PP. 32 -40 A V A I L A B I L I T Y - S U P T . OF D O C U M E N T S , GPO,


7056 ..Date January 1977 112B00 121200 810000 Variation of Total to K - S h e l l Photoelectric Cross Section

Ratios with Atomic Number and Photon Energy. Gowda, R.; Sanjeevaiah, B. NBS SPEC. PUB. 461, PP. 41 -43 A V A I L A B I L I T Y - S U P T . OF D O C U M E N T S , GPO,


7058 Date January 1977 121100 121200 632200 Geometric Factors in Radiation Physics Measurements. Ghose, A .M. NBS SPEC. PUB. 461, PP. 47 -54 A V A I L A B I L I T Y - S U P T . OF D O C U M E N T S , GPO,


7059 Date January 1977 121200 810000 Measurement of Angular Distribution of Incoherently Scat-

tered Gamma Rays from Atoms. Sinha (Goswami), B.; Chaudhuri, N . NBS SPEC, PUB. 461, PP. 55 -56 A V A I L A B I L I T Y - S U P T . OF D O C U M E N T S , GPO,

W A S H I N G T O N , D.C. 20402*$ABSTRACT I N D I A "

7078 Date January 1977 010000 121200 220000 423240 Actual Problems in Photon Dosimetry. Regulla, D.F.; Drexler, G. NBS SPEC. PUB. 461, PP. 197-208 A V A I L A B I L I T Y - S U P T . OF D O C U M E N T S , GPO,

W A S H I N G T O N , D.C. 20402 G E R M A N

8116 Date July 1978 112130 121200 329000 512110 610000 830000 The Time Dependence of the Compton Current and Energy

Deposition from Scattered Gamma Rays. Mal ik . J.S.; Cashwell, E.D.; Schrandt, R.G. L A - 7 3 8 6 - M S

69

AVAILABILITY-LOS ALAMOS SCIENTIFIC LAB., P.O. BOX 1663, LOS ALAMOS, NEW MEXICO 87545

LOASL

8130 Date October 1977 111110 111210 111220 121100 121200 531000 532000


nuclear Radiation. Part II. Transient Energy Deposition, Temperatures, and Displacement Rate.

Hunter, T.O.; Kulcinski, G.L. UWFDM-217 AVAILABILITY-FUSION RESEARCH PROGRAM,


U - W I

8215 Date September 1978 112B00 121/200 329000 820000 o A Monte Carlo Code (PHOEL) for Generating Initial Ener-

gies of'FJfptoelectrons and Compton Electrons Produced by PhotuiS>in Water.

Turner, J.E.; Modolo, J.T.; Sordi, G.M.A.A.; Hamm, R.N.; Wright, H.A.

ORNL/TM - 6515 AVAILABILITY-NTIS $4.00 II OARNL

UVVVR-6 AVAILABILITY-INSTITUTE FOR RESEARCH,

PRODUCTION AND USES OF RADIOISOTOPES, PRAGUE 7, PRISTAVNI 24, CZECHOSLOVAKIA

CZECHO

9166 Date May 1, 1979 010000 121100 121200 420000 Average Energy Required to Produce an Ion Pair. Wyckoff, H.O. ICRU-31 AVAILABILITY-ICRU PUBLICATIONS, P.O. BOX


9862.- Date April 1978 121200 122210 32A000 810000 Definition of Two Band Parameters for Use in Photon Trans-

port Calculations. Cullen, D.E. ° UCID-17774 AVAILABILITY-NTIS, PC A02/MF A01 LALL o

Interactions of Radiation with Matter - Cross Section Evaluation or Compilation - Neutron

L CATEGORY NUMBER 122100

8401 Date July 1978 r

121100 121200 122110 122210 220000 531000 532000 794000 810000

MACK-IV, A New Version of MACK: A Program to Cal-culate Nuclear Response Functions from Data in ENDF/B Format.

Abdou, M.A.; Gohar, Y.; Wright, R.Q. ANL/FPP-77-5 AVAILABILITY-NTIS $6.00 o ARGONN

6235 Date September 1976 122100 870095 Evaluation of 241-Am Nuclear Data. Lgarasi, S.I. JAERI-M-6221 AVAILABILITY-DIVISION OF TECHNICAL

INFORMATION, JAPAN ATOMIC ENERGY RESEARCH INSTITUTE, TOKAI-MURA, N AKA - GUN, IBARAKI - KEN, JAPAN

JAPAN

8982 Date March 1979 121200 The Partition of Kerma to Account for Bremsstrahlung. Attix, F.H. HEALTH PHYS., 36(3), 347-354 U-WI

9126 Date 1979 112B00 121200 810000 Energy and Angular Distribution of Secondary Particles in

the Detection Media After the Interaction of Ionizing Radiation. Part One. ^

Okta, L.; Petr, I.

6317 Date January 1978 111110 122100 870092 Evaluation of the 238-U Neutron Cross Sections for Inci-

dent Neutron Energies Up to 4 keV. de Saussure, G.; Olsen, D.K.; Perez, R.B.; Difilippo, F.C. ORNL/TM-6152; ENDF-257 AVAILABILITY-NTIS $6.50 OARNL

6418 Date Dec. 1977 020000 122100 Activities of the Shielding Subcommittee of the ENDF/B

Cross Section Evaluation Working Group.

Roussin, R.W. CONF-770401, PP.463-471 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6498 Date 1976 111110 122100 870092 870094 Proceedings of the NEANDC/NEACRP Specialists Meet-

ing on Fast Neutron Fission Cross Sections of U-233, U -235 , U-238 , and Pu-239, June 28-30, 1976, at Argonne National Laboratory.

Poenitz, W.P.; Guenther, P.T. ANL-76-90(SUPPL.) ;CONF-760647-SUPPL. A V A I L A B I L I T Y - N T I S $5.50 ARGONN

6585 Date 1976 111110 122100 870092 870094 Comments on the Evaluation Ratios of Fission Cross Section

for U - 2 3 8 and Pu-239 to U-235. Poenitz, W.P.; Guenther, P. A N L - 7 6 - 9 0 , PP.154-169 A V A I L A B I L I T Y - N T I S ARGONN

6586 Date 1976 020000 122100 870092 The Status of U -235 Fission as a Cross Section Standard. Carlson, C.W.; Czirr, J.B. A N L - 7 6 - 9 0 , PP.258-269 A V A I L A B I L I T Y - N T I S L A L L

6510 Date 1976 020000 111110 111210 111220 122100 122200 810000

845000 Basic Physical Data for Neutron Dosimetry. Broerse, J.J. (Ed.) EUR-5629 A V A I L A B I L I T Y - INIS NETHER

6587 Date 1976 111110 122100 Common Normalization of Several U -235 Fission Data

Sets in the Thermal and Resonance Region. Leonard, B.R.,Jr. A N L - 7 6 - 9 0 , PP.281-306 A V A I L A B I L I T Y - N T I S BANW

6532 Date December 1977 122100 870090 Evaluation of the 232-U Neutron Cross Sections for Inci-

dent Neutron Energies up to 3 keV. de Saussure, G.; Macklin, R.Lv'1

O R N L / T M - 6 1 6 I A V A I L A B I L I T Y - N T I S $5.25 O A R N L

6588 Date 1976 111110 122100 870092 Evaluation of the U - 2 3 5 Fission Cross Section from 100 eV

to 20 keV. Bhat, M.R. A N L - 7 6 - 9 0 , PP.307-332 A V A I L A B I L I T Y - N T I S BROOKH

1 o

6571 Date March 1978 122100 887000 Predictions of Fission Cross Sections in the 3 - to 5 - M e V

Neutron Energy Range. Behrens, J.W.; Howerton, R.J. NUCL. SCI. ENG., 65(3), 464-467 L A L L

6572 Date March 1978 122100 Practical Formalisms for Nuclear Data Representation in

Evaluated Nuclear Data Files in the Unresolved Reso-nance Energy Region.

Gur, Y.; Yiftah, S. , NUCL. SCI. ENG.,.65(3), 468-476

ISRAEL

6589 Date 1976 111110 121100 122100 123000 870092 Simulation of the Structure in U-235 Cross Sections. James, C.D. A N L - 7 6 - 9 0 , PP.382-390 A V A I L A B I L I T Y - N T I S ENGLAN

6591 Date 1976 010000 020000 122100 Requirements on Experiment Reporting to Meet Evaluation'

Needs. Peelle, R.W. A N L - 7 6 - 9 0 , PP.421-430 A V A I L A B I L I T f ' - N T I S O A R N L

71

6615. Date August 1977 020000 122100 SOKRATOR Manual. Format of the Recommended

Nuclear Data Library for Reactor Calculations. Kolesov, V.E.; Nikolaev, M.N. INDC(CCP) -97 /L SPECIAL A V A I L A B I L I T Y - I A E A NUCLEAR DATA SECTION,

KARNTNER RING 11, A-1010 V IENNA IAEA

6630 ! Date Apri l 1978 010000 122100 810000 Status Report to the DOE Nuclear Data Committee. Perey, F.G.; Gentry, J.C. O R N L / T M - 6 3 3 8 A V A I L A B I L I T Y - N T I S $4.50 O A R N L ' - (i

A V A I L A B I L I T Y - N E T H E R L A N D S ENERGY RESEARCH FOUNDATION (ECN), 3 WESTERDUINWEG, PETTEN (NH) , THE NETH-ERLANDS

NETHER

6686 Date February 1977 122100 870092 870094 Neutron Nuclear Data of 235-U, 238-U, 239-Pu,

240-Pu and 241 - P u Adopted in JENDL-1 . Prelimi-nary Results. c

Kikuchi, Y.; Nakagawa, T.; Matsunobu, H.; Kanda, Y.; Kawai, M.

J A E R I - M - 6 9 9 6 AVA ILAB IL ITY-DEP. , NTIS (U.S. SALES O N L Y ) JAPAN

6659 Date February 1978 122100 870090 Evaluated Nuclear Data File of Th-232. Meadows, J.; Poenitz, W.; Smith, A.; Smith, D.; Whalen, J.;

Howerton, R. A N L / N D M - 3 5 A V A I L A B I L I T Y - N T I S ARGONN

6700 Date May 1978 111500 122100 870090 Evaluation of 232-Th(n,n'), (n,2n), and (n,3n) Cross Sec-

tions. , Fu, C.Y. ORNL/TM-6316 ; ENDF-267 A V A I L A B I L I T Y - N T I S $4.50 OARNL


Fast-Reactor Structural Materials. Smith, A.; McKnight, R.; Smith, D. A N L / N D M - 4 1 A V A I L A B I L I T Y - N T I S ARGONN

6702 Date 1978 111210 122100 870009 Evaluation of Neutron Cross Sections for 19-F in the

Energy Range from 100 keV to 20 MeV. Sugi, T. f O R N L - T R - 4 6 0 5 A V A I L A B I L I T Y - N T I S JAPAN

6674 Date November 1976 122100 112120 713000 <• Intercomparison of Recent Evaluations for the Capture

Cross Sections of Some Fission-Product Nuclides. Gruppelaar, H.; Janssen, A.J.; Dekker, J.W.M. ECN-12 c

A V A I L A B I L I T Y - S T I C H T I N G ENERGIEONDER-ZOEK CENTRUM NEDERLAND, PETTEN

NETHER

6705 Date November 11, 1977 111110 121100 122100 887000 Systematics of Neutron-Induced Fission Cross Sections

over the the Energy Range 0.1 Through 15 MeV, and at 0.0253 eV.

Behrens, J.W. UCID-17509-2 AVAILABIL ITY-DEP. , NTIS L A L L

6675 Date December 1977 111500 122100 810000 Tables of R C N - 2 Fission-Product .Cross Sections, Evalu-

ation, Volume 2 (13* Nuclides). Gruppelaar, H. ECN-33

6757 Date March 1977 122100 810000 Evaluations for the German Nuclear Data Library

K E D A K - 3 . Pt. l . Non-fissile Materials. lGoel, B. (Comp.) KFK-2386/1 I

O 72

A V A I L A B I L I T Y - I N S T . FUER N E U T R O N E N P H Y -SIK U N D R E A K T O R T E K N I K ; K E R N F O R S C H U N G S Z E N T R U M K A R L S R U H E ( G E R M A N Y , F.R.)

G E R M A N

6761 Date May 1978 111110 122100 870090 Review and Combination of Experimental Results for Neu-

tron Emission per Fission of 232-Th. Gwin, R. O R N L / T M - 6 2 4 5 ; E N D F - 2 6 2 A V A I L A B I L I T Y - N T I S $4.00 O A R N L c.

6763 Date March 1978 122100 870003 Cross Sections for the 7 -L i (n , xn ) and 7-L i (n ,n 'gamma)

Reactions Between 1 and 20 MeV. Morgan, G.L. O R N L / T M - 6 2 4 7 A V A I L A B I L I T Y - N T I S $4.50 O A R N L


Used in Reactor Neutron Dosimetry. Vlasov, M. I A E A - 2 0 8 , VOL. I , PP.353-360 A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE A U S T R I

6821 Date 1978 122100 870079 Evaluation of the Capture Cross Section of 197-Au. Mughabghab, S.F. I A E A - 2 0 8 , VOL. I , PP.395-406 A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE B R O O K H

8032 Date September 1978 111210 122100 312000 32A000 511110 512210 717000

830000 842000 853100 861000 882000 Macroscopic Cross Section Sensitivity Study for Fusion

Reactor Shielding Experiments. Seki, Y. ; Santoro, R.T.; Oblow, E.M.; Lucius, J.L. O R N L - 5 4 6 7 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8113 Date August 1978 122100 870001 Neutron Cross-Sections of Deuterium in the Energy Range

0.0001 e V - 1 5 MeV. Bazazyants, N.O.; Zabrodskaya, A.S.; Larina, A.F.; Nikola-

ev, M .N . I N D C ( C C P ) - 107/L A V A I L A B I L I T Y - I A E A N U C L E A R D A T A SECTION,

K A R N T N E R R I N G 11, A - 1 0 1 0 V I E N N A IAEA

8147 Date October 1978 122100 870094 Multi level Resonance Parameters of Plutonium-241.

(Tech. Note) Weston, L.W.; Todd, J.H. N U C L . SCL ENG., 68(1), 125-128 O A R N L

8148 Date October 1978 122100 882000 Best Values for the Cross Section of the Neutron Standard

Reaction 10-B(n,alpha sub 1 ) * * 7 - L i * in the Range from 0.1 to 2.0 Mev. (Tech. Note)

Liskien, H.; Wattecamps, E. N U C L . SCL ENG., 68(1), 132-137 B E L G I U

8222 Date May 17, 1978 122100 122200 810000 The L L L Evaluated Nuclear Data Library ( E N D L ) :

Descriptions of Individual Evaluations for Z = 0 - 9 8 . Howerton, R.J.; MacGregor, M . H . UCRL-50400 , VOL.15, 'PT.D, REV . l A V A I L A B I L I T Y - N T I S L A L L

6889. .<: Date June 1978 ^ 010000 122100 810000 <!) A n Index to the Literature on Microscopic Neutron Data. I A E A C I N D A 78 - SUPPL.4 TO C I N D A 76/77 A V A I L A B I L I T Y - I A E A , A U S T R I A I A E A


etry to 44 MeV. Greenwood, L.R. A N L / F P P / T M -115 1

73

A V A I L A B I L I T Y - N T I S $4.50 A R G O N N

8498 Date January 1979 122100 870090 870095 H E D L Evaluation of Thorium Cycle Cross Sections for

E N D F / B - V . Mann, F .M. H E D L - T M E - 7 8 - 1 0 0 A V A I L A B I L I T Y - N T I S H A N F O R

8576 Date November 1978 020000 010000 122100 122310 713000 810000 Nuclear Data Needs for Fast Breeder Reactor Shielding. Oblow, E.M.: Perey, F.G. C O N F - 7 8 1 1 1 7 - 5 A V A I L A B I L I T Y - D E P . , N T I S N O A R N L

8629 Date 1977 111110 122100 210000 810000 421140 Differential Neutron Data for Reactor Dosimetry. Paulsen, A.; Magurno, B.A. ^ EUR-5667E/F .PT . I I , PP.93-111;

CONF-750935,PT. I I , PP.93-111 A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L P U B L I C A -


B E L G I U "

8681 Date October 31, 1978 122100 122200 810000 The L L L Evaluated-Nuclear-Data Library ( E N D L ) :

Graphs of Cross Sections from the Library. Howerton, R.J.; Cullen, D.E.; MacGregor, M . H ; Perkins,

S.T.; Plechaty, E.F. UCRL-50400 , VOL. 15,PT.B,REV. 1 A V A I L A B I L I T Y - N T I S « L A L L

8772 Date January 1979 122100 122200 810000 Summary Documentation of L A S L Nuclear Data Evalua-

tions for E N D F / B - V . Young, P.G. L A - 7 6 6 3 - M S A V A I L A B I L I T Y - L O S A L A M O S S C I E N T I F I C LABO-

R A T O R Y , P.O. B O X 1663, LOS A L A M O S , N E W M E X I C O 87545

L O A S L

I)


Hydrogen, Carbon, Nitrogen and Oxygen in the Energy Range 20 -50 MeV.

Dimbylow, P.J. N R P B - R 7 8 A V A I L A B I L I T Y - H M S O E N G L A N

8808 Date Apr i l 1979 111220 122100 810000 Status of E N D F / B - V Neutron Emission Spectra Induced

by 1 4 - M e V Neutrons. He'r ick, D.M.; Larson, D.C.; Fu, C.Y. O R N L / T M - 6 6 3 7 ; E N D F - 2 8 0 A V A I L A B I L I T Y - N T I S $4.50 O A R N L •

8823 Date September 1978 122100 870006 Neutron Scattering Cross Sections of Carbon -Below 2 MeV

„ Recommended from R - Matr ix Fits to Data. U

Fu, C.Y.; Perey, F.G. A T O M I C D A T A A N D N U C L . D A T A TABLES, 22(3),

249-267 o O A R N L

8837 Date September 1978 010000 122100 810000 Nuclear Data for Reactor Design, Operation and Safety. Rowlands, J.L. o CONF-780921, PP.7-27 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - ; P A S C A L ,

75775 PARIS CEDEX 16, F R A N C E E N G L A N

0 ^ 8838 Date September 1978

010000 122100 122200 810000 Nuclear Data for Reactor Shielding. . Butler, J. " o CONF-780921, PP.28-60 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,


//

8839 Date September 1978 010000 122100 810000 Non-Prol i ferat ion and Nuclear Data. Sowerby, M.G. CONF-780921, PP.61 —75 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, F R A N C E cf

74- 0

E N G L A N

8840 Date September 1978 010000 122100 122310 870006 870092 Covariance Matrices of Experimental Data. Perey, F.G. CONF-780921, PP.104- 115 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, F R A N C E O A R N L

8841 Date September 1978 010000 122100 122310 810000 Correlated Uncertainties in Integral Data. McCracken, A.K. CONF-780921, PP.116-135 W A 1 L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,


8846 Date September 1978 010000 122100 870090 870092 870094 Cross-Sections of the Major Transactinium Isotopes in the

Resonance Region. Keyworth, G.A.; Moore, M.S. CONF-780921, PP.241 -267 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, F R A N C E L O A S L

0 " 8847 Date September 1978

010000 122100 861000 862000 o o Resonance Cross Sections for Structural Material. Frohner, F.H. , CONF-780921, PP.268-2B7 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,



Nuclear Data Aspects. Kusters, H.; Lalovic, M.; Wiese, W.H. CONF-780921, PP.518-550 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,


( c8854. Date September 1978 ° „ 010000 122100 122200 220000 312000 32A000 760000

795207 795254 845000 870006 870008 793000

Nuclear Data Requirements for the Calculation of Absorbed Dose and Simulation of Tissue Response in Neutron Therapy.

Pfister, G.; Hehn, G.; Mattes, M. ; Fricdlein, H.P. CONF-780921, PP.621-627 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,


8855 Date September 1978 010000 122100 210000 760000 845000 Basic Nuclear Data for Dosimtlry in Radiotherapy and

Radiobiology. Ricourt, A.; Chemtob, M.; Nguyen, V.D.; Parmentier, N. CONF-780921, PP.628-635 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,


8857 Date September 1978 010000 122100 210000 760000 845000 Nuclear Data for Radiotherapy with Neutrons. Cross, W.G. CONF-780921, PP.648-666 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, F R A N C E C A N A D A

8858 Date September 1978 010000 122100 210000 760000 845000. Recent Trends in Nuclear Reaction Data Needs for Nuclear

Medicine., c, Stocklin, G.; Qaim, S.M. CONF-780921, PP.667-687 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,


8864 Date September 1978 010000 122100 810000 ' «0 Nuclear Data for Safeguards. Fuketa, T. CONF-780921, PP.922-940 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, F R A N C E f A P A N

" Q 8869 Date September 1978

010000 122100 717000 810000 Nuclear Data for Fusion Reactors. « Jarvis, O.N. CONF-780921, PP.1073-1087 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, F R A N C E " 0

E N G L A N


nix Project. Darrouzet, M.; Fabbri, F.; Fort, E.; Krebs, J.; Langlet, J.;

Martin-Deidier, L.; Montaguti, A.; Menapace, E.; Motta, M.; Panini, G.C.; Reffo, G.; Ribon, P.; Thuong, T.Q.; Vaccari, M.; Ventura, A.


75775 PARIS CEDEX 16, FRANCE FRANCE

8874 Date 1978 122100 870094 Review of Microscopic Neutron Cross Section Data for the

/•Higher Plutonium Isotopes in the Resonance Region. Weston, L.W. CONF-781174-4 A V A I L A B I L I T Y - D E P . , NTIS O A R N L

8964 Date June 1979 010000 112120 122100 719AOO Symposium Summary: Nuclear Data Problems for,Thermal

Reactor Applications. 1,1

Rose, P.F.; Pearlstein, S.;,Ozer, O. E P R I - N P - 1098-SY A V A I L A B I L I T Y - N A T I O N A L NUCLEAR DATA

CENTER, BROOKHAVEN N A T I O N A L LABORA-TORY, UPTON, NEW YORK 11973

BROOKH

8968 Date Apri l 1979 122100 870092 Determination of the Errors in Evaluated Data with Allow-

ance for Correlations. Evaluation of U - 2 3 5 Fission Cross-Sections, alpha (235-U) , alpha(239-Pu) and 239-Pu Fission Cross-Sections for the Evaluated Nuclear Data Library BOYaD-3.

Kon'shih, V.A.; Sukhovitskij, E.Sh.; Zharkov, V.F. INDC(CCP)-132/LV 0

A V A I L A B I L I T Y - I A E A NUCLEAR'DATA SECTION, K A R N T N E R R ING 11, A-1010 V I E N N A

RUSSIA 11 0

8902 Date 1979 121100 122100 870012 870013 870029 870040 Evaluation of the Cross-Sections for the Reactions 2 4 - M g

(n,p) 24-Na, 64 -Zn (n,p) 64-Cu, 63-Cu (n,2n) 62-Cu and 9 0 - Z r (n,2n) 89-Zr .

T°vsen, S.; Vonach, H.; Strohmaier, B. PHYSICS D A T A - N R . 1 3 - 1 A V A I L A B I L I T Y - I S S N 0344-8401 G E R M A N J

IJ 9021 Date Apri l 1979

122100 870040 > ^ Calculation of Neutron Cross Sections on Isotopes of

Yttr ium and Zirconium. Arthur, E.D. L A - 7 7 8 9 - M S Cr

c

A V A I L A B I L I T Y - N T I S LOASL «

o

8906 Date October 17, 1978 121100 122100 810000 \< ACTL: Evaluated Neutron Activation Cross Section

L ibrary- -Evaluation Techniques and Reaction Index. Gardner, M.A.; Howerton, R.J. UCRL-50400, VOL.18 A V A I L A B I L I T Y - N T I S L A L L

9263 Date May 1979 122100 870095 A Review'of the Microscopic Cross Sections for the Ameri-

cium Isotopes in the Resolved Resonance Region. Browne, J.C. B N L - 50991 ,PP. 17-32; CONF-781174,PP. 17-32 A V A I L A B I L I T Y - N T I S L A L L

8963 Date Apri l 1979 122100 887000 Evaluation and Testing of Actinide Cross Sections. Benjamin, R.W. " " EPRI -NP-1067 A V A I L A B I L I T Y - S A V A N N A H RIVER LAB., E.I. DU

PONT DE NEMOURS A N D CO., INC., AIKEN,c

S.C. 29801 , _ o DUPONT °

9264 Date May 1979 122100 870095 Evaluation of 241-Am Resonance Parameters and Their

Consequences for the Unresolved Region. c

Derrien, H.; Fort, E.; Lafond, D. BNL-50991,PP.71 -81; CONF-781174,PP.71-81 " A V A I L A B I L I T Y - N T I S " FRANCE

G

,9265 Date May 1979 122100 122310 870094 u 242-Pu: Preliminary Evaluation with [Consideration of

240 -Pu and Some Sensitivity Results. •, Jary, J.; Lagrange, Ch.; Philis, C. („ BNL-5099LPP.83 -131; CONF-781174,PP.83r-131 A V A I L A B I L I T Y - N T I S F R A N C E

9266 Date May 1979 122100 870094 Evaluation of High Plutonium Isotopes for the German

Nuclear Data File Kedak. Goel, B. BNL-50991,PP. 165-176; CONF-78U74.PP.165-176 A V A I L A B I L I T Y - N T I S G E R M A N

9267 Date May 1979 122100 870094 Evaluation of n plus 242-Pu Reactions from 10 keV to 20

MeV. Madland, D.G.: Young, P.G. B N L - 50991 ,PP. 189 - 230; C O N F - 781174,PP. 189 - 230 A V A I L A B I L I T Y - N T I S L O A S L

9268 Date May 1979 122100 870094 242-Pu Evaluation in the Resolved Resonance Region. Menapace, E.; Motta, M.; Ventura, A. BNL-50991,PP.251 -274; CONF-781174,PP.251 -274 A V A I L A B I L I T Y - N T I S I T A L Y

9269 Date May 1979 122100 870094 870095 H E D L Evaluation of High Plutonium and Americium Cross

Sections for E N D F / B - V . Mann, F.E.; Schenter, R.E. BNL-50991,PP.275-286; CONF-781174,PP.275-286 A V A I L A B I L I T Y - N T I S H A N F O R

9274 Date January 1979 122100 870036 E N D F / B - V Neutron Cross Section Evaluation for the

Krypton Isotopes. Prince, A. B N L - N C S - 5 1 0 2 8 ; E N D F - 2 7 9 A V A I L A B I L I T Y - N T I S S5.25 B R O O K H

9366 Date March 1979 122100 810000 Graphs of Neutron Cross Section Data for Fusion Reactor

Development. Asami, T.; Tanaka, S. J A E R I - M - 8 1 3 6 A V A I L A B I L I T Y - D I V I S I O N OF T E C H N I C A L

I N F O R M A T I O N , J A P A N A T O M I C ENERGY RESEARCH INST ITUTE, T O K A I - M U R A , N A K A - G U N , I B A R A K I - K E N , JAPAN

JAPAN,

9369? Date July 1979 122100 870004 O Evaluated Data for n plus 9 - B e Reactions. Young, P.G.; Stewart, L. L A - 7 9 3 2 - M S ; E N D F - 2 8 3 A V A I L A B I L I T Y - N T I S LOASL

9432 Date October 1979 010000 122100 810000 W R E N D A 79/80. World Request List for Nuclear Data. Muir , D.W. I N D C ( S E C ) - 7 3 / U R S F A V A I L A B I L I T Y - I A E A N U C L E A R D A T A SECTION,


9441 Date September 1979 112710 122100 610000 717000 793000 810000 G A M M O N Activation Library. Battat, M.E.; LaBauve, R.J.; Mui r , D.W? L A - 8 0 4 0 - M S A V A I L A B I L I T Y - D E P . , NTIS , PC A 0 3 / M F A01 LOASL


Be(d,n) Sources,,E /sub d / = 1 4 - - 4 0 MeV. Greenwood, L.R.; Heinrich, R.R. CONF-790125, PT.A, PP.473-477; J. N U C L E A R

MATER. , 85 A N D 86, A V A I L A B I L I T Y - N O R T H - H O L L A N D PUBLISH-

I N G C O M P A N Y - A M S T E R D A M A R G O N N ^

9491 Date 1979 111220 122100 121100 210000 717000 810000 «

o Helium Accumulation Fluence Dosimetry for Fusion Reac-tor Materials Irradiations. r

Kneff, D.W.; Farrar, H.. IV

77

CONF-790125, PT.A, PP.479-483; J. N U C L E A R M A T E R . , 85 A N D 86,

A V A I L A B I L I T Y - N O R T H - H O L L A N D PUBLISH-I N G C O M P A N Y - A M S T E R D A M

R O I

,9538 Date November 1979 122100 122200 220000 610000 531000 532000 Kerma Factors for Neutrons and Photons with Energies

Below 20 MeV. Singh, M.S. UCRL-52 ,850 A V A I L A B I L I T Y - N T I S L A L L

9574 Date August 1979 122100 123000 421140 794000 810000 Nuclear Data Guide for Reactor Neutron Metrology. Part

1: Activation Reactions. (1979 Edition) Zi jp, W.L. ; Baard, J.H. E C N - 7 0 A V A I L A B I L I T Y - N E T H E R L A N D S ENERGY

RESEARCH F O U N D A T I O N ECN, P.O. BOX 1, 1755 Z G PETTEN ( N H ) , T H E N E T H E R L A N D S

N E T H E R

9575 Date August 1979 122100 123000 421150 810000 Nuclear Data Guide for Reactor Neutron Metrology. Part

2: Fission Reactions. (1979 Edition) Z i jp , W.L.; Baard, J.H. E C N - 7 1 A V A I L A B I L I T Y - N E T H E R L A N D S ENERGY

RESEARCH F O U N D A T I O N ECN, P.O. BOX 1, 1755 Z G PETTEN ( N H ) , T H E N E T H E R L A N D S

N E T H E R

9705 Date July 1979 122100 810000 Status of the Nuclear Data Library K E D A K - 3 . Goel, B.; Krieg, B. K F K - 2 3 8 6 / I A V A I L A B I L I T Y - K E R N F O R S C H U N G S Z E N T R U M

K A R L S R U H E (F.R. G E R M A N Y ) , I N S T I T U T FUER N E U T R O N E N P H Y S I K U N D REAKTOR-T E C H N I K

G E R M A N


Program of the United States of America. (Introductory Paper N o . l )

Head, C.R. I A E A - T E C D O C - 2 2 3 , PP.1-7 A V A I L A B I L I T Y - M F O N L Y - I N I S M I C R O F I C H E

C L E A R I N G H O U S E , I A E A , W A G R A M E R -STRASSE 5, P.O. BOX 100, A - 1 4 0 0 V I E N N A , A U S T R I A

DOE

9781 Date December 1979 010000 111210 122100 717000 810000 Nuclear Data Requirements for Fusion Reactor Design -

Neutronics Design, Blanket Neutronics and Tr i t ium Breeding. (Review Paper N o . A l )

Constantine, G. I A E A - T E C D O C - 2 2 3 , PP.11-29 A V A I L A B I L I T Y - M F O N L Y - I N I S M I C R O F I C H E

C L E A R I N G H O U S E , IAEA , W A G R A M E R -STRASSE 5, P.O. BOX 100, A - 1 4 0 0 V I E N N A , A U S T R I A

E N G L A N

9784 Date December 1979 010000 111210 122100 210000 71 WOO 810000 Nuclear Data Needs for Radiation Damage Studies Rele-

vant to Fusion Reactor Technology. (Review Paper No.A4) " o

Qaim, S.M. I A E A - T E C D O C - 2 2 3 , PP.75-89 A V A I L A B I L I T Y - M F O N L Y - I N I S M I C R O F I C H E


G E R M A N l*

978 5 Date December 1979 010000 111210 122100 122200 717000 810000 Nuclear Data Requirements for Fusion Reactor Shielding.

.'(Review Paper No.A5) Abdou, M.A. I A E A - T E C D O C - 2 2 3 , PP.91-110 A V A I L A B I L I T Y - M F O N L Y - I N I S M I C R O F I C H E

C L E A R I N G H O U S E , IAEA, W A G R A M E R -STRASSE 5, P.O. BOX 100, A - 1 4 0 0 V I E N N A , A U S T R I A

U - G A

978 6 Date December 1979 010000 111210 717100 810000 122100 Neutron Data for Hybrid Reactor Calculations. (Review

Paper N0.A6) Markovskii, D.V.; Shatalov, G.E. I A E A - T E C D O C - 2 2 3 , PP.111-118

A V A I L A B I L I T Y - M F ONLY - IN IS MICROFICHE CLEARINGHOUSE, IAEA, WAGRAMER-STRASSE 5, P.O. BOX 100, A-1400 VIENNA, AUSTRIA

RUSSIA

9788 Date December 1979 010000 111210 122100 123000 717000 810000 Theoretical Approsch to Nuclear Data Required for Fusion

Reactor Calculations. (Review Paper No.B2) Seeliger, D. IAEA-TECDOC-223 , PP.139-152 A V A 1 L A B I L I T Y - M F ONLY - IN IS MICROFICHE

CLEARINGHOUSE, IAEA, WAGRAMER-STRASSE 5, P.O. BOX 100, A-1400 V IENNA, AUSTRIA

G E R M A N


tor Calculations. (Review Paper No.B3) Bhat, M.R. IAEA-TECDOC-223 , PP.153- 183 A V A I L A B I L I T Y - M F ONLY - IN IS MICROFICHE

CLEARINGHOUSE, IAEA, WAGRAMER-STRASSE 5, P.O. BOX 100, A-1400 V IENNA,

„ AUSTRIA BROOKH

9790 Date December 1979 010000 122100 717000 810000 Neutron Reaction Data in the MeV Range. (Review Paper

No.B4) Liskien, H. IAEA-TECDOC-223 , PP.185-197 A V A I L A B I L I T Y - M F ONLY - INIS MICROFICHE

CLEARINGHOUSE, IAEA, WAGRAMER-STRASSE 5, P.O. BOX 100, A-1400 V IENNA, AUSTRIA i-i

BELGIU

982 7 Date July 1979 020000 122100 122200 810000 ENDF/B Summary Documentation. Kinsey, R. (Comp.) BNL-NCS-17541 (ED.3); ENDF-201(ED.3) A V A I L A B I L I T Y - D E P . , NTIS, PC A 2 2 / M F A01 BROOKH

982 8 Date February 1979 122100 870024 Evaluation of Natural Chromium Neutron Cross Sections

for E N D F / B - V . Prince. A.; Burrows, T.W. BNL-NCS-51152 ; ENDF-286 A V A I L A B I L I T Y - N T I S S6.00 BROOKH

9832 .' Date May 1979 112120 122100 810000 Tables of>RCN-2 Fission-Product Cross Section Evalua-

tion. Volume^. (Nd and Pm Isotopes). Gruppelaar, H."""~ ECN-65 A V A I L A B I L I T Y - D E P . , NTIS (U.S. SALES ONLY) ,

PC A 0 8 / M F A01 NETHER

O 9834 Date March 1979

122100 870096 Curium-244 Neutron Data Evaluation. Caner, M.; Yiftah, S. IA-1353 A V A I L A B I L I T Y - S O R E Q NUCLEAR RESEARCH

CENTER, ISRAEL ATOMIC ENERGY COMMIS-SION, Y A V N E

ISRAEL

9837 Date June 1*978 122100 870096 Evaluation of Neutron Nuclear Data for 245-Cm. Igarasi, S.; Nakagawa, T. JAER1-M-7733 ( I N JAPANESE) A V A I L A B I L I T Y - D E P . , NTIS (U.S. SALES ONLY) ,

PC A04 /MF A01 JAPAN

9791. . / /?. . . . . « . : . . Date December 1979 010000 1112$ 122100 717000 810000 Status of 14-MeV Neutron Cross Section Data. (Review

Paper N0.B6) Csikai, J. IAEA-TECDOC-223 , PP.199-222 0

A V A I L A B I L I T Y - M F O N L Y - IN IS MICROFICHE CLEARINGHOUSE, IAEA, WAGRAMER-STRASSE 5, P.O. BOX 100, A-1400 V IENNA, AUSTRIA

H U N G A R

10057 Date May 1980 010000 122100 887000 0

Transactinium Isotope Nuclear Data - 1979. Proceedings of the Second Advisory Group Meeting on Transac-tinium Isotope Nuclear Data Organized by. the IAEA

3. and held in Cadarache, 2 - 5 May 1979. IAEA

K 79

IAEA-TECDOC-232 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE, IAEA, WAGRAMERSTRASSE 5, P.O. BOX 100, A-1400 V IENNA, AUSTRIA

IAEA

10066 Date May 1980 122100 810000 Graphs of the Cross Sections in the Recommended Monte

Carlo Cross-Section Library at the Los Alamos Scien-tific Laboratory.

Soran, P.D.; Seamon, R.E. L A - 8 3 7 4 - M S « AVAILABIL ITY - NTIS„$ 13.25 LOASL

10067 Date June 1980 122100 810000 Graphs of the Cross Sections in the Alternate Monte Carlo

Cross Section Library at the Los Alamos Scientific Lab-oratory.

Seamon, R.E.; Soran, P.D. L A - 8 3 9 4 - M S A V A I L A B I L I T Y - N T I S $4.00 LOASL

10076 Date September 1980 122100 870011 An Evaluation of Cross Sections for Neutron-Induced

Reactions in Sodium. Larson, D.C. ORNL-5662; ENDF-299 A V A I L A B I L I T Y - N T I S , PC A09/MF A01 OARNL

10078 Date September 1980 122100 861000 Evaluation of Resonance Parameters for Neutron Interac-

tion with Iron Isotopes for Energies up to 400 keV. Perey, C.M.; Perey, F.G. O R N L / T M -6405; ENDF-298 A V A I L A B I L I T Y - N T I S , PC A05 /MF A01 OARNL

Interactions of Radiation with Matter -Group Cross-Sections - Neutron // CATEGORY NUMBER 122110

Energy

6419 Date Dec. 1977 020000 122110 The Role of "Standard" Fine-Group Cross Section

Libraries in Shielding Analysis. Weisbin, C.R.; Roussin, R.W.; Oblow, E.M.; Cullen, D.E.;

White, J.E.; Wright, R.Q. CONF-770401, PP.472-481 AVAILABIL ITY-SCIENCE PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 OARNL

6420 Date Dec. 1977 020000 122110 Generation and Testing of Shielding Data Libraries for Fis-

sion and Fusion Technology. Caglioti.'E.; Mattes, M.; Nicks, R.; Penkuhn, H.; Hehn, G.;

Herrnberger, V. CONF-770401, PP.482-493 AVAILABIL ITY-SCIENCE PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 ITALY

6454 Date Dec. f977 122110 The Background Cross Section Approach to Generating

Group Constants for Shielding Calculations. MacFarlane, R.E.; Kidman, R.B.; Becker, M. CONF-770401, PP.762-769 AVAILABIL ITY-SCIENCE PRESS, 8 BROOKSTONE


6499 ". Date. 1976 111110 121100 122110 810000 ^ Twenty-Seven Group Cross Section Set Derived from

ENDF/B Library. Garg, S.B. (

e

BARC-892 AVAILABIL ITY-DEP. , NTIS (U.S. SALES ONLY) INDIA

6522 Date January 1978 111210 122110 122310 32A000 521130 717000 795042

870003 810000 The Consistency of Differential and Integral Thermonuclear

Neutronics Data. (Thesis) Reupke, W.A. < L A - 7 0 6 7 - T 0 "

c o 80

A V A I L A B I L I T Y - N T I S LOASL

6649 Date Apri l 1978 121100 122110 A Multigroup Formalism for Evaluation of Continuous

Slowing Down Theory Parameters. (Tech. Note) Parvez, A.; Becker, M . NUCL. SCI. ENG., 66(1), 134-140 U - N Y

6661 Date February 1978 010000 111110 122100 122110 713000 810000 Energy-Averaged Neutron Cross Sections ,of

Fast-Reactor Structural Materials. Smith, A.; McKnight, R.; Smith, D. A N L / N D M - 4 1 # A V A I L A B I L I T Y - N T I S A R G O N N f,

~~ 6662 Date No Date 111110 122110 122310 713000 810000 Results of Calculating the Physical Characteristics of a

Standard Fast Reactor with the OSKAR-75 System of Constants.

Bobkov, Yu":G.; Usachev, P.N. A N L - T R A N S - 1 0 8 6 ; FEI -659 ( I N RUSSIAN) A V A I L A B I L I T Y - N T I S RUSSIA

6676 Date February 1978 111110 122110 122310 325000 312000 521130 810000 Adjusted Neutron Spectra of STEK Cores for Reactivity

Calculations. Dekker, J.W.M.; Dragt, J.B.; Janssen, A.J.; Heijboer. R.J.;

Klippel, H.Th. ECN-35 A V A I L A B I L I T Y - N E T H E R L A N D S ENERGY

RESEARCH F O U N D A T I O N (ECN), 3 WESTERDUINWEG, PETTEN (NH) , T H E NETH-ERLANDS

NETHER

6690. . Date February 1978 1 >! 1220 122110 32A000 421000 521130^551110 760000

810000 795042 Nuclear Data Development and Shield Design for Neutrons

Below 60 MeV. Wilson'; W.B.=. L A - 7 1 5 9 - T ' , 0 A V A I L A B I L I T Y - N T I S LOASL':„•>. ' .,

6691. Date March 1978 , "111210 122110 521130 522130 717000 793000 810000 Riggatron Nucleonics: One-Dimensional Analysis. Wienke, B.R.; Dudziak, D.J.; Bosler, G.E. L A - 7 1 8 3 - M S -A V A I L A B I L I T Y - N T I S LOASL

6758 Date March 1978 111110 122110 325000 511110 794000 810000* Differences Between L A S L - and ANL-Processed Cross

Sections. Kidman, R.B.; MacFarlane, R^E.; Becker; M. L A - 7 L 9 L - M S A V A I L A B I L I T Y - N T I S S8.00 LOASL

6802 Date June,l 978 ' 122110 The Background Cross Section Method as"a General Tool (,'

for Reactor Analysis. MacFarlane, R.E.; Kidman, R.B.; LaBauve, R.J.; Becker,

„ M . f, CONF-780401, PP.329-339 A V A I L A B I L I T Y - NTIS LOASL fJ

i «

6847 v . . . Date 1978 l l l f l O 122110 421140 Comparison of D E T A N - 7 4 and E N D F / B - I V Cross Sec-

tion Data in 620 Groups. Zijp, W.L.; Nolthenius, H.J.; Rieffe, H.Ch. IAEA-208 , VOL.11. PP.349-373 A V A I L A B I L I T Y - I N I S M ICROFICHE CLEARING-

HOUSE NETHER

0

6899 Date October 1977 e 111110 122110 421140 430000 521230 719AOO 795112

'' <795233 810000 Neutron Metrology jn the L.F.R. Neutron Flux Density

Spectrum in the Inner Graphite Reflector of the L.F.R. Zsolnay, E.M. ECN-77 -134 (RESTRICTED DISTRIBUTION)

vV A V A I L A B I L I T Y - S T I C H T I N G .ENERGIEONDER-ZOEK CENTRUM N E D E R L A N D (ECN), VOORTZETTING V A N DE ST ICHTING REAC-

o TOR CENTRUM (RCN), WESTERDUINWEG 3, PETTEN (NH) , T H E N E T H E R L A N D S

NETHER

" o 81

7048 Date April I, 1977 121100 122110 ^ „ <&, Neutron-Induced Angular and Energy Distributions:

Graphi'.dl Experimental Data. Cullen, D.E.; Howerton, R.J.; MacGregor, M.H.; Perkins,

S.T. " UCRL-50400 (VOL.19) A V A I L A B I L I T Y - N T I S LALL - .

! 7129 Date March 1977 111130 111400 122110 122210 32A000 511110 512210

830000 853100 810000 Production and Testing of the D N A Few-Group Coupj^-1

Neutron-Gamma Cross-Section Library. Bartine, D.E.; Knight, J.R.; Pace, J .V , I I I ; Roussin, R. O R N L / T M - 4 8 4 0 ' i A V A I L A B I L I T Y - D E P . , NT IS $5.50 O A R N L " t

7050 Date September 1977 111210; 122110 122210 32AOOO 312000 521130 522130

717000 810000 Cross-Section Sensitivity Analyses for a Tokamak Experi-

mental Power Reactor. Simmons, E.L.; Gerstl, S.A.W.; Dudziak, D.J. L A - 6 9 4 2 - M S A V A I L A B I L I T Y - N T I S $5.00 &

LOASL '

8023..., Date June 1978 -111110 122110 511110 551110 713000 793000 794000

0122310 E N D F / B - I V , L I B - I V , and the CSEWG Benchmarks. Kidman, R.B. L A - 7 3 5 5 - M S A V A I L A B I L I T Y - L O S A L A M O S SCIENTIFIC) L A B ,

P.O. BOX 1663, LOS ALAMOS, 'N .M. 87545 LOASL dj

7061 Date January 1977 122110 870090 870092 Nuclear Theory Based Cross Sections of Th-232, Th-233

and U - 2 3 3 and Their Applications in Reactor Technol-ogy:,

Garg, S.B.; Kumar, .A., , NBS SPEC. PUB. 461, PP. 70-73 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


" 0 l> 7100 Datcpuly 1976

111110 122110 32A000 511110 810000 Using the Method of Subgroups to Allow for the Resonance

Structure of Cross - Sections in Computations of the Passage of Neutrons Through Plane Layers of Shielding.

Germogenova, T.A.; Isayev, N.V.; Nikoiayev, M.N.; Khokhlov, V.F.

E R D A - T R - 125, PP. 17-24 A y A I L A B I L I T Y - N T I S RUSSIA

^ ^ 7121 Date July 1976 111110 121100 122110 810000 0

Analysis of Complete Neutron-Matter Interaction Cross Sections in Nuclear Reactor.

Yegorov, Yu.A.; Pankrat'yev, Yu.V.; Tolstykh, V.D. =r-, E R D A - T R - 1 2 5 , PP. 207-216 ' " " A V A I L A B I L I T Y - N T I S RUSSIA

8035 Date August 1978 111220 122110 32A000 511110'853900 853700 861000

512210 793000 Neutron-Photon Multigroup Cross Sections for Neutron^

Energies to 60 MeV^ „ " Alsmiller, R.G,Jr. V a o O R N L / T M - 6 4 8 6 "" A V A I L A B I L I T Y - N T I S $4.50 ° O A R N L

O

8114 Date August 1 9 7 ^ 0

111110 122110 713000 810000 . Q

Preparation of Nuclear Data for Detailed Calculation of the Neutron Spectrum in Fast Systems.

Vozyakov, V.V.; Voropaev, A.I.; Abdullaev, Kh .Sh^ /o ro -tyntsev, M.F.; Van'kov, A.A.; Krivtsov, A.S.; Pivovarov, V.A.

INDC(CCP) - 124/LV A V A I L A B I L I T Y - I A E A NUCLEAR DATA SECTION,

K A R N T N E R R ING 11, A-1010 VIENNA?' 1: IAEA o ?

8115. . . Date February 1978 111110 122110 793000 810000 - = Multigroup and Few-Group Cross Sections for

E N D F / B - I V Fission Products; theTOAFEW Collaps Data of ing_ Code and Data File

Fission -ProductcCross Sections. Wilson, W.B.; England, T.R.; LaBauve, R.J.

' ' L A - 7 1 7 4 - M S A V A I L A B I L I T Y - D E P , NTIS LOASL

154-Group

V

82

8201 Date March 1975 111110 122110 713000 810000 Nuclear Data and Multigroup Methods in Fast Reactor Cal-

culations. Gur, Y. IA -1312; THESIS A V A I L A B I L I T Y - I S R A E L A T O M I C ENERGY COM-

M I S S I O N ISRAEL

8223 Date May 18, 1978 111110 121100 122110 810000 Bondarenko Self-Shielded Cross Sections and Multiband

Parameters Derived from the L L L Evaluat-ed-Nuc lear -Data Library (ENDL) .

Cullen, D.E. UCRL-50400, VOL.20 A V A I L A B I L I T Y - N T I S L A L L

o 8252 Date November 1978

122110 122310 A Generalized Treatment of Heterogeneity Effects for the

Shielding Factor Method. Kujawski, E.; Protsik, R. N U C L . T E C H N O L O G Y , 41(1), 36-45 GEE

8395 y Date December 1978 122110 Detailed Calculations in Energy and Space of Effective Neu-

- tron Resonance Cross Sections. Aragones, J.M. NUCL . SCL ENG., 68(3), 281-289 SPAIN

8401 Date July 1978 121100 121200 122110 122210 220000 531000 532000

794000 810000 M A C K - I V , A New Version of M A C K : A Program to Cal-

culate Nuclear Response Functions from Data in E N D F / B Format.

Abdou, M.A. ; Gohar, Y.; Wright, R.Q. A N L / F P P - 7 7 - 5 A V A I L A B I L I T Y - N T I S $6.00 A R G O N N (>'

8403 Date March 1978 122110 122210 220000 531000 532000 793000 794000

810000 M A C K L I B - I V - A Library of Nuclear Response Func-

tions Generated with the M A C K - I V Computer Program from E N D F / B - I V .

Gohar, Y.; Abdou, M .A . A N L / F P P / T M - 1 0 6 A V A I L A B I L I T Y - N T I S $9.25 A R G O N N

8462 Date October 1978 122110 Multiband Calculations of Neutron and Photon Transport. Cullen, D.E. U C R L - 5 2 0 0 0 - 7 8 - 1 0 , PP.25-33 A V A I L A B I L I T Y - N T I S $4.00 L A L L

8514. . . . ^ . . 122110 122210 810000

An

Date February 1979

E N D F / B - V Mult igroup V I T A M I N - E : 0 Cross-Section Library for L M F B R Core and Shield,

L W R Shield, Dosimetry, and Fusion Blanket Technolo-o gy-

Weisbin, C.R.; Roussin, R.W.; Wagschal, J.J.; White, J.E.; Wright, R.Q.

O R N L - 5 5 0 5 ; E N D F - 2 7 4 ' A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8515 Date January 1979 111110 122110 32A000 521130 522130 794000 122210 Sample Problems for the Novice User of the A M P X - 1 I

System. " , , 6

Ford, W.E.,111; Roussin, R.W.; Petrie, L.M.; Diggs, B.R.; Comolander, H.E.

O R N L / C S D / T M - 7 2 ( A M P X - 7 ) A V A I L A B I L I T Y - N T I S $9.25 O A R N L

8516 Date February 1979 112120 122110 123000 532000 795217 Updated Decay and Photon Libraries for the ORIGEN

Code. Croff, A.G.; Haese, R.L.; Gove, N.B. O R N L / T M - 6 0 5 5 A V A I L A B I L I T Y - N T I S $6.50 O A R N L

8637 Date 1977 111110 122110421140 795112 Neutron Selfshielding of Activation Detectors Used in Spec-

trum Unfolding. Zi jp, W.L.; Nolthenius, H.J. E U R - 5667E/F,PT.II, PP.297-321;

CONF-750935,PT.I I , PP.297-321 A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L PUBL ICA-

T IONS OF T H E EUROPEAN C O M M U N I T I E S , BOITE POSTAL 1003 - L U X E M B O U R G

83

NETHER A V A I L A B I L I T Y - N T I S S5.25 OARNL

o

8640 Date 1977 111110 122110 421140 795112 Remarks on the Comparison of Cross Section Libraries for

Neutron Metrology. Zijp. 'W.L.; Nolthenius, H.J.; Appelman, K.H. EUR-5667E/F.PT.I I , PP.381-395;

CONF-750935,PT.II, PP.381-395 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-

TIONS OF T H E EUROPEAN COMMUNITIES, BOITE POSTAL 1003 - LUXEMBOURG

NETHER

86S2. : Date October 31, 1978 122110 810000 ' Tabular and Graphical Presentation of 175 Neu-

tron-Group Constants Derived, from the LLL Evaluated-Nuclear-Data Library (ENDL).

Plechaty, E.F.; Culien, D.E.; Howerton, R.J.; Kimlinger, J.R.

UCRL-50400, VOL.16,REV.2 A V A I L A B I L I T Y - N T I S L A L L

8770 Date January 1979 111110 122110 521130 713000 810000 Comparison of Some Multigroup Nuclear Data Sets on

Existing Fast Neutron Assemblies, Cuculeanu, V.; Mocioiu, D.; Constantinescu, D. I N D C ( R U M ) - 9 / G V „ " A V A I L A B I L I T Y - I A E A NUCLEAR DATA SECTION,

K A R N T N E R R I N G 11, A-1010 V I E N N A ROMAN1

8873 Date September 1978 122110 122310 861000 The Linearity Assumption in Adjustment Procedures: Is It

a Real Problem? Yeivin, Y. CONF-780921, PP.1172-1177 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL,

75775 PARIS CEDEX 16, FRANCE ISRAEL

8975. . Date June 1979 111110 122110 122310 810000 Specifications for Adjusted Cross Section and Covariance

Libraries Based upon CSEWG Fast Reactor and Dosim-etry Benchmarks.

Weisbin, C.R.; Marable, J.H.; Collings, P.J.; Cowan, C.L.; Peelle, R.W.; Salvatores, M.

ORNL-5517

8977 Date January 1979 122110 DOWNER (Version 79-1) : Group Collapse Cross.Section /

and Transfer Matrices. Cullen, D.E. UCRL-50400,VOL.17, PT.F A V A I L A B I L I T Y - N T I S L A L L //

9000 Date July 1979 122110 A Correlation Technique for Resonance Calculations.

(Tech. Note) Gregory, M.V. j, NUCL. SCL ENG., 71(1), 59-64 DUPONT

9065 Date August 1979 122110 510000 795180 Discrete Transfer Cross-Section Expansion for

Time-Dependent Neutron Transport. Beranek, F.; Conn, R.W. NUCL. SCL ENG., 71(2), 100-110 U - W I

9071 Date 1977 111110 112110 122110 328000 329000 511110 512110

795203 830000 Order of Scattering Calculations of Photon and Neutron

Transport. De Gangi, N.L. THESIS A V A I L A B I L I T Y - M A T H E M A T I C A L APPLICA-

TIONS GROUP, INC., 3 WESTCHESTER PLAZA, ELMSFORD, N.Y. 10523

M A A G

9093 Date 1979 122110 32AOOO 794000 870079 Range Calculations Using Multigroup Transport Methods. Hoffman; T.J.; Robinson, M.T.; Dodds, H.L.,Jr. CONF-790125-57 AVAILABIL ITY-DEP. , NTIS O A R N L

9098 Date 1978 122110 122310 32A000 312000 Lecture Notes on Cross-Section Adjustment Procedures.

(Nuclear Science'and Technology)

84

Yeivin, Y.: Matthes, W. EUR-6041EN AVAILABIL ITY-OFF ICE FOR OFFICIAL PUBLICA-

TIONS OF THE EUROPEAN COMMUNITIES, BOITE POSTALE 1003 - LUXEMBOURG

ISRAEL

9155 Date 1979 122110 Multigroup P8 - Elastic Scattering Matrices of Main Reac-

tor Elements. Garg, S.B.; Shukla, V.K. B.A.R.C.- 1001 AVAI L A B I L I T Y - B H A B H A ATOMIC RESEARCH

CENTRE, BOMBAY, INDIA INDIA

9156 Date 1979 122110 Multigroup Resonance Self-Shielding Factors and

Cross-Sections of Main Reactor Elements. Garg, S.B. B.A.R.C.-1002 A V A I L A B I L I T Y - B H A B H A ATOMIC RESEARCH

CENTRE, BOMBAY, INDIA INDIA

9362 Date September 1979 122110 122310 F F Ferret Data Analysis Code.

y Schmittroth, F. ' H E D L - T M E - 7 9 - 4 0 A V A I L A B I L I T Y - H A N F O R D ENGINEERING

DEVELOPMENT LAB., RICHLAND, WASHING-TON

HANFOR

h 9442 Date November 1979

112400 112500 112600 122110 122210 794000 810000 Comparison of Photon-Production Processing Codes

LAPHNGAS, M A C K - I V , and NJOY. Barrett, R.J.; Ford, W.E.,III; Gohar, Y.; Bohn, T.S.; Mac-\V

Farlane, R.E.; Boicourt, R.M. V .LA-8100-MS; ENDF-288 A V A I L A B I L I T Y - N T I S LOASL

GA - A - 15009( VOL. 1) AVAILABIL ITY-DEP. , NTIS, PC A09/MF A01 GEAC

9933 Date May 1980 111110 122110 122210 711100 793000 794000 810000 FCXSEC: Multigroup Cross-Section Libraries for

Nuclear Fuel Cycle Shielding Calculations. Ford, W.E.,III; Webster, C.C.; Diggs, B.R.; Pevey, R.E.;

Croff, A.G. ORNL/TM-7038; ENDF-287 A V A I L A B I L I T Y - N T I S OARNL

9934 Date June 1980 122110 122310 Processing ENDF/B-V Uncertainty Data into Multigroup

Covariance Matrices. Smith, J.D.,III ORNL/TM-7221 (, A V A I L A B I L I T Y - N T I S OARNL

9991 Date,August 1980 111110,122110 329000 711100 793000794000 810000 KENO Calculations of Light Water Fuel Lattices. Hebert, M.J.; Handschuh, J.A.; Pilat, EE.; Harris, D.R.;

Mayer, J.A. Z ORNL/RSIC-44, PP.107-120 A V A I L A B I L I T Y - N T I S , PC A16/MF A01 YAAEC

9992 Date August 1980 010000 122110 3 29000 712000 KENO V - The Newest KENO Monte Carlo Criticality

Program. Landers, N.F.; Petrie, L.M. ORNL/RSIC-44, PP.121-128 A V A I L A B I L I T Y - N T I S , PC A16/MF A01 OARNL

# Interactions of Radiation jvith Matter - Cross

Section Evaluation or Compilation - Gamma-Ray and X-Ray


9700 Date December 1979 111110 122110 330000 MICROX-2 : An Improved Two-Region Flux Spectrum

' Code for the Efficient Calculation of Group Cross Sec-tions.

Mathews, D.; Koch, P.

6510 Date 1976 020000 111110 111210 111220 122100 122200 810000

845000 Basic Physical Data for Neutron Dosimetry. Broerse, J.J. (Ed.) EUR-5629

85

A V A I L A B I L I T Y - I N I S N E T H E R

6808 Date 1978 010000 111110 122200 210000 421140 430000 511120

810000 i, . Neutron Cross Sections for Reactor Dosimetry - Review

Papers. Summary Report. Vlasov, M.F. (Ed.) I A E A - 2 0 8 , VOL. I , PP.1-49 A V A I L A B I L I T Y - I N I S M I C R O F I C H E CLEARING-

HOUSE I A E A

8222 Date May 17, 1978 122100 122200 810000 The L L L Evaluated Nuclear Data Library ( E N D L ) :

Descriptions of Individual Evaluations for Z = 0 - 9 8 . Howerton, R.J.; MacGregor, M.H. UCRL-5040C, VOL.15, PT.D, REV. l A V A I L A B I L I T Y - NT IS L A L L „ (j

8681 Date October 31, 1978 122100 122200 810000 > f( If

6809 Date 1978 010000 111 110 410000 122200 511120 421140 770000

430000 ' ' Benchmark Neutron Fields for Reactor Dosimetry. Grundl, J.; Eisenhauer, C. I A E A - 2 0 8 , VOL. ! , PP.53-104 A V A I L A B I L I T Y - I N I S M I C R O F I C H E CLEARING-

HOUSE

/

6851. Date May 1978 010000 122200 810000 Compilations and Evaluations of Data on the Interaction of

Electromagnetic Radiation with,Matter. Lorenz, A. (Comp.)c I N D C ( N D S ) - 9 4 / L N fv_ A V A I L A B I L I T Y - I A E A N L I N E A R D A T A SECTION,

K A R N T N E R R I N G 11, A -1010 V I E N N A I A E A c

6859 Date June 1978 122200 810000 X - R a y Fluorescence Cross Sections for K and L X - R a y s

of the Elements. ,;r Krause, M.O.; Nestor, C.W.,Jr.; Sparks; C.J.,Jr.; Ricci, E. O R N L - 5 3 9 9 ' <; ' ° A V A I L A B I L I T Y - N T I S $8.00 ! O A R N L 1

6936 Date June 1978 122200 810000 Total Photon Absorption Cross Section Measurements, The-

oretical Analysis and Evaluations for Energies Above 10 MeV.

Gimm, H.A.; Hubbell, J.H. NBS T N - 9 6 8 A V A I L AB1L ITY - SUPT. OF DOC., U.S. GOVERN-

M E N T P R I N T I N G OFFICE, W A S H I N G T O N , D.C. 20402 $2.40 ?

N A B S ;

t Lit The L L L Evaluated-Nuclear-Data\L ibrary (ENDL) : Graphs of Cross Sections from the Library.

Howerton, R.J.; Cullen, D.E.; MacGregor, M.H. ; Perkins, S.T.; Plechaty, E.F. c,

UCRL-50400, VOL. 15,PT.B,REV.l A V A I L A B I L I T Y - N T I S " L A L L

8772 Date January 1979 122100 122200 810000 Summary Documentation of L A S L Nuclear Data Evalua-

tions for E N D F / B - V . Young, P.G. L A - 7 6 6 3 - M S ^ ' A V A I L A B I L I T Y - L O S A L A M O S SCIENT IF IC LABO-

RATORY, P.O. BOX 1663, LOS A L A M O S , N E W M E X I C O 87545 u

LOASL

8812 Date December 7, 1978 122200 810000 J / Tables and Graphs of Photon-Interaction Cross Sections

from 0.1 keV to 100 MeV Derived from the L L L Evalu-ated-Nuclear-Data Library.

Plechaty, E.F.; Cullen, D.E.;,.Howerton, R.J. UCRL-50400, VOL.6, REV.2 ^ A V A I L A B I L I T Y - N T I S L A L L -

8822 Date August 1978 122200 613000 <' K and L X - R a y Mass Attenuation Coefficients for L o w - Z

Materials. Montenegro, E.C.; Baptista, G.B.; Duarte, P.W.E.P. A T O M I C D A T A A N D NUCL. D A T A TABLES, 22(2),

131-177 B R A Z I L

8828 Date February 1979 122200 423250 220000 845000 Dosimetry of Very Low Energy Photons. Reddy, A.R.; Mehta, S.C.

86

H E A L T H PHYSICS. 36(2), 175-182 I N D I A

//

8838 Date September 1978 010000 122100 122200 810000 Nuclear Data for Reactor Shielding. B,utler, J. CONF-780921, PP.28-60 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,


8842 Date September 1978 010000 122200 112400 112500 112600 810000 Photon Production in Neutron Induced Reactions, van Heerden, I.J. CONF-780921, PP.160-180 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, F R A N C E SAFRIC

„ 8844 Date September 1978 010000 122200 112710 810000 The UK Chemical Nuclear Data Files: An Evaluated Set of

Radioactive Decay Data for Reactor Applications. Davies, B.S.J.; Crouch, E.A.C.; James, M.F.; Nichols,

Parkinson, J.R.; Tobias, A.; Vallis, D.G. 6) CONF-780921, PP.209-214 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,


8845 Date September 1978 010000 112710 122200 810000 Bibliotheque de Donnees Nucleaires non Neutroniques des

Isotopes Radioactifs, Produits de Fission et Noyaux Lourds.

Blachot, J.; Fiche, Ch. / v

CONF-780921, PP.215-222 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,


8854 Date September 1978 010000 12lil00 122200 220000 312000 32AOOO 760000

795207 795254 845000 870006 870008 793000 Nuclear Data Requirements for the Calculation of Absorbed

Dose and Simulation of Tissue Response in Neutron Therapy. ^

Pfister, G.; Hehn, G.; Mattes, M.; Friedlein, H.P. n


75775 PARIS CEDEX 16, F R A N C E

G E R M A N


nix Project. Darrouzet, M.; Faobri, F.; Fort, E.; Krebs, J.; Langlet, J.;

Mart in-Deidier , L.; Montaguti, A.; Menapace, E.; Motta, M.; Panini, G.C.; Reffo, G.; Ribon, P.; Thuong, T.Q.; Vaccari, M. ; Ventura, A.

CONF-780921, PP.1146-1150 A V A I L A B I L I J Y - O E C D , 2, RUE A N D R E - P A S C A L ,


8911 Date 1978 112710 122200.421140 810000 Gam.-na-Ray Spectra of Neutron-Irradiated Activation

Detectors. Hogel, J. Z J E - 2 3 0 ,, A V A I L A B I L I T Y - S K O D A WORKS, N U C L E A R

POWER CONSTRUCTION DEPART., I N F O R M A -T I O N CENTRE, P L Z E N - C Z E C H O S L O V A K I A

CZECHO

9251 Date October 1979 122200 A Method for Data Evaluation with Lognormal Distribu-

tions. Schmittroth, F. N U C L . SCI. ENG., 72(1), 19-34 H A N F O R

9538 Date November 1979 122100 122200 220000 610000 531000 532000 Kerma Factors for Neutrons and Photons with Energies

Below 20 MeV. Singh, M.S. " ... v UCRL-5:',)850 A V A I L A B I L I T Y - N T I S L A L L


(Review Paper No.A5) 'J± Abdou, M.A. ;> -I A E A - T E C D O C - 2 2 3 , PP.91 -110 A V A I L A B I L I T Y - M F O N L Y - IN IS M I C R O F I C H E

CLEARINGHOUSE, IAEA, W A G R A M E R -STRASSE.5, P.O. BOX 100, A - 1 4 0 0 V I E N N A , A U S T R I A

U - G A

9789 Date December 1979 010000 111210 122100 122200 717000 717100 810000 , Evaluated Files of Nuclear Cross Sections for Fusion Reac-

tor Calculations. (Review Paper No.B3) Bhat, M.R. I A E A - T E C D O C - 2 2 3 , PP.153-183 A V A I L A B I L I T Y - M F O N L Y - IN IS M I C R O F I C H E

C L E A R I N G H O U S E , IAEA, „ W A G R A M E R -STRASSE 5, P.O. BOX 100, A - 1 4 0 0 V I E N N A , A U S T R I A

BROOK.H

9827 . Date July 1979 020000 122100 122200 810000 E N D F / B Summary Documentation. Kinsey, R. (Comp.) BNL-NCS-17541 (ED.3 ) ; ENDF-201(iED.3) A V A I L A B I L I T Y - D E P . , NTIS, PC A 2 2 / M F A01 <b

B R O O K H

Interactions of Radiation with Matter - Energy Group Cross-Sections - Gamma-Ray


6435 Date Dec. 1977 329000 122210 A Part ial-Range Expansion for Multigroup Monte Carlo

Photon Transport. Ward, J.T.,Jr.; Scudiere, M.B. CONF-770401, PP.613-621 J ft A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., P R I N C E T O N , NJ 08540 U " V A ^

' 1) 7050 Date SeptemberT 977 -J

111210 122110 122210 32AOOO 312000 521130 522130 ''717000 810000

Cross-Section Sensitivity Analyses for a Tokamak Experi-mental Power Reactor. 0

Simmons, EX . ; Gerstl, S.A.W.; Dudziak, D.J. L A - 6 9 4 2 - M S A V A I L A B I L I T Y - N T I S $5.00 L O A S L

7052 Date January 1977 112BOO 122210 810000 Present Status of Photon Cross Section Data 100 eV to 100

GeV. Hubbell, J.H.

NBS SPEC. PUB. 461, PP. 3 - 1 6 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

W A S H I N G T O N , D.C. 20402 NABS

7129 Date March 1977 111130 I I1400 122110 122210 32A000 511110 512210

830000 853100 810000 Production and Testing of the D N A Few-Group Coupled

Neutron-Gamma Cross-Section Library. Bartine, D.E.; Knight, J.R.; Pace, J.V.,I I I ; Roussin, R. O R N L / T M - 4 8 4 0 A V A I L A B I L I T Y - D E P . , NT IS $5.50 O A R N L <

/)

8004 Date March 1978 122210 326000 713000 Approximations of Gamma Cross Sections for Fast Nuclear

Reactors. Grimm, K.N.; Meneghetti, D. " j) A N L - 7 7 - 8 8 , " '' " A V A I L A B I L I T Y - N T I S $4.00 \ R G O N N

8401. .' Date July 1978 121100 121200 122110 122210 220000 531000 532000


culate Nuclear Response Functions from Data in ENDF/B" Format.

Abdou, M.A.; Gohar, Y.; Wright, R.Q. A N L / F P P - 7 7 - 5 A V / v . L A B I L I T Y - N T I S $6.00 A R G O N N „ " l !

8403 Date March 1978 122110 122210 220000 531000 532000 793000 794000



Gohar, Y.; Abdou^M.A. , A N L / F P P / T M -106 A V A I L A B I L I T Y - N T I S $9.25 ARGO'NN

8 514Ci Date February 1979 122110 122210 810000 V I T A M I N - E : An E N D F / B - V Multigroup

Cross-Section Library for L M F B R Core and Shield, L W R Shield, Dosimetry, and Fusion Blanket Technolo-gy-

Weisbin, C.R.; Roussin, R.W.; Wagschal, J.J.; White, J.E.; Wright, R.Q. , <'

88

ORNL.-5505; ENDF-274 A V A I L A B I L I T Y - N T I S $4.50 O A R N L ii

8515 Date January 1979 111110 122110 32A000 521130 522130 794000 122210 Sample Problems for the Novice User of the A M P X - I I

System. Ford, W.E.,111; Roussin, R.W.; Petrie, L.M.; Diggs, B.R.;

Comolander, H.E. O R N L / C S D / T M - 7 2 ( A M P X - 7 ) A V A I L A B I L I T Y - N T I S $9.25 O A R N L U

Cross-Section Evaluation by Integral Experiment, Sensitivity Study, or Calculational Analysis -

Neutron CATEGORY NUMBER 122310

6459 Date Dec. 1977 122310 861000 870011 Use of Integral Data for the Prediction of Neutron Propaga-

tion in Iron-Sodium Mixtures. Estiot, J.C.; Trapp, J.P.; Palmiotti, G.; Salvatores, M. CONF-770401, PP.804-811 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


9442 Date November 1979 112400 112500 112600 122110 122210 794000 810000 Comparison of Photon-Production Processing Codes

LAPHNGAS, M A C K - I V , and NJOY. Barrett, R.J.; Ford, W.E.,III; Gohar, Y.; Bohn, T.S.; Mac-

Farlane, R.E.; Boicourt, R.M. LA-8100.-MS; ENDF-288 " V A V A I L A B I L I T Y - N T I S ^ ^ LOASL

9862 Date Apri l 1978 121200 122210 32^.000 810000 Definition of Two Band Parameters for Use in Photon Trans-

port Calculations. Cullen, D.E. UCID-17774 A V A I L A B I L I T Y - N T I S , PC A02/MF A01 L A L L

9933 Date May 1980, 111110 122110 122210 711100 793000 794000 810000 FCXSEC: Multigroup Cross-Section Libraries for

Nuclear Fuel Cycle Shielding Calculations. Ford, W.E.,111; Webster; C.C.; Diggs, B.R.; Pevey, R.E.;

Crofl^A.G. O R N L / T M - 7 0 3 8 ; ENDF-287 A V A I L A B I L I T Y - N T I S O A R N L

6463 Date Dec. 1977 122310 870041 870098 430000 794000 Integral Tents of Niobium Cross Sections Through Simulta-

neous Measurements of Neutron and Gamma-Ray Leakage Spectra.

Ingersoll, D.T.; Doming, J.J.; Wehring, B.W. CONF-770401, PP.841-848 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6522 Date January 1978 111210 122110 122310 32A000 521130 717000 795042


Neutronics Data. (Thesis) Reupke, W.A. L A - 7 0 6 7 - T A V A I L A B I L I T Y - N T I S LOASL i.

O 6570 V ^ Date March 1978 122310 870092 An Evaluation of E N D F / B - I V and Hansen-Roach Ura-

nium-233 Cross Sections for Use in Criticality Calculations.

McNeany, S.R.; Jenkins, J.D. NUCL. SCI. ENG., 65(3), 441 -453 OARNL

9979 Date May 1980 112120 122210 793000 810000 PEFPYD - A Library of Aggregate Fission-Product

Decay Data Derived from E N D F / B - I V . LaBauve, R.J.; George, D.C. , L A - 8 3 6 5 - M S ^ A V A I L A B I L I T Y - N T I S $4.00 LOASL

6573 Date March 1978 122310 861000 Consistent Utilization of Shielding Benchmark Experiments. D'Angelo, A.; Oliva, A.; Palmiotti, G.; Salvatores, M.; Zero,

S. NUCL. SCI. ENG., 65(3), 477-491 I T A L Y

89

6584 rr ' . . . .<• Date 1976 111110 122310 713000 870092 870094 The Importance of Fast Fission Cross Sections in Fast Reac-

tors. Bohn, E.M.; McKnight, R.D. A N L - 7 6 - 9 0 , PP.31-44 A V A I L A B I L I T Y - N T I S A R G O N N

(i 6627 Date March 1978

122310 312000 521130 719A00 870092 870013 870001 870008 810000

A Compendium of Energy-Dependent Sensitivity Jrofiles for the T R X - 2 Thermal Lattice.

Tomlinson, E.T.; Lucius, J.L.; Drischler, JiD. ORNL-5336; ENDF-253 A V A I L A B I L I T Y - N T I S $8.00 O A R N L / /

6662 Date No Date 111110 122110 122310 713000 810000 Results of Calculating the Physical Characteristics of a

Standard Fast Reactor with the OSKAR-75 System of Constants. 0

Bobkov, Yu.G.; Usachev, P.N. A N L - T R A N S - 1 0 8 6 ; FEI-659 ( I N RUSSIAN) A V A I L A B I L I T Y - N T I S RUSSIA

6676 Date February 1978 111110 122110 122310 325000 312000 521130 810000 Adjusted Neutron Spectra cf STEK Cores for Reactivity

Calculations. Dekker, J.W.M.; Dragt, J.B.; Janssen, A,J.; Heijboer, R.J.;


RESEARCH FOUNDATION (ECN), 3 WESTERDUINWEG, PETTEN (NH) , THE NETH-ERLANDS r

NETHER »

6734. : Date May 1978 111210 122310 312000 521130 795204 717000 870006

870092 861000 Cross-Section Sensitivity Analysis of 235-U and 238-U

Fission Rates Measured in a Graphite-Reflected Lith-ium Assembly. (Tech. Note) "

Seki, Y.; Maekawa, H. NUCL. SCL ENG., 66(2), 243-251 JAPAN

&

6812 Date 1978 J ) 010000 430000 122310 795112 Spectral Characterization by Combining Neutron Spectros-

copy, Analytical Calculations, and Integral Measurements.

McElroy, W.N.; Gold, R.; Lippincott, E.P.; Faory, A.; Rob-erts, J.H.

IAEA-208, VOL.1, PP.147-181 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE ( J„ HANFOR

681 5 , Date 1978 010000 111.110 122310 5lii;'/20 810000 870092 870098 Review of Microscopic Integral Cross Section Data.in Fun-


Fabry, A.; McElroy, W.N.; Kellogg, L.S.; Lippincott, E.P.; Grundl, J.A.; Gilliam, D.M.; Hansen, G.E. < v

IAE^ -208 , VOL.1, PP.233-263 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE HANFOR^ !

681 6 P ' . Date 1978 111110 122310 421140 511120^10000 870092 870098 Ratios of Measured and Calculated Reaction Rates for

Some Known Spectra. Zijp, W.L.; Nolthenius, H.J.; Baard, J.H. ' IAEA-208, VOL.I, PP.265-300V

A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-HOUSE

NETHER • o

0 6695 Date Apri l 1978

111110 122310 311000 312000 719A00 795217 870092 870094 °

Sensitivity and Uncertainty Analysis for Functionals of Time-Dependent Nuclide Density Field.

Williams, M.L.; Weisbin, C.R. ORNL-5393; ENDF-263 t> A V A I L A B I L I T Y - N T I S $6.00 O A R N L

6818 Date 1978 010000 122310 210000 421140 Remarks Concerning the Accurate Measurement of Differ-

ential Cross Sections for Threshold Reactions Used in Fast-Neutron Dosimetry for Fission Reactors'

Smith, D.L. -IAEA-208, VOL.I, 321-351 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

o HOUSE „ Sc

ARGONNE C<

90

O o

6872 Date June 1978 122310 | ' \ Application of Sensitivity and Uncertainty Methodology to

Fast Reactor Integral Experiment Analysis. Weisbin, C.R.;'Oblow, E.M.; Marable, J.H.; Peelle, R.W.;

Lucius, J.L. NUCL. SCI. ENG., 66(3), 307-333 O A R N L Vl

6880 Date Ju 'y 1978 122310 870011 794000 ' i Interactive Graphics (Interpretation of Calculation Measure-

ment Discrepancies for Neutron Spectrum Measurements in Sodium.

Parvez, A.; Becker, M. NUCL. SCI. ENG., 67(1), 130-136 U - N Y

6976 Date August 1978 111110 122310 326000 511120 820000 870098 Spatial Distribution Measurements of Fiscjon Neutrons in

Water as an Oxygen Data Test. Green, L,; Ullo, J.J. NUCL. SCI. ENG., 67(2), 172-183 BETTIS

7031 Date September 1976 111210 122310 312000 32A000 511110 870003 717000 Neutronic Data Consistency Analysis for Lithium Blanket

Shield Design. Reupke, W.A.; Muir, D.W. CONF-760935-P3, PP. 861-871; L A - U R - 7 6 - 2 0 9 2 A V A I L A B I L I T Y - N T I S U - G A



Cramer, S.N.; Oblow, E.M. Q O R N L / T M - 5535 . A V A I L A B I L I T Y - N T I S $4.50 O A R N L

J v 7131 Date March 1977

020000 111110 122310 312000 32A000 810000 Compilation of Sensitivity Profiles for Several CSEWG Fast

Reactor Benchmarks. Marable, J.H.; Lucius, J.L.; Weisbin, C.R. ' ORND-5262; ENDF-234 A V A I L A B I L I T Y - E R D A , TIC, P.O. BOX 62, OAK

RIDGE, TENN. 37830

O A R N L

8023 Date June 1978 © 111110 122110 511110 551110 713000 793000 794000

122310.. E N D F / B - I V , L I f B- IV , and the CSEWG Benchmarks. Kidman, R.B. L A - 7 3 5 5 - M S A V A l L A B I L I T Y - L O S ALAMOS SCIENTIFIC LAB.,

P.O. BOX 1663, LOS ALAMOS, N.M. 87545 LOASL

\> • <a % 8191 Date 1978

010000 111110 122310 870090 870092 Evaluation of Fast Integral Data Related to 233 -U and

Thorium.

W Beck, C.L.; Lineberry, M.J.; Sctjaefer, R.W.; Carpenter, S.G.; Wade, D.C.

CONF-780401 - 1 4 A V A I L A B I L I T Y - D E P . , NTIS ARGONN

8192 '.1 Date 1978 111110 122310 312000 521130 713000 870090 870092 Nuclear Data Sensitivity Coefficients for

( 2 3 3 - U — 2 3 2 - T h ) Fueled LMFBR. Turski, R.B.; McKnight, R.D. CONF-780401-15 A V A I L A B I L I T Y - D E P , NTIS ARGONN

8193 Date 1978 ls^UO 122310 312000 32A000 521130 713000 794000 Uncertainties in the Breeding Ratio of a Large LMFBR. Marable, J.H.; Weisbin, C.R. ° CONF-780401 - 1 6 A V A I L A B I L I T Y - D E P , NTIS O A R N L

0 8254 Date November 1978

122310 430000 794000 Development and Testing of Neutron Dosimetry Techniques

for Accelerator-Based Irradiation Facilities. Greenwood, L.R.; Heinrich, R.R.; Kennerley, R.J.; Medrzy-

chowski, R. tgUCL. TECHNOLOGY, 41(1), 109-128 ARGONN

8275 Date August 1978~ 010000 122310 112120 810000 Impact of Integral Measurements on the Capture

Cross-Section Evaluations of Individual Fission Prod-uct Isotopes. o

91

^Gruppelaar, H.; Dekker, J.W.M. IAEA-213, PP.219-277 ,, A V A I L A B I L I T Y - I A E A , V I E N N A ( M F ONLY) NETHER

8276 Date August 1978 010000 111210 122310 810000 Status of Fast Neutron Reaction Cross Section of Fission

Products. 'Iijima, S. IAEA-213, PP.279-350 0 A V A I L A B I L I T Y - I A E A , V I E N N A (MF O N L Y ) JAPAN

8421 Date August 1978 111110 122310 521130 810000 Integral Determination of RP Neutron Cross Sections. Bustraan, M. IAEA-213, VOL.11, PP.627-675 A V A I L A B I L I T Y - I A E A ( M F ONLY) NETHER

8503 Date 1978 122310 717100 870092 Analysis of the Sensitivity of Hybrid Reactor Parameters to

Nuclear Data. Kotov, V.V.; Maynard, Ch.W.; Markovskii, D.V.; Shatalov,

1 G.E. L A - T R - 7 8 - 6 5 ; IAE-2817 ( I N RUSSIAN) A V A I L A B I L I T Y - L O S ALAMOS SCIENTIFIC LAB.

« RUSSIA


and of 238 -U Fast Fissions on Fission Product Decay Power.

JTrapp,T.J.,Jr. NUREG/CR-0404; OSU-NE-7806; THESIS A V A I L A B I L I T Y - N T I S U - O R o

<0 8517 Date February 1979

020000 U1210 122310 312000 32A000 551110 552110 795276 717000 721100 793000 794000 861000 853100 O I

Cross Section Sensitivity Analysis of a Proposed Neutron Streaming Experiment with a Two-Dimensional Model.

Seki, Y.; Santoro, R.T.; Oblow, E.M.; Barnes, J.M.; Lucius, J.L.

O R N L / T M - 6 5 8 8 A V A I L A B I L I T Y - N T I S S4.50 O A R N L

8518 Date January 1979 111210 122310 32A000 521130 551110 717000 793000

795276 795254 794000 Comparison of One- and Two-Dimensional

Cross-Section Sensitivity Calculations for a Fusion Reactor Shielding Experiment.

Seki, Y.; Santoro, R.T.; Oblow, E.M.; Lucius, J.L. ORNL /TM-6667 A V A I L A B I L I T Y - N T I S $4.00 H OARNL "

8553 Date February 1979 111110 122310 422110 870098 Measurement and Calculation of Average Activation Cross

Sections in the Spontaneous Fission Neutron Field of 252-Cf. (Tech. Note)

Mannhart, W.; Alberts, W.G. NUCL. SCI. ENG., 69(2), 333-338 GERMAN

8576 £ Date November 1978 020000 010000 122100 122310 713000 810000 Nuclear Data Needs for Fast Breeder Reactor Shielding. Oblow, E.M.; Perey, F.G. CONF-781117-5 AVAIL£B IL ITY-DEP. , NTIS OARNL

8580 ? Date 1977 111110 122310 327000 511110 861000 870011 Neutron Slowing Down and Transport in Monoisotopic

Media with Constant Cross Sections or with a Square-Well Minimum. «

Peng, W.H. COO-2509-6 AVAILABIL ITY-DEP. , NTIS U - N Y

8650 Date February 1979 010000 122310 312000 A Review of the Theory and Application of Sensitivity and

Uncertainty Analysis. Proceedings of a Semi-nar-Workshop, Oak Ridge, Tennessee, August 22-24, 1978. 0


ORNL/RSIC-42 A V A I L A B I L I T Y - N T I S $13.00 OARNL ^

8651; Date February 1979 Til 110 122310 312000 325000 521130 810000 The Use of Cross-Section Sensitivities in the Analysis of

Fast Reactor Integral Parameters. 6> v.

Collins, P.J.; Lineberry, M.J. ORNL /RS IC-42 , PP.13-23 A V A I L A B I L I T Y - N T I S ARGONN

865 2 Date February 1979 111110 122310 312000 713000 794000 521130 32A000 Advances in Fast Reactor Sensitivity and Uncertainty Anal-

ysis.// Marable, J.H.; Weisbin, C.R. ORNL/RSIC-42 , PP.25-48 A V A I L A B I L I T Y - N T I S OARNL

o 865 3 '. Date February 1979

111110 122310 32A000 521130 713000 810000 312000 Controlled Cross-Section Adjustment.by Integral Data. Salmi, U.; Wagschal, J.J.; Ya'ari, A.; Yeivin, Y. ORNL/RSIC-42 , PP.49-59 A V A I L A B I L I T Y - N T I S ISRAEL

8658 Date February 1979 111110 122310 210000 42U40 430000 521130 810000

870098 " " ,J

Testing of ENDF/B Cross-Section Data in the Californi-um-252 Neutron Benchmark Field.

Mannhart, W. " ,, ORNL/RSIC-42 , PP.119-133 A V A I L A B I L I T Y - N T I S G E R M A N

8659. Date February 1979 111110 122310 210000 421140 719A00 861000 7,95112

430000 Use of HEDL Codes in the Sensitivity and Uncertainty

Analysis of the Pressure Vessel Embrittlement Damage Function Problem.

Guthrie, G.L.; Schmittroth, F.; Simons, R.L.; Lippincott, E.P.; Oster, C.

ORNL/RSIC-42 , PP.135-143 A V A I L A B I L I T Y - N T I S HANFOR

865 5 Date February 1979 111110 122310 719A00 810000 Sensitivity of Water Reactor Fuel Cycle Parameters and

Costs to Nuclear Data. Becker, M.; Harris, D.R.; Quan, B.; Ryskamp, J.M. ORNL/RSIC-42 , PP.75-87 A V A I L A B I L I T Y - N T I S U - N Y

//

865 6 Date February 1979 111110 122310 123000 719A00 Nonlinear Model Fitting of Thermal Neutron Data and its

Application in Resonance Parameter Uncertainty Anal-ysis.

Thompson, J.K. ORNL/RSIC-42 , PP.89-10^ A V A I L A B I L I T Y - N T I S B A N L

8660 Date February 1979 111110 122310 210000 430000 521130 861000 810000 Varied Applications of a New Maximum-Likelihood Code

with Complete Covariance Capability. Schmittroth, F. <3 ORNL/RSIC-42 , PP. 145-159 A V A I L A B I L I T Y - N T I S HANFOR "

8661 Date February 1979 Q

U1110 122310 32A000 312000 210000 521130 810000 795254 794000

Sensitivity and^. Uncertainty Analysis Applied to the NBS- ISNF.

Broadhead, B.L.; Marable, J.H. ORNL/RSIC-42 , PP.161 -178 ., A V A I L A B I L I T Y - tOTlS

* U - T N "


3 istic Reactor Operating Histories. Trapp, T.J.; Spinrad, B.I. ORNL/RSIC - 42, PP. 105 -118 A V A I L A B I L I T Y - N T I S P A N L

8663 Date February 1979 111210 122310 32A000 312000 521130 551110 717000

795204 795254 795276 810000 The Application of Uncertainty Analysis in Conceptual

Fusion Reactor Design. Wu, T.; Maynard, C.W. ORNL/RSIC-42 , PP.191-217; UWFDM-290 A V A I L A B I L I T Y - N T I S U - W I O

O o 93

8664 Date February 1979 111110 122310 32AOOO 312000 717000 810000 Uncertainty Analysis for Secondary Energy Distributions. Gerstl, S.A.W. ORNL/RSIC-42 , 219-229 A V A I L A B I L I T Y - N T I S

' LOASL

8672 Date February 1979 111110 122310 795254 795204 421140 861000 The Linearity Assumption in Adjustment Procedures. Yeivin, Y. O R N L / k s i C - 4 2 , PP .343-350 AVAILABILITY-NTIS ISRAEL v

8665 Date February 1979 111110 122310 32AOOO 312000 521130 795248 High Order Effects in Cross-Section Sensitivity Analysis. Greenspan, E.; Karri;,* Y.; Gilai, D. ORNL/RSIC-42/PP.231-249 , A V A I L A B I L I T Y ^ N T I S <i ISRAEL "

8673 Date,February 1979 111110 122310 312000 0 /

/First and Higher Order Perturbation Techniques and Their Application in System Analysis and Data Adjustments!'

Gandini, A. 'ORN'L/RSIC-42, PP.351-361 A V A I L A B I L I T Y - NTIS ITALY

8667 Date February 1979 111110 122310

•V A New Approach to the Adjustment of Group

Cross-Sections Fitting Integral Experiments. Chao, Y. ORNL/RSIC-42 , PP.281-297 A V A I L A B I L I T Y - N T I S , U - P A

8674 . Date February 1979 111110 122310 32AOOO 312000 521130 713000 719AOO

795204 795254 861000 810000 * " The Use of Error Files in Uncertainty Analysis and Data

Adjustment. f j " . Chestnutt, M.M.; MCracken, A.K. ORNL/RSIC-42 , PP.363-373 * A V A I L A B I L I T Y - N T I S o ENGLAN

,8668 Date February 1979 111110 122310 123000 - * Sensitivity Theory for Depletion Analysis. Williams, M.L.; White, J.R.; Marable, J.H.; Oblow, E.M. ORNL/RSIC-42 , PP.299-310 A V A I L A B I L I T Y - N T I S O A R N L <a

I

8675. . . i V . Date February 1979 111110 122310 42U40 430000 795112 Influence of Cross-Section Structure on Unfolded Neutron

Spectra. <•• Ertek, C.; Vlasov, M.F.; Cross, B.; Smith, P.M. ORNL/RSIC-42 , PP.375-383

s ^ A V A I L A B I L I T Y - N T I S AUSTRI II

8669 Date February 1979 010000 020000 122310 810000 ° Expectations for E N D F / B - V Covariance Files: Coverage,

Strength and Limitations. Perey, F.G. ORNL/RSIC-42 , PP.3.11-318 „ A V A I L A B I L I T Y - N T I S O A R N L

8671 Date February 1979 111110 122310 719A00 810000 Sensitivity of LWR Fuel Cycle Costs to Uncertainties in

Detailed Thermal Cross Sections. Ryskamp, Becker, M.; Harris, D.R. ORNL/RSIC-42 , PP.329-342 A V A I L A B I L I T Y - f J T I S ' U^NV »

\Y

0 0

\ 94

. 8715 •r". Date February 1979 111110 122310 312000 719A00 Sensitivity of Nuclear Fuel Cycle Cost to Uncertainties in

Nuclear Data. . Becker;- M.; Harris^ D.R. ()

^ R I - N P - 9 8 5 " , o -AVAILABIL ITY-RENSSELAER POLYTECHNIC

INSTITUTE, DEPT. OF NUCLEAR'ENGINEER-ING, TROY, N ^ W YORK 12181

U - N Y e t>,

8818 Date February 1979 111210 122310 312000 717100 _. . A Separation Method for the Transport Equation and Sensi-

'tivity Theory in Fusion-Fission Hybrid Analysis. ° Youssef, M.Z.; Conn, R.W. UWFDM-289

A V A I L A B I L I T Y - N U C L E A R ENGINEERING DEPARTMENT, UNIVERSITY OF WISCONSIN, MADISON 53706

U - W I

• 8840 Date September 1978 010000 122100 122310 870006 870092 Covariance Matrices of Experimental Data. Perey, F.G. CONF-780921, PP.104-115 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL,

75775 PARIS CEDEX 16, FRANCE O A R N L

8841 Date September 1978 010000 122100 122310 810000 Correlated Uncertainties in Integral Data. McCracken, A.K. CONF-780921, PP.116-135 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL,


8843 Date September 1978 010000 122310 713000 887000 Determination of Transactinide Nuclear Data Required

Accuracy for Burn-up Calculation in Fast Reactors. Usachev, L.N.; Bobkov, Yu.G.; Kolesov, V.E.; Krivtsov, A.S. CONF-780921, PP.181-186 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL,

75775 PARIS CEDEX 16, FRANCE RUSSIA

8865 '-I Date September 1978 122310 713000 810000 Consequences des Incertitudes sur les Donnees de Base dans

les Calculs de Protection. Estiot, J.C.; Rado, V.; Salvatores, M.; Trapp, J.P. CONF-780921, PP.993-998 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL,



870092 Reproduction of the Weale Experiment Results with Modi-

fied E N D F / B - I V U-238 Data. Segev,' M.; Krumbein, A. CONF-780921, PP.1028-1032 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL,


8872 Date September 1978 122310 713000 Adjustment of Evaluated Neutron Capture Cross-Sections

of Neodymium Isotopes to Integral STEK and CFRMF Data.

Gruppelaar, K..; Dekker, J.W.M.; Janssen, A.J.; Rieffe, H.Ch.

CONF-780921, PP.1167-1171 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL ,

75775 PARIS CEDEX 16, FRANCE NETHER

8859 Date September 1978 122310 111210 329000 421130 421200 511120 512220

717000 717000 870090 870092 870029 870041 Neutron Spectra from Materials Used in Fusion and

Fusion-Fission Hybrid Reactors. Hansen, L.F.; '^ong, C.; Komoto, T.; Pohl, B.A. CONF-780921, PP.766-771 * A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL,

75775 PARIS CEDEX 16, FRANCE L A L L

J) 8861 Date September 1978

010000 122310 521230 717100 810000 Neutron Data for the Hybrid Reactor Calculation. Markovskii, D.V.; Shatalov, G.E. CONF-780921, PP.783-791 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL,


8873 Date September 1978 122110 122310 861000 The Linearity Assumption in Adjustment Procedures: Is It

a Real Problem? Yeivin, Y. CONF-780921, PP.1172-1177 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL ,


8895 Date December 1978 010000 111210 122310 312000 717000 Cross-Section Sensitivity and Uncertainty Analysis for

Fusion Reactors (A Review). Dudziak, D.J. L A - U R - 7 9 - 1 6 8 A V A I L A B I L I T Y - L O S ALAMOS SCIENTIFIC LAB.,

UNIVERSITY OF CALIFORNIA, LOS ALAMOS, NEW MEXICO 87544

LOASL

95

8950 Date May 1978 111210 122310 32A000 521130 522130 620000 717000 A Minimum-Thickness Blanket/Shield with Optimum

Trit ium Breeding and Shielding Effectiveness. Gerstl, S.A.W. , CONF-780508,VOL.1, PP.269-278 A V A I L A B I L I T Y - D E P . , NTIS LOASL


Reactors (AWBA Development Program). Hardy, J.,Jr.; Ullo, J.J.; Steen, N .M. W A P D - T M - 1 4 4 9 A V A I L A B I L I T Y - BETTIS A T O M I C POWER LABO-

RATORY, WEST M I F F L I N , PA. BETTIS

8975 Date June 1979 111110 122110 122310 810000 Specifications for Adjusted Cross Section and Covariance


Weisbin, C.R.; Marable, J.H.; Collings, P.J.; Cowan, C.L.; Peelle, R.W.; Salvatores, M.

ORNL-5517 A V A I L A B I L I T Y - N T I S $5.25 O A R N L

8991 Date February I, 1979 122310 795254 Sensitivity Analyses for the Secondary Intermedi-

ate-Energy Standard Neutron Field at the Nisus Facility.

Azimi-Garakani, D.; Shahbazi, M. N U C L . INSTRUM. METHODS, 159(1), 135-138 I R A N


Fusion Reactors. Verschuur, K.A. E C N - 7 9 - 0 1 2 A V A I L A B I L I T Y - S T I C H T 1 N G ENERGIEONDER-

ZOEK C E N T R U M N E D E R L A N D (ECN), POSTBUS 1, 1755 ZG PETTEN ( N H )

NETHER

9098 Date 1978 122110 122310 32A000 312000 Lecture Notes on Cross-Section Adjustment Procedures.

(Nuclear Science and Technology) Yeivin, Y.; Matthes, W. EUR-6041 E N A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-

TIONS OF T H E EUROPEAN COMMUNIT IES , BOITE POSTALE 1003 - LUXEMBOURG

ISRAEL

9249 Date October 1979 122310 A New Approach to the Adjustment of Group Cross Sec-

tions Fitting Integral Measurements. Chao, Y. NUCL. SCI. ENG., 72(1), 1 - 8 U - P A

o

9252 Date October 1979 111210 122310 1 J. 2400 112500 329000 421130 421200 Neutron and Gamma-Ray Spectra from 232-Th,

235-U, 238-U, and 239-Pu after Bombardment with 14-MeV Neutrons.

Hansen, L.F.; Wong, C.; Komoto, T.T.; Pohl, B.A.; Gold-berg, E.; Howerton, R.J.; Webster, W.M.

NUCL. SCI. ENG., 72(1), 35-51 L A L L

9265 Date May 1979 122100 122310 870094 242-Pu: Preliminary Evaluation with Consideration of

240 - P u and Some Sensitivity Results. Jary, J.; Lagrange, Ch.; Philis, C. BNL-50991,PP.83-131; CONF-781174.PP.83-131 A V A I L A B I L I T Y - N T I S FRANCE

9270 Date May 1979 122310 870094 870095 Reactor Application of Actinide Cross Section Data. Beaman, S.L.; Cowan, C.L. BNL-50S91,PP.287-295; CONF-781174.PP.287-295 A V A I L A B I L I T Y - N T I S GEE

9362. . - Date September 1979 122110 122310 Ferret Data Analysis Code. Schmittroth, F. H E D L - T M E - 7 9 - 4 0 A V A I L A B I L I T Y - H A N F O R D ENGINEERING

DEVELOPMENT LAB., R I C H L A N D , WASHING-T O N

96

HANFOR

9400 Date November 1979 122310 422110 795112 Integral Tests of Neutron Activation Cross Sections in a

9-Be(d,n) Fields at E/sub d /=40 MeV. Greenwood, L.R.; Heinrich, R.R.; Saltmarsh, M.J.; Hari-

har, P. NUCL. SCI. ENG., 72(2), 175-190 ARGONN

9448 Date August 1979 111110 122310 32A000 521130 793000 794000 719A00

861000 870094 Integral Data Evaluation of Stainless Steel, 239-Pu,

240-Pu, and H /sub 2/ O for Homogeneous Plutonium Systems.

Jenqiiin, U.P.; Thompson, J.K.; Trapp, T.J.; Kottwitz, D.A. NUREG/CR-0965; PNL-3071 A V A I L A B I L I T Y - D E P . , NTIS, PC A 0 5 / M F A01 PANL

9654 Date December 1979 111210 122310 312000 717000 810000 Estimated Target Accuracies for Neutronic Responses in

Fusion Reactors. Verschuur, K.A. ECN-64 A V A I L A B I L I T Y - N E T H E R L A N D S ENERGY

RESEARCH FOUNDATION ECN, P.O. BOX 1, 1755 ZG PETTEN (NH) , T H E NETHERLANDS

NETHER

9934 Date June 1980 122110 122310 Processing E N D F / B - V Uncertainty Data into Multigroup

Covariance Matrices. Smith, J.D.,III O R N L / T M - 7 2 2 1 A V A I L AB IL ITY - NTIS O A R N L

9989 Date August 1980 010000 122310 329000 521130 795372 795254 Study of Perturbations Using Correlated Monte Carlo

Method. Dejonghe, G.; Gonnord, J.; Nimal, J.C. ORNL/RSIC-44 , PP.63-93 A V A I L A B I L I T Y - N T I S , PC A16 /MF A01 FRANCE

10146 Date August 1980 111210 122310 32A100 521130 717000 810000 SENSIT: A Cross-Section and Design Sensitivity and

Uncertainty Analysis Code. Gerstl, S.A.W. L A - 8 4 9 8 - M S A V A I L A B I L IT Y - NTIS LOASL

Nuclear Structure and Parameters


9733 Date April 1980 122310 A Sensitivity Study on the Influence of the Choice of the

Mean Resonance Data Set in the Unresolved Resonance Region on the Doppler Effect Calculations. (Tech. Note)

Ganesan, S. NUCL. SCI. ENG., 74(1), 49-51 I N D I A


9853 Date May 1980 122310 123000 A Consistent Nuclear Model for Compound and Precom-

pound Reactions with Conservation of Angular Momentum.

Fu, C.Y. O R N L / T M - 7 0 4 2 A V A I L A B I L I T Y - N T I S , PC A 0 3 / M F A01 O A R N L

6861 Date May 1978 111220 121100 123000 421150 810000 SIOB: A FORTRAN Code for Least-Squares Shape Fit-

ting Several Neutron Transmission Measurements Using the Breit-Wigner Multilevel Formula,

de Saussure, G.; Olsen, D.K.; Perez, R.B. ORNL /TM-6286 ; ENDF-261 A V A I L A B I L I T Y - N T I S S6.00 O A R N L

97


Elements. Segev, M . N U C L . SCL ENG., 67(2), 221-234 A R G O N N

8668 Date February 1979 111110 122310 123000 Sensitivity Theory for Depletion Analysis. Williams, M.L. ; White, J.R.; Marable, J.H.; Oblow, E.M. O R N L / R S I C - 42, PP.299-310 A V A I L A B I L I T Y - N T I S O A R N L

8211 Date August 1978 123000 810000 The Nuclear Structure References (NSR) File. Ewbank, W.B. O R N L - 5 3 9 7 A V A I L A B I L I T Y - N T I S O A R N L

W

8274 Date August 1978 010000 123000 112120 810C00 . s v Status of Neutron Reaction Cruss Sections of Fission Prod-

ucts in the Energy Range ofvResolved and Unresolved Resonances. , '•'"*()

Fort, E. , o I A E A - 2 1 3 , PP.139-218 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) F R A N C E

8418 Date August 1978 010000 112120 123000 870092 870094 Prediction of Unmeasured Fission Yields by Nuclear Theory

or Systematics. Denschlag, J.O. I A E A - 2 1 3 , VOL.11, PP.421 -485 A V A I L A B I L I T Y - I A E A ( M F O N L Y ) G E R M A N

8516 Date February 1979 112120 122110 123000 532000 795217 Updated Decay and Photon Libraries for the O R I G E N

Code. Croff, A.G.; Haese, R.L.; Gove, N.B. O R N L / T M - 6 0 5 5 A V A I L A B I L I T Y - N T I S $6.50 O A R N L

8656 Date February 1979 111110 122310 123000 719A00 Nonlinear Model Fitt ing of Thermal Neutron Data and its


Thompson, J.K. O R N L / R S I C - 4 2 , PP.89-104 A V A I L A B I L I T Y - N T I S B A N L

8849 Date September 1978 010000 123000 Recent Developments in the Theory of the Nuclear Level

Density. Jensen, A.S. CONF-780921, PP.378-395 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, F R A N C E D E N M A R

8955 Date May 1978 111210 123000 210000 531000 532000 793000 794000

810000 Computations of Nuclear Response Functions with

M A C K - I V . Abdou, M.A. ; Gohar, Y . ' > 1 ' , , CONF-780508.VOL. 1, PP.402-410 A \ \ A V A I L A B I L I T Y - D E P . , N T I S A R G O N N

9014 Date Apr i l 1979 010000 123000 High Energy Physics. The Ult imate Structure of Matter and

Energy. ' DOE DOE/ER-0027 A V A I L A B I L I T Y - D I V I S I O N OF H I G H ENERGY

PHYSICS, OFFICE OF ENERGY RESEARCH, DOE, W A S H I N G T O N , D.C.

DOE


1: Activation Reactions. (1979 Edition) Zi jp, W.L.; Baard, J.H. E C N - 7 0 A V A I L A B I L I T Y - N E T H E R L A N D S ENERGY

RESEARCH F O U N D A T I O N ECN, P.O. BOX 1, 1755 ZG PETTEN ( N H ) , T H E N E T H E R L A N D S

NETHER

9575 Date August 1979 122100 123000 421150 810000 Nuclear Data Guide for Reactor Neutron Metrology. Part

2: Fission Reactions. (1979 Edition)

98

Zijp, W.L.; Baard, J.H. E C N - 7 1 A V A I L A B I L I T Y - N E T H E R L A N D S ' ' ENERGY

RESEARCH F O U N D A T I O N ECN, P.O. BOX 1, 1755 ZG PETTEN (NH) , T H E NETHERLANDS

NETHER

9587 Date July 1979 123000 [ HAUSER*5, A Computer Code to Calculate Nuclear Cross

Sections. Mann, F.M. H E D L - T M E - 7 8 - 8 3 A V A I L A B I L I T Y - N T I S HANFOR

9788 . Date December 1979 010000 111210 122100 123000 717000 810000 Theoretical Approach to Nuclear Data Required for Fusion

Reactor Calculations. (Review Paper No.B2) Seeliger, D. IAEA-TECDOC-223 , PP. 139-152 „ A V A I L A B I L I T Y - M F O N L Y - IN IS MICROFICHE

CLEARINGHOUSE, IAEA, WAGRAMER-STRASSE 5, P.O. BOX 100, A-1400 V I E N N A , AUSTRIA

GERMAN (


by Electron-Transport Calculations. ' ' Peek, J.M. SAND-79 -0772 A V A I L A B I L I T Y - D E P . , NTIS, PC A 0 6 / M F A01 SANDIA

9853 Date May 1980 122310 123000 A Consistent Nuclear Model for Compound and Precom-

pound Reactions with Conservation of Angular Momentum.

Fu, C.Y. O R N L / T M - 7 0 4 2 A V A I L A B I L I T Y - N T I S , PC A03 /MF A01 O A R N L

9940 Date October 1979 121100 123000 Program RECENT (Version 79-1) : Reconstruction of

Energy-Dependent Neutron Cross Sections from Reso-nance Parameters in the ENDF/B Format.

Cullen, D.E.

UCRL-50,400, VOL.17, PT.C A V A I L A B I L I T Y - N T I S $6.00 L A L L

10054 Date 1977 121100 123000 Calculation of Nuclear Reaction Cross Section with the Sta-

tistical Model. Matthes, W. EUR-5722 E A V A I L A B I L I T Y - C O M M I S S I O N OF T H E EURO-

PEAN COMMUNIT IES, D IRECTORATE-GENERAL , SCIENTIFIC A N D T E C H N I C A L I N F O R M A T I O N A N D INFORMA-T I O N M A N A G E M E N T , BATIMENT, JEAN MONNET, LUXEMBOURG; CATALOGUE N O . C K - S E - 7 7 - 0 2 6 - E N - C

ITALY (>

Radiation Damage


6247 Date December 1977 111210 32AOOO 210000 521130 522130 531000 532000

717000 793000 795254 810000 861000 870003 Nuclear Performance Calculations for the ELMO Bumpy

Torus Reactor (EBTR) Reference Design. Santoro, R.T.; Barnes, J.M. O R N L / T M - 6 0 8 5 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

6392 Date Dec. 1977 713000 210000 Irradiation Effects and Design of LMFBR Permanent Reac-

tor Structures. Blackburn, L.D.; Knecht, R.L. CONF-770401, PP.230-237; ATOMKERNENERGIE,

30(4), 278-281 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 WEE

6393 Date Dec. 1977 719A00 210000 Determination of Radiation Damage to Structural Compo-

nents Outside the Core of PWRs. Koban, J.; Leitz, G.; Hehn, G.; Issler, L. CONF-770401, PP.238-245 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


99

G E R M A N


placement per Atom Cross-Sections to Different Secondary Neutron Energy and Angular Distributions and " In-Group" Weighting Schemes.

Gabriel, T.A.; Bishop, B.L, O R N L / T M - 6 1 0 8 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

6607. . ; Date February 1978 010000 111210 210000 717000 810000 Special Purpose Materials for the Fusion Reactor Environ-,

ment. A Technical Assessment. Scott, J.L. (Ch.) DOE/ET-0015 A V A I L A B I L I T Y - N T I S $6.50 DOE

6677 Date June 1977 111110 121100 210000 421140 861000 Importance and Status of (n, alpha)-Cross Sections for a

Reliable Prediction of Radiation Damage in Stainless Steel.

Goel, B. EURFNR-1465 A V A I L A B I L I T Y - N T I S " GERMAN

6709 Date September 1976 111110 111210 121100 210000 713000717000 861000 A Systematic Approach to the Radiation Damage Problem

in Fission and Fusion Reactor Structural Alloys. Bullough, R.; Eyre, B.L.; Kulcinski, G.L. U W F D M - 1 8 4 A V A I L A B I L I T Y - N U C L E A R ENGINEERING

DEPARTMENT, UNIVERSITY OF WISCONSIN, MADISON, WISCONSIN

U - W I V) ' h

6609 '. Date December 1977 111110 210000 311000 32A000 551110 795276 719AOO

861000 810000 Calculations of Neutron Flux Levels in the Pressure Vessel

of an LWR. Final Report (Research Project 827-2). Livesay, R.B.; Wells, M.B. EPRI -NP-617 A V A I L A B I L I T Y - R A D I A T I O N RESEARCH ASSOCI-

ATES, INC. RARA


Source, INS. Battat, M.; Dierckx, R.; Emigh, C.R. L A - U R - 7 7 - 1 0 5 4 ; CONF-770523-2 A V A I L A B I L I T Y - D E P . , NTIS LOASL

6744 . . . Date May 1978 111110 111210 111130 210000 121100 870019 Fusion/Fission Damage Ratios for Neutron-Induced Dis-

placement Damage in Silicon. 1

Van Antwerp, W.R.; Hollandsworth, C.E.; Youngblood, J.E. A R B R L - M R - 0 2 8 3 6 . , A V A I L A B I L I T Y - N T I S A R M Y

6767 Date October 1977 111210 210000 717000 870006 870042 Response of First Walls in Inertial Confinement Reactors to

Thermonuclear Radiation. Hunter, T.O.; Abdel-Khalik, S.I.; Kulcinski, G.L. U W F D M - 2 2 1 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,

UNIV. OF WISCONSIN, MADISON, WISCONSIN v 53706

U - W I

6635 Date January 1978 111210 111220 210000 717000 870023 870029 870041 Exploratory Experiments Comparing. Damage Effects of


Mitchell, J.B. UCRL-52,388 A V A I L A B I L I T Y - L A W R E N C E L IVERMORE LAB.,

CAL IFORNIA UNIV. L A L L

6768 Date October 1977 010000 111210 210000 717000 810000 Progress in Materials Research for Fusion Reactors. Kulcinski, G.L. UWFDM-228 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,


U - W I

t. !•

6769 Date March 1978 010000 111210 111220 210000 717000 810000 „ Intense Sources of Fast Neutrons. Barschal), H.H. U W F D M - 2 3 1 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,


U - W I

6849 Date 19?8 010000 111110 210000 421140 Cross-Section Requirements for Reactor Neutron Flux

Measurements from the User's Point of View. Mas, M.; Lloret, R. IAEA-28 , VOL.11, PP.387-394 ( IN FRENCH) A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE FRANCE

6770 Date April 1978 111210 210000 717000 870029 Surface Damage and Thermal Effects from Transient Ther-

monuclear Radiation in Inertial Confinement Fusion Reactors.

Hunter, T.O.; Kulcinski, G.L. UWFDM-233 C-A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,

NUCLEAR,ENGINEERING DEPT., UNIVERSITY OF WISCONSIN, MADISON, WISCONSIN 53706

U - W I

6771 Date March 1978 111210 210000 717000 810000 First Wall and Divertor Plate Material Selection in Fusion

Reactors. Conn, R.W. UWFDM-237 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,


U - W I

6810 Date 1978 010000 210000 421130 421140 511120 719A00 861000 Power Reactor Pressure Vessel Benchmarks. Rahn, F.J. IAEA-208, VOL.I, PP. 105-140 $ A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE EPRI

6848 Date 1978 111110 210000 5 l fF20 861000 870092 One Material Experiments in the Frame of Power Reactor

Pressure Vessel Benchmarks. De Leeuw-Gierts, G.; De Leeuw, S. IAEA-208, VOL.11, PP.375-383 A V A I L A B I L I T Y - I N I S MICROFICHE_CLEARING-

HOUSE f ~ \ BELGIU , U

6944 Date May 1978 111110 112120 210000 421200 719B00 810000 Distribution of Fission Products in Peach Bottom HTGR

Fuel Element F03-01. Dyer, F.F.; Wichner, R.P.; Martin, W.J.; Fairchild, L.L. O R N L / T M - 5 9 9 6 A V A I L A B I L I T Y - N T I S $10.75 O A R N L

7007 Date September 1976 111110 210000 870042 Neutron-Irradiation Effects on Molybdenum and Molyb-

denum Alloys. Bentley, J.; Wiffen, F.W. CONF-760935-P1, PP. 209-218 A V A I L A B I L I T Y - N T I S O A R N L

7008 Date September 1976 111210 210000 870041 870050 Determination of the Damage-Energy Cross Section of

14 - MeV Neutrons from Critical - Property Changes in Irradiated Nb/SUB3/Sn.

Snead, C.L.,Jr.; Parkin, D.M.; Guinan, M.W.; Van Konynenburg, R.A. ^

CONF-760935-PI , PP. 229-237 A V A I L A B I L I T Y - NTIS BROOKH

7028 Date September 1976 010000 111210 210000 32A000 329000 531000 532000


Reactors. Dudziak, (D.J. CONF-760935-P3, PP: 819-832; L A - U R - 7 6 - 2 0 8 6 A V A I L A B I L I T Y - N T I S LOASL

,, 7034 Date September 1976 111110 210000 870006 717000 Neutron Irradiation Effects on Graphite Cloth. Gray, W.J.

101

CONF-760935-P3, PP. 1049-1059 A V A I L A B I L I T Y - N T I S BANW


VlPower Program. • ,, Williams, J.M.; Beal, J.W.; Coffman, F.E.; Henning, C.D,';

Zwilsky, K.M. CONF-760935-P3, PP. 1075-1094 A V A I L A B I L I T Y - N T I S DOE

8087 Date Mid-August 1978 210000 U Void Swelling in Metals and Alloys Under Irradiation: An

Assessment of the Theory. [f Mansur, L.K. " NUCL. TECHNOLOGY, 40(1), 5 -34 OARNL

/T 8089. Dale Mid-Augu ' - >1978

010000 210000 How Does One Predict and Measure Radiation Damage? Nichols, F.A. NUCL. TECHNOLOGY, 40(1), 98-105 ARGONN U

7042 Date September 1976 010000 111210 112760 223000 210000 521130 522130


Reactors. Vogelsang, W.F. CONF-760935-P4, PP. 1303-1318; UWFDM-178 A V A I L A B I L I T Y - N T I S U - W I

7044 Date September 1976 111210 210000 717000 810000 ^ Radiation Damage Analysis as Applied to' Fusion Reactor

First Walls. Odette, G.R.; Doran, D.G. CONF-760935-P4, PP. 1485-1500 A V A I L A B I L I T Y - N T I S U - C A

7125 Date July 1976 111110 210000 853100 Requirements on Concrete and Structures of Reinforced

Concrete Reactor Shield. Korenevskiy, V.V.; Pergamenshchik, B.K.; Perevalov, V.S. E R D A - T R - 1 2 5 , PP. 251 -2 iS\ A V A I L A B I L I T Y - N T I S RUSSIA

/ 8043 Date June 1978

111210 210000 717000 810000 The Newest Frontier in Radiation Damage Research -

Laser Fusion Reactors. n Kulcinski, G.L. f f U W F D M - 2 5 0 -J/ A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,


U - W I

8129 Date March 1977 111110 111210 111220 121100 210000 717000 810000 Description of the Response of Reactor First Walls to Pulsed

Thermonuclear Radiation (Part I). Hunter, T.O.; Kulcinski, G.L. UWFDM-196 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,

NUCLEAR ENGINEERING DEPT., UNIVERSITY, OF WISCONSIN, MADISON, WISCONSIN 53706

U - W I

8133 Date July 1978 111210 210000 717000 862000 > r Effects of Bombarding Ions on the Void Swelling Profile in

Nickel. Whitley, J.B.; Kulcinski, G.L.; Smith, H.V.,Jr.; Wilkes, P, UWFDM-252 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,


U - W I

8186 Date 1976 111110 210000 421140 810000 . Damage Model and Neutron Spectrometry Applied in Reac-

tor Steel Irradiation Programmes. Weise, L. AED-CONF-76 -556 -008 ( I N GERMAN) A V A I L A B I L I T Y - I N 1 S GERMAN

8188 Date June 1978 111210 210000 7(17000 841000 842000 844000 The Effects of Radiation on Electrical Insulators in Fusion

Reactors. Phillips, D.C. AERE-R-8923 A V A I L A B I L I T Y - N T I S

102

E N G L A N

n 8248,, Date November 1978 210000 32A0J0 717000 795254(03) Sputtering Calcuiat io^.with Discrete-Ordinates Method. Hoffman, T.J.; D{ ' { T\Jr. ; Robinson, M.T.; Holmes,

D.K. J N U C L . SCI. ENG., 204-211 OA'RNL "'„ •

8258 Date 1976 010000 210000 Radiation Damage in Metals. Peterson, N.L.; Harkness, S.D. BOOK A V A I L A B I L I T Y - A M E R I C A N SOCIETY FOR MET-

ALS, M E T A L S PARK, OHIO A R G O N N

8411 Date Apr i l 1978 111210 210000 717000 870023 Technical Assessment of Vanadium- Base Alloys for Fusion

Reactor Applications. Vol.1. Assessment of Data Base, Needs and Recommendations. Final Report.

Gold, R.E.; Harrod, D.L.; Ammon, R.L.; Buckman, R.W,Jr . ; Svedberg, R.C.

COO - 4540 - 1 (VOL. 1) A V A I L A B I L I T Y - N T I S $5.25 WEE


Electron Irradiations. Goldstonc, J.A. L A - 7 4 2 4 - T ; THESIS A V A I L A B I L I T Y - N T I S L O A S L

8433 Date October 1978 111210 210000 717000 841000 842000 844000 Evaluation of Performance of Select Fusion Experiments

and Projected Reactors., rMiley, G.H. N A S A CONTRACTOR REPORT 3043 A V A I L A B I L I T Y - N T I S N A A S A

8463 Date May 1978 111210 210000 717000 329000 521130 861000 870003 Conceptual Design Considerations and Neutronics of Lith-

ium Fall Laser Fusion Target Chambers.

Meier, W.R.; Thomason, W.B. UCRL-80782 A V A I L A B I L I T Y - L A W R E N C E L I V E R M O R E LABO-

RATORY Q L A L L

8465 Date June 1978 111210 210000 717000 861000 870003 810000 r

Materials Considerations for Inertially-Confined Fusion Reactors ( ICFR).

Hovingh, J. UCRL-81206 A V A I L A B I L I T Y - L A W R E N C E L IVERMORE LABO-

RATORY L A L L

8477 Date January 1979 210000 861000 0

Helium Production in Stainless Steel. (Tech. Note) Goel, B. NUCL . SCI. ENG., 69(1), 99-104 G E R M A N


etry to 44 MeV. Greenwood, L.R. A N L / F P P / T M - 1 1 5 A V A I L A B I L I T Y - N T I S $'4.50 A R G O N N

8495 Date 1977 111210 210000 717000 810000 Radiation Considerations for Superconducting Fusion Mag-

nets. Abdou, M.A. CONF-770649-6 A V A I L A B I L I T Y - N T I S A R G O N N

8585 Date 1977 010000 111110 210000 421140 430000 713000 717000



McElroy, W.N.; Bennett, R.A.; Johnson, D.L. EUR-5667E/F.PT. I , PP.1-26; CONF-750935,PT.I,

PP.1-26 A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L PUBLICA-


103

WEE

; 8586 : Date 1977 010000 111110 210000 421140 713000 719A00 810000 Dosimetry Methods for Structural Material Irradiation in

the European Countries. Farinelli, U. EUR-5667E/F.PT.I, PP.27-40; CONF-750935.PT.I,

PP.27-40 VAVAILAB IL ITY-OFF ICE FOR OFFICIAL PUBLICA-

TIONS OF THE EUROPEAN COMMUNITIES, BOITE POSTAL 1003 - LUXEMBOURG

ITALY

8587 Date 1977 111110 210000 421140 719A00 861000 Influence of Neutron Dosimetry on Radiation Damage Con-

siderations in LWR Pressure Vessels. Serpan, C.Z.,Jr. EUR-5667E/F.PT.1, PP.41-51; CONF-750935.PT.I,

PP.41-51 J A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


yNURC

8588 Date 1977 111110 210000 521130 713000 719A00 795254 861000

795276 ( i . .. Prediction of Radiation Damage in Structural Materials

Outside the Reactor Core. Hehn, G.; Stiller, P. y

EUR-5667E/F,PT.I, PP.52-62; CONF-750935,PT.I, PP.52-62

AV A I I l A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-TIONS OF THE EUROPEAN COMMUNITIES, BOITE POSTAL 1003 - LUXEMBOURG

G E R M A N

8589 Date 1977 111110 210000 421140 32AOOO 551110 810000 Neutron Energy Spectrum Determination for Irradiation ,

Damage Study of Reactor Structural Materials. Takeuchi, K.; Miura, T.; Yamaji, A. EUR-5667E/F,PT.I, PP.63-73; CONF-750935.PT.I,

PP.63-73 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


JAPAN

8591 Date 1977 111210 210000 421140 430000 717000 521130 795254

793000 795112 810000 Investigation of Neutron Flux Spectral Measurement for

Controlled Thermonuclear Reactor Radiation Damage Studies.

Odette, G.R. EUR-5667E/F.PT.I, PP.84-97; CONF-750935.PT.I,



U - C A O

8602 Date 1977 111110 210000 325000 713000 861000 The Calculation of Atomic Displacement Dose in Fast Reac-

tors. Etherington, E.W, EUR- 5667E/F,PT.I, PP.375-413;

CONF-750935,PT.I, PP.375-413 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-

TIONS OF THE EUROPEAN COMMUNITIES, , BOITE POSTAL 1003 - LUXEMBOURG

: N E T H E R

8604 Date 1977v

111110 210000 421140'422130 430000 870092 870094-' Fission Rate Measurements for Materials Neutron Dosime-

try in Reactor Environments. <, Grundl, J.; Eisenhauer, C. EUR-5667E/F,PT.I, ° PP.425-454;



NABS

8606 Date 1977 111110 210000 421140 422130 870092 870094 Specimen Fission Rate Estimation in the JMTR. Mizuho, M.; Oyamada, R.; Sezaki, K. EUR-5667E/F,PT.I, * PP.498-523;

CONF-750935,PT.I, PP.498-523 <-A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-

TIONS OF THE EUROPEAN COMMUNIT IES, BOITE POSTAL 1003 - LUXEMBOURG

JAPAN

8608 Date 1977 111 110 210000 421150 Methodes Speciales Utilisees en Dosimetric des Neutrons. Mas, P. EUR-5667E/F,PT.I, PP.536-549(IN FRENCH);

CONF-750935,PT.I, : PP.536-549(IN FRENCH)

104

AVAILABIL ITY-OFFICE FOR OFFICIAL PUBLICA-T I O N S OF THE EUROPEAN COMMUNITIES, BOITE POSTAL 1003 - LUXEMBOURG

FRANCE

8610 Date 1977 111110 210000 421140 Absolute Measurements of Neutron Induced Reaction

Rates. " Murphy, M.F.; Sweet, D.W.; Taylor, W.H. EUR-5667E/F.PT.I, PP.560-578;

CONF-750935.PT.I, PP.560-578 AVAILABIL ITY-OFFICE FOR OFFICIAL PUBLICA-

TIONS OF-THE EUROPEAN COMMUNITIES, BOITE POSTAL 1003 - LUXEMBOURG

ENGLAN

8621 Date 1977 111110 210000 422110 810000 870041 Utilization of the Reaction 93 - N b (n,n') 93m-Nb for Fast

Neutron Fluence Measurement. Hegedus, F. EUR-5667E/F,PT.I, PP.757-762;

CONF-750935,PT.I, PP.757-762 AVAILABIL ITY-OFF ICE FOR OFFICIAL PUBLICA-


J ' SWITZ^

19/7 8617 Date 111110 210000 422110 Neutron Fluence Measurements Applied to Reactor Materi-

als Irradiation. Schneider, W. EUR-5667E/F.PT.I, " PP.649-674;



GERMAN

8618 Date 1977 111110 210000 422110 423250 532000 713000 810000 Dosimetry Work in Connection with Irradiations in the High

FluxJVIaterials Testing Reactor BR2. Debruefj.;De Leeuw-Gierts, G.; De Leeuw, S.; Raedt, Ch.

de; Fabry, A,; Leenders, L.; Maene, N.; Menil, R. EUR-5667E/F, PT.I; " PP.700-737;

CONF-750935,PT.I, PP.700-737 AVAILABIL ITY-OFFICE FOR OFFICIAL PUBLICA-


FRANCE

8620 Date 1977 111110 210000 422110 810000 870041 Application de la Reaction 93 -Nb (n,n') 93m-Nb a la

Dosimetrie des Irradiations de Materiaux. Lloret, R. EUR-5667E/F,PT.I, PP.747 -756( IN FRENCH);

CONF-750935.PT.I, PP.747-756(IN FRENCH) AVAILAB IL ITY-OFF ICE FOR OFFICIAL PUBLICA-

TIONS OF THE EUROPEAN COMMUNITIES, BOITE POSTAL 1003 - LUXEMBOURG'S

"FRANCE „ "

8622 . Date 1977 111110 210000 422110 861000

<0

Vessel's Material Surveillance Program Fast Neutron (E greater greater than 1 MeV)Flux Measurement.

Galliani, M.; Benatti, P.I.N.; Puliandri, P.I.A. « EUR-5667E/F,PT.I, PP.763-777;

CONF-750935,PT.I, PP.763-777 AVAILABIL ITY-OFF ICE FOR OFFICIAL PUBLICA-

TIONS OF THE EUROPEAN COMMUNITIES, ^ BOITE POSTAL 1003 - LUXEMBOURG

ITALY V

8623 Date 1977 111110 210000 422110 810000 Neutron Flux Measurements for Radiation Damage Studies

in the 10 M W Research Reactor HIFAR. Hilditch, R.J.; Lowenthal, G.C. EUR-5667E/F,PT.I, PP.791-807;

CONF-750935,PT.I, PP.791-807 AVA ILAB IL ITY-OFF ICE FOR OFFICIAL PUBLICA-


AUSTRA

8624 Date 1977 111110 210000 220000 713000 795179 Sensitivity of Fluence-to-Dose Conversion to Changes in

Fast Pulse Reactor Spectra. Kazi, A.H.; Dunn, T.A.; Saccenti, J.C. EUR-5667E/F,PT.I, PP.808-822;



ARMY

8627 Date 1977 111110 210000 810000 Radiation-Induced Defect Production in Structural Mate-

rials at Reactor Temperatures. Beeler, J.R,Jr.; Brudnoy, D.M.; Beeler, M.F. EUR-5667E/F,PT.1I, PP.1-23; CONF-750935,PT.II,

PP. 1-23

105

A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-TIONS OF T H E EUROPEAN COMMUNIT IES, BOITE POSTAL 1003 - LUXEMBOURG \ // V a

Schmittroth, F. ORNL/RSIC-42 , PP.145-159 A V A I L A B I L I T Y - N T I S HANFOR

8628. ., Date 1977 111110 210000 422110 551120 810000 795254 795209 Dosimetrie Relative a des Irradiations d'Acier dans lc Reac-

teur Melusine. Devillers, C.; Perdreau, R. EUR-5667E/F.PT.I I , PP.69-80(IN FRENCH);

CONF-750935,PT.II, PP.69-80(IN FRENCH) A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-

TIONS OF T H E EUROPEAN COMMUNIT IES, BOITE POSTAL 1003 - LUXEMBOURG

FRANCE 0

8629 Date 1977 111110 122100 210000 810000 421140 Differential Neutron Data for Reactor Dosimetry. Paulsen, A.; Magurno, B.A. EUR - 5667E/F.PT.II,

CONF-750935,PT.II, PP.93 -111 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-

TIONS OF T H E EUROPEAN COMMUNIT IES, , BOITE POSTAL 1003 - LUXEMBOURG"1"'

BELGIU 6

8658 Date February 1979 111110 122310 210000 421140 430000 521130 810000

870098 Testing of E N D F / B Cross-Section Data in the Californi-

um-252 Neutron Benchmark Field. Mannhart, W. O R N L / R S I C - 4 2 , PP.119-133 " A V A I L A B I L I T Y - N T I S G E R M A N

PP.93 A 1 1 ;

V„»

8661 Date February 1979 < r 111110 122310 32A000 312000 210000 521130 810000

795254 794000 Sensitivity and Uncertainty Analysis Applied to the

NBS- ISNF. Broadhead, B.L.; Marable, J.H. ORNL/RSIC-42 , PP.161-178 A V A I L A B I L I T Y - N T I S U - T N

8095 Date June 1978 111110 210000 421140 521230 713000 810000 The Zero-Power Basis of Fast Rcactor Dosimetry. Sanders, J.E. AEEW-R-1183 A V A I L A B I L I T Y - U K A E A , A T O M I C ENERGY

ESTABLISHMENT, WINFRITH, ' DORCHESTER, DORSET, GREAT B R I T A I N

ENGLAN

8736 -.). . . Date March 1979 111400 112130 210000 32A000 521130 522130 551110

552110 552220 830000 851000 853900 795320 Radiation Transport in Earth for Neutron and Gamma Ray

Point Sources Above an A i r -Ground Interface. Lillie, R.A.; Santoro, R.T. O R N L / T M - 6 6 5 5 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

865 9 Date February 1979 111110 122310 210000 42M40 719AOO 861000 795112




ORNL /RS IC -42 , PP.135-143 A V A I L A B I L I T Y - N T I S HANFOR -i,

fi 866 0 : Date February 1979

111110 122310 210000 430000 521130 861000 810000 , Varied Applications of a New Maximum-Likelihood Code

with Complete Covariance Capability.. ,f.:.

8753 Date Apri l 1979 210000 870014 Transfer Damage Characterization by Neutron Displace-

ment Cross Section in Silicon: Experimental. Verbinski, V.V.; Cassapakis, C.; Pease, R.L.; Scott, H.L. NUCL. SCI. ENG., /0(1), .66-72 SCA

; ) ij 8830 Date March 1978o

4

111210 U10000 210000 717000 810000 ° ° D (I Radiation Considerations for Superconducting Fusion Mag-

nets. C ^ a

Abdou, M.A. r 0 o J. NUCL. MATER., 72(1 -2 ) . 147-167 A R G O N N

2548 " it 106

8855 Date September 1978 010000 122100 210000 7§0000 845000

.Basic Nuclear Data for Dosimetry in Radiotherapy and Radiobiology.

<^.icourt, A.; Chemtob, M.; Nguyen, V.D.; Parmentier, N. CONF-780921, PP.628-635 AVAILABIL ITY-OECD, 2, RUE ANDRE-PASCAL,

75775 PARIS CEDEX 16, FRANCE FRANCE „

8857 Date September 1978 010000 122100 210000 760000 845000 Nuclear Data for Radiotherapy with Neutrons. S-J 0

GA-A15356 A V A I L A B I L I T Y - N T I S $4.00 GEAC

Cross, W.p: CONF-780921. PP.648-666 AVAILABIL ITY-OECD, 2, RUE ANDRE-PASCAL,

75775 PARIS CEDEX 16, FRANCE CANADA

8858 ^ . Date September 1978 010000 122100 210000 760000 845000 Recent Trends in Nuclear Reaction Data Needs for Nuclear

Medicine. Stocklin, G.; Qaim, S.M. CONF-780921, PP.667-687 AVAILABIL ITY-OECD, 2, RUE ANDRE-PASCAL,

75775 PARIS CEDEX 16, FRANCE GERMAN

8875 Date 1979 111210-210000 717000 810000 Radiation Damage in Diagnostic Windows for the TFTR. Primak, W. 0

CONF-790125-12 AV A I L A B I L'lTY - DEP., NTIS " ARGONN

8876 Date 1979 0

010000 111210 210000 717000 810000 Q Effects of Irradiation on the Normal Metal of a Composite1

Superconductor: A Comparison o f Copper and Alumi-" num. Klabunde, C.E.; Coltman, R.R.,Jr.; Williams, J.M. CONF-790125-25 AVAILABIL ITY-DEP. , NTIS OARNL

8887 Date March 1979 ' 111210 210000 717000 861000 J

,;The Application of Martensitic Stainless Steels in Long Life-time Fusion First Wall/Blankets.

Rosenwasser, S.N,; Miller, P.; Dalessandro, J.A.; Rawls, <? , J.M.; Toffolov, W.E.; Chen, W.

Date June 1977 111110 121100 210000 810000 Damage Correlation in Theory and Practice. Doran, D.G.; Odette, G.R.; Simons, R.L.; Mansur, L.K. HEDL-SA-1144 -A ; CONF-770641-9 A V A I L A B I L I T Y - N T I S HANFOR

8909 Date January 1979 111210 210000 717000,810000 Tokamak Reactors and Structural Materials. Conn, R.W. UWFDM-288 V j

A V A I L A B I L I T Y - N U C L E A R ENGINEERING DEPARTMENT, UNIVERSITY OF WISCONSIN, MADISON, WI 53706

U - W I

8932.°. . . ,L'f Date January 1979 010000 111210 J2110(I 210000 521130 717000 795217

795254 810000 c , Transmutationj^and Activation of Fusion Reactor Wall and

Structural Materials.,! Jarvis, O.N. o " ; AERE-R-9298 0„ AVAILABILITY-H?M.S.O. ENGLAN , ,

p ^ Ti o^. %

r q -O 8951 o. Date May 1978

111210 210000 717000 870006 870014 An Assessment of Carbon and Silicon Carbide as First Wall

Materials in Inertial Confinement Fusion Reactors. Hopkins, G.R.; Price, R.J.pBullock, R.E.; Dalessandro, J.A.;

Hovingh, J. ° . CONF-780508,VOL.1, PP.324-333 AVAILABIL ITY-DEP. , NTIS GEAC

8952 Date May 1978 111210 210000 717000 FWLTB - A Mathematical Model to Calculate the Life-

time of the Fusion Reactor First Wall. Daenner, W.; Raeder, J. n CONF-780508,VOL.1, PP.347-356 ^

O

AVAILABIL ITY-DEP. , NTIS GERMAN

o

107

U 8955 . " . . . . " . Date May 1978

111210 123000 210000 531000 532000 793000 794000 810000 • (J

Computations of Nuclear Response Functions with M A C K - I V .

Abdou, M.A. ; Gohar, Y . (j <, CONF-780508,VOL.1, PP:402-410 A V A I L A B I L I T Y - D E P . , NT IS A R G O N N w, •

9030 DaiVOctober 1978 111210 210000 32AOOO 521130 717000 861000 862000

870023 870027 793000.^ . The Effects of Fe-N i -Co-V ' -S t ruc tu ra l Alloys on Fusion

Reactor Neutronic Performance. .Barnes, J.M.; Bishop, B.L.; Santoro, R.T.; Gabriel, T.A. O R N L / T M - 6 5 4 3 " " rf<> A V A l L A B I L I T Y - NT IS S4.00 O A R N L

d

8956 Date May 1978 010000 111210 210000 717000 810000 Materials Program for Magnetic Fusion Energy. Zwilsky, K.M.; Cohen, M.M. ; Finfgeld, C.R.; Reuther, T.C., CONF-780508,VOL.1, PP.549-553 ° ' A V A I L A B I L I T Y - D E P . , NT IS DOE

9 0 6 9 . . : Date Mid-December 1978 o 111210 210000 32A000 521130 810000 861000 117000-

• 795323 Minimizing Radioactivity and Other Features of Elemental

" -—and Isotopic Tailoring of Materials for Fusion Reactors. Conn, R.W.; Okula, K.; Johnson, A .W. N U C L . T E C H N O L O G Y , 41(3), 389-400;

U W F D M - 3 0 5 U - W I

, «

8957 Date May 1978 111210 210000 810000 The Damage Analysis and Fundamental Studies Program. Doran, D.G.; Farrar, H.,IV; Goland, A.N.; Greenwood,

L.R.; Heinrich, R.R.; Nolfi, F.V.; Odette, G.R.; Parkin, D.M.; Reuther, T.C.; Robinson, M.T.; Smidt, F.A.; Spraque, J.A.; Vandervoort, R.R.; Wilkes, P.

CONF-780508,VOL.1, PP.575-587 A V A I L A B I L I T Y - D E P . , NT IS H A N F O R

9337 Date June 1979 210000 841000 842000 844000 0

Compilation of Radiation Damage Test Data. Part 1: Cable Insulating Materials.

Schonbacher, H.; Stolarz-lzycka, A. CERN - 7 9 - 0 4 it A V A I L A B I L I T Y - E U R O P E A N O R G A N I Z A T I O N

FOR N U C L E A R RESEARCH (CERN), G E N E V A CERN

8962 Date Apr i l 1979 111110 111600 210000 521230 719A00 795254 861000


tamination of Neutron Dosimetry Procedures Used for Reactor Pressure Vessel Applications.

Simmons, G.L. E P R I - N P - 1 0 5 6 A V A I L A B I L I T Y - S C I E N C E o APPLICATIONS,

INCORPORATED, 1200 PROSPECT ST., LA J O L L A , C A L I F O R N I A 92038

SCA

9029 Date August 1979 111110 210000 717000 793000 810000 Calculated Irradiation Response of Materials Using Fission

Reactor (HF IR , ORR, and E B R - I I ) Neutron Spectra. Gabriel, T.A.; Bishop, B.L.; Wiffen, F.W. O R N L / T M - 6 3 6 1 -

. . A V A I L A B I L I T Y - N T I S $4.50 O A R N L

9386 Date August 1979 010000 111210 210000 717000 810000 A Critical Assessment of the Effects of Pulsed Irradiation on

Materials. .. Ghoniem, N .M. ; Kulcinski, G.L. U W F D M - 3 1 1 A V A I L A B I L I T Y - F U S I O N E N G I N E E R I N G 0 PRO-

G R A M , N U C L E A R E N G I N E E R I N G DEPT., U N I V E R S I T Y OF WISCONSIN, M A D I S O N , W I 53706 *

U - W I

9387 Date September 1979 111110 111210 210000 870029 870079 The Radiation Induced Order-Disorder Transformation in

Cu/sub 3/Au. ^Zee, R.; Wilkes, P. o U W F D M - 3 1 4 A V A I L A B I L I T Y - F U S I O N E N G I N E E R I N G PRO-

G R A M , N U C L E A R E N G I N E E R I N G DEPT., U N I V E R S I T Y OF WISCONSIN, M A D I S O N , W I 53706

U - W I

9427 Date August 1979 111210 111220 210000 717000 810000 Fusion Technology Development. Coffman, F.E.(Dir.) DOE/ET-O l 16/1 A V A I L A B I L I T Y - U . S . DOE, OFFICE OF FUSION

ENERGY, DIVISION OF DEVELOPMENT A N D TECHNOLOGY, WASHINGTON, D.C. 20545

DOE

9443 Date 1977 111220 210000 717000 810000 Jet Target Intense Neutron Source. Meier, K.L. L A - U R - 7 7 - 2 3 9 8 ; CCNF-771029-38 A V A I L A B I L I T Y - N T I S PC A 0 2 / M F A01 LOASL

Maniscalco, J.A.; Berwald, D.H.; Meier, W.R. CONF-790125, PT.A, PP.37-46; J. NUCLEAR


ING COMPANY - AMSTERDAM L A L L

9486 Date 1979 010000 111210 111220 210000 717000 810000 Irradiation Sources for Fusion Materials Development. Holmes, J.J.; Straalsund, J.L. CONF-790125, PT.A, PP.447-451; J. NUCLEAR



9455 Date 1979 111110 210000 861000 422110 511120 The Determination of Fast Neutron Fluence in Radiation

Stability Tests of Steel Samples. Hogel, J.; Vespalec, R. ZJE-237 A V A I L A B I L I T Y - S K O D A WORKS, NUCLEAR

POWER CONSTRUCTION DEPT., INFORMA-T I O N CENTRE, PLZEN - CZECHOSLOVAKIA

CZECHO

9487 Date 1979 111210 121100 210000 717000 810000 Experimental Evaluation of the Primary Damage Process -

Neutron Energy Effects. Goland, A.N. CONF-790125, PT.A, PP.453-461; J. NUCLEAR


ING COMPANY - AMSTERDAM BROOKH

9456 Date 1979 111110 210000 719AOO 861000 Radiation Damage and Annealing of C r - M o - V Steel. Vacek, M.; Havel, S.; Brunovsky, M. ZJE-239 A V A I L A B I L I T Y - S K O D A WORKS, NUCLEAR

POWER CONSTRUCTION DEPT., INFORMA-T I O N CENTRE, PLZEN - CZECHOSLOVAKIA

CZECHO

9482 Date 1979 010000 111210 210000 717000 Tokamak Reactors and Structural Materials. Conn, R.W. CONF-790125, PT.A, PP.9-16; J. NUCLEAR


ING COMPANY - AMSTERDAM U - W I


Inertial Confinement Fusion Systems.

9488 Date 1979 010000 111220 210000 410000 717000 The Fusion Materials Irradiation Test Facility at Hanford. Pottmeyer, E.W.,Jr. CONF-790125, PT.A, PP.463-465; J. NUCLEAR



9489 Date 1979 111220 210000 717000 Measurements and Calculations of Neutron Spectra from 35

MeV Deuterons on Thick Lithium for the FMIT Facili-ty.


CONF-790125, PT.A, PP.467-471; J. NUCLEAR MATER., 85 A N D 86,

A V A I L A B I L I T Y - NORTH - H O L L A N D PUBLISH-ING COMPANY - AMSTERDAM

HANFOR

109

9491 Date 1979 111220 122100 121100 210000 717000?,810000 Helium Accumulation Fluence Dosimetry for Fusion Reac-

tor Materials Irradiations. Kneff, D.W.; Farrar, H.,IV CONF-790125, PT.A, PP.479-483; J. NUCLEAR


ING COMPANY - AMSTERDAM ROI

9497 Date 1979 111210 210000 717000 810000 (f

Predicting the Effects of Radiation upon the Constitution of Fusion Reactor Materials.

Gittus, J.H.; Miodownik, A.P. CONF-790125, PT.A, PP.621-625; J. NUCLEAR


ING COMPANY - AMSTERDAM ENGLAN

9492 Date 1979 111110 210000 717000 870022 870023 870041 New Approach to Simulation of Helium and Simultaneous

Damage Production in Fusion Reactors - In Reactor Trit ium Trick.

Andresen, H.; Harling, O.K. CONF-790125, PT.A, PP.435-489; J. NUCLEAR


ING COMPANY - AMSTERDAM U - M A

9493 Date 1979 111220 210000 717000 810000 Spatial Variations of Damage Parameters in F M I T and

Their Implications. Schiffgens, J.O.; Simons, R.L.; Mann, F.M.; Carter, L.L. CONF-790125, PT.A, PP.491-495; J. NUCLEAR



9494 Date 1979 111210 210000 717000 870013 Fusion-Fission Neutron Damage Ratio for Alumina. Evans, B.D.; Stapelbroek, M. CONF-790125, PT.A, PP.497-502; J. NUCLEAR


ING COMPANY - AMSTERDAM N A V Y

9495 Date 1979 111210 II1220 210000 717000 870029 870079 The Nature of High Energy Neutron Damage in Copper and

Gold. Narayan, J.; Ohr, S.M. CONF-790125, PT.A, PP.5I5-519; J. NUCLEAR

MATER., 85 A N D 86, A V A I L A B I L I T Y - NORTH - H O L L A N D PUBLISH-

ING COMPANY - AMSTERDAM O A R N L

9618 Date August 1979 113100 210000 851000 Probabilistic Approach to EMP Assessment. Bevensee, R.M.; et al. UCRL-52,804" A V A I L A B I L I T Y - N T I S L A L L , u

9637 Date March 1980 210000 717000 795180 Neutron Moderation in Inertial Confinement Fusion Pellets

and Effects on Damage and Radioactive Inventory. Beranek, F.; Conn, R.W. NUCL. TECHNOLOGY, 47(3), 406-411 U - W I

9723 Date January 1980 210000 717000 870006 870014 Radiation Damage by High-Energy Neutrons. Primak, W. NUCL. SCI. ENG., 73(1), 29-34 ARGONN

9782 Date December 1979 010000 111210 210000 717000 810000 Review of Nuclear Heating in Fusion Reactors. (Review

Paper No.A2) Seki, Y. IAEA-TECDOC-223 , PP.31-45 A V A I L A B I L I T Y - M F O N L Y - INIS MICROFICHE

CLEARINGHOUSE, IAEA, WAGRAMER-STRASSE 5, P.O. BOX 100,, A-1400 V IENNA, AUSTRIA

JAPAN



Qaim, S.M. IAEA-TECDOC-223 . PP.75-89

110

A V A I L A B I L I T Y - M F O N L Y - INIS MICROFICHE CLEARINGHOUSE, IAEA, WAGRAMER-STRASSE 5, P.O. BOX 100, A-1400 V I E N N A , AUSTRIA

G E R M A N

Russo, AJ . ; Wayland, J.R.; Ritchie, L.T. r. SAND-76-0534 A V A I L A B I L I T Y - N T I S SANDIA

9825 Date March 1980 112720 210000 717000 870007 Gamma Irradiation of Nitrate-Based Salts. Breon, S.R.; Chellew, N.R.; Clemmer, R.G.; Hoh, J.C. A N L / F P P / T M - 1 2 9 A V A I L A B I L I T Y - N T I S , PC A03 /MF A01 ARGONN

9965 Date June 1980 111210 210000 717000 870022 Assessment of Titanium Alloys for Fusion Reactor

First - Wall and Blanket Applications (Research Project 1045-3) Final Report.

Jones, R.H.; Leonard, B.R.,Jr.; Johnson, A.B.,Jr. EPRI -AP-1433 A V A I L A B I L I T Y - R E S E A R C H REPORTS CENTER,

BOX 50490, PALO ALTO, CA 94303 BANL

6698 Date Apri l 1978 113100 220000 329000 423210 423250 553120 845000 An Evaluation of the Distribution of Absorbed Dose in Child

Phantoms Exposed to Diagnostic Medical X-Rays. Chen, W.; Poston, J.W.; Warner, G.G. O R N L / T M - 5 9 3 3 A V A I L A B I L I T Y - N T I S O A R N L

6737 Date 197u 220000 Application of Variational Methods to Fusion Reactor Blan-

ket Studies. Cheng, E.T.C. THESIS A V A I L A B I L I T Y - U N I V E R S I T Y MICROFILMS

ORDER N0.76-28,905 U - I L

Biological Effects and Health Physics


6417 Date Dec. 1977 020000 220000 Shielding Standards--A Case History. Battat, M.E. CONF-770401, PP.457-462 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE



rium Beam Injectors. Kim, J. O R N L / T M - 6 1 8 9 A V A I L A B I L I T Y - N T I S 54.50 OARNL


Material Releases.

6856 Date 1978 111110 220000 423135 521210 Neutron Response of a New Albedo-Neutron Dosimeter. Blackstock, A.W.; Cortez, J.R.; Littlejohn, G.J.; Storm, E. L A - U R - 7 8 - 4 0 ; CONF-780110-8 A V A I L A B I L I T Y - D E P . , NTIS LOASL

6857 Date January 1978 112710 220000 222000 230000 Preliminary Assessment of the Radiological Protection

Aspects of Disposal of High - Level Waste in Geologic Formations.

Hil l, M.D.; Grimwood, P.D. NRPD-R69 A V A I L A B I L I T Y - H M S O E N G L A N

6870 Date May 1978 111110 220000 551110 552210 845000 Depth Dose, Dose Equivalent and Quality Factor for Leak-

age Neutron Spectra from Critical Assemblies. Singh, D.; Bisht, J.S.; Madhvanath, U. NUCL. INSTRUM. METHODS, 151(1,2), 331-338 JAPAN

111

6887 Date March 1977 020000 220000 610000 Neutron and Gamma-Ray Flux- to-Dose-Rate Fac-

tors. Battat, M.E. ANSI /ANS-6.1 .1-1977 A V A I L A B I L I T Y - A M E R I C A N NUCLEAR SOCIETY,

555 N O R T H KENSINGTON, AVE., LAGRANGE PARK, I L L I N O I S 60525 $12.00

AMNS

6893 Date 1977 020000 220000 430000 Radiation Protection Instrumentation Test and Calibration. Selby, J.M.; Larson, H.V.; Bartlett, W.T.; Mulhern, O.R.;

Fleming, D.M. CONF-771209-12; I A E A - S M - 2 2 2 / 0 6 AVA ILAB IL ITY -DEP. , NTIS BANW

6957 Date 1977 010000 220000 Sources and Effects of Ionizing Radiation: UNSCEAR 1977

Report. United Nations Scientific Committee on the Effects of

Atomic Radiation U N PUB. SALES NO.E.77.IX-1 A V A I L A B I L I T Y - U N I T E D NATIONS, SALES SEC-

TION, NEW YORK OR GENEVA $28.00 IAEA >

7078 Date January 1977 010000 121200 220000 423240 Actual Problems in Photon Dosimetry. Regulla, D.F.; Drexler, G. NBS SPEC. PUB. 461, PP. 197-208 AVA ILAB IL ITY -SUPT . OF DOCUMENTS, GPO,

WASHINGTON, D.C. 20402 GERMAN

7091 Date February 1974 112930 220000 222000 713000 719A00 719B00 Projections of Radioactive Wastes to be Generated by the


RATORY OARNL

7092 Date January 1975 112930 220000 222000 795185 795304 870092 870094

A Comparison of the Potential Radiological Impact of Recy-cle 233 -U HTGR Fuel and LMFBR Plutonium Fuel Released to the Environment.

Till, J.E. O R N L - T M - 4 7 6 8 A V A I L A B I L I T Y - O A K RIDGE N A T I O N A L LABO-

RATORY OARNL


Radiotherapy. Wells, A.H. L A - 7 2 8 8 - T A V A I L A B I L I T Y - N T I S $13.25 LOASL

8025 ' Date July 1978 112930 220000 222000 717000 810000 Application of Probabilistic Consequence Analysis to the

Assessment of Potential Radiological Hazards of Funon Reactors.

Sawdye, R.W.; Kazimi, M.S. MITNE-220 AVAILABIL ITY-MASSACHUSETTS INSTITUTE


8034 Date August 1978 111110 220000 32A000 551110 552210 820000 861000

853100 793000 Nuclear Accident Dosimetry: Calculations and Comparison

with Experimental Data. Santoro, R.T.; Alsmiller, R.G.,Jr.; Barnes, J.M. ORNL /TM-6401 /R1 A V A I L A B I L I T Y - N T I S $4.00 OARNL

8045 Date January 1978 329000 220000 Isotropic and Cloud Source Irradiation by Monoenergctic

Neutrons and Photons. Jones, T.D.; Poston, J.W. HEALTH PHYS., 34(1), 83-93 OARNL

8210 Date March 1978 112760 220000 Dose-Response Curves from Incomplete Data. Groer, P.G. O R A U / I E A - 7 8 - 9 ( M ) A V A I L A B I L I T Y - N T I S

112

OARAU

8212 Date October 1978 010000 111130 112130 220000 521120 522120 Organ Dose Estimates for the Japanese Atomic-Bomb Sur-" vivors. Kerr, G.D. ORNL-5436 A V A I L A B I L I T Y - N T I S $5.25 OARNL

8213 Date April 25, 1978 112110 112710 220000 845000 Estimates of Internal Dose Equivalent to 22 Target Organs

for Radionuclides Occurring in Routine Releases from Nuclear Fuel-Cycle Facilities. Vol.1.

Killough, G.G.; Dunning, D.E.,Jr.; Bernard, S.R.; Pleasant, J.C.

O R N L / N U R E G / T M -190; NUREG/CR-0150 AVAILABIL ITY-DEP. , NTIS OARNL



Kocher, D.C. O R N L / T M - 6526 A V A I L A B I L I T Y - N T I S $6.00 OARNL

8379 Date August 1978 220000 632110 Depth Dose, Dose Equivalent and Quality Factor for Reac-

tor Neutron Spectra. Singh, D.; Bisht, J.S.; Madhvanath, U. HEALTH PHYS., 35(2), 369-374 INDIA

8381 Date September 1978 220000 Fluence- and Exposure-to-Dose Conversion Human

Whole-Body Irradiation. (Notes) O'Brien, K. HEALTH PHYS., 35(3), 494-495 DOE

8384 Date September 1978 220000 The Application of the Dose-Equivalent Index to the Natu-

ral Radiation Background. (Letters to the Editor)

O'Brien, K. HEALTH PHYS., 35(3), 506-508 DOE

8401 Date July 1978 121100 121200 122110 122210 220000 531000 532000

794000 810000 M A C K - I V , A New Version of MACK: A Program to Cal-


Abdou, M.A.; Gohar, Y.; Wright, R.Q. A N L / F P P - 7 7 - 5 A V A I L A B I L I T Y - N T I S $6.00 ARGONN

8403 Date March 1978 122110 122210 220000 531000 532000 793000 794000



Gohar, Y.; Abdou, M.A. ANL /FPP /TM-106 A V A I L A B I L I T Y - N T I S $9.25 ARGONN ,

8434 Date November 1978 010000 220000 222000 223000 230000 Radiation Exposure of the UK Population. Taylor, F.E.; Webb, G.A.M. NRPB-R77 A V A I L A B I L I T Y - H M S O ENGLAN

8456 Date October 1978 112760 220000 223000 632300 861000 Generic Assessment of Radiation Exposures to Workers in

a Portable Smelter and to the Surrounding Population. Randolph, M.L.; Watson, A.P.; O'Donnell, F.R. ORNL/TM-6442 A V A I L A B I L I T Y - N T I S OARNL

8459 Date October 1978 111210 112760 102930 220000 223000 521130 531000

532000 795303.795254 717000 810000 32A000 Safety Aspects of Activation Products in a Compact Toka-

mak Fusion Power Plant. Willenberg, H.J.; Bickford, W.E. PNL-2823 A V A I L A B I L I T Y - N T I S PANL

113

8505 Date 1978 010000 220000 420000 Instrumentation and Monitoring Methods for Radiation

Protection. NCRP NCRP-57 A VAILABILITY - NCRP PUBLICATIONS, P.O. BOX


Radiation Dose to Construction Workers at Operating Nuclear Power Plant Sites. Final Report, Sept. 1975 -Sept. 1978.

Endres, G.W.R.; Shipler, D.B. NUREG/CR-0426; PNL-2773 AVAILABILITY-DEP., NTIS PANL



Kelly, G.N.; Jones, J.A.; Simmonds, J.R. NRPB-R73 AVAILABILITY - H MSO ISBN 0 85951 082 4 ENGLAN i{

8731 Date December 15, 1978 220000 Operational Radiation Safety Program. NCRP NCRP-59 AVAILABILITY-NATIONAL COUNCIL ON RADI-

ATION PROTECTION AND MEASUREMENTS, 7910 WOODMONT AVENUE, WASHINGTON, D.C. 20014

NCRP

8512 Date December 1978 010000 220000 On Dose-Response and Standard Setting. Weinberg, A.M. ORAU/IEA-78-2KO) AVAILABILITY-NTIS OARAU

8513 Date January 1978 112910 220000 410000 423210 The KFM, a Homemade yet Accurate and Dependable Fall-

out Meter. Kearny, C.H.; Barnes, P.R.; Chester, C.V.; Cortner, M.W. ORNL-5040 AVAILABILITY-NTIS OARNL ;

8624 Date 1977 111110 210000 220000 713000 795179 Sensitivity of Fluence-to-Dose Conversion to Changes in

Fast Pulse Reactor Spectra. Kazi, A.H.; Dunn, T.A.; Saccenti, J.C. EUR-5667E/F.PT.I, PP.808-822;

CONF-750935,PT.I, PP.808-822 AVAILABILITY-OFFICE FOR OFFICIAL PUBLICA-


ARMY

8649 Date October 1978 220000 223000 423135 423250

8734 Date March 1979 112760 220000 222000 870090 870094 793000 Doses for Various Pathways to Man Based on Unit Concen-

trations of Radionuclides Pertinent to Decontamination and Decommissioning of Properties.

Hill, G.S. ORNL/OEPA-7 AVAILABILITY-NTIS OARNL

8735 Date February 1979 112760 220000 795185 AQUAMAN - A Computer Code for Calculating Dose

Commitment to Man from Aqueous Releases of Radionuclides.

Shaeffer, D.L.; Etnier, E.L. ORNL/TM-6618 AVAILABILITY-NTIS OARNL

8780 Date January 1979 010000 220000 Doses in Radiation Accidents Investigated by Chromosome

Aberration Analysis. IX. A Review of Cases Investigat-ed: 1978.

Lloyd, D.C.; Purrott, R.J.; Prosser, J.S.; White, A.D.; Dol-phin, G.W.; Reeder, E.J.; Martin, L.C.; Priseman, S.J.; Gray, S.A.

NRPB-R83 AVAILABILITY - HMSO ENGLAN y< "

114




NUREG/CR-0134; O R N L / N U R E G / T M - 2 1 5 AVA ILAB IL ITY -DEP. , NTIS O A R N L

8785 Date April 1979 112760 220000 795337 810000 845000 Dose-Rate Conversion Factors for External Exposure to

Photon and Electron Radiation from Radionuclides Occurring in Routine Releases from Nuclear Fuel Cycle Facilities.

Kocher, D.C. NUREG/CR-0494; O R N L / N U R E G / T M - 2 8 3 A V A I L A B I L I T Y - N T I S O A R N L

8835 Date 1978 112930 220000 222000 610000 Manual of Dose Evaluation from Atmospheric Releases. Shirvaikar, V.V.; Abrol, V. B.A.R.C./I-503 A V A I L A B I L I T Y - B H A B H A ATOMIC RESEARCH

CENTRE, BOMBAY, IND IA I N D I A '

t!

8854 Date September 1978 010000 122100 122200 220000 312000 32A000 760000


Dose and Simulation of Tissue Response in Neutron Therapy.

Pfister, G.; Hehn, G.; Mattes, M.; Friedlein, H.P. CONF-780921, PP.621-627 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL,

75775 PARIS CEDEX 16, FRANCE G E R M A N

8904 Date March 1979 111500 220000 329000 845000 793000 795203 Neutron and Gamma Ray Response/Fluence Factors for

Human Dosimetry Applications. Kaul, D.; Chen, S.; Jarka, R. SAI-121 - 1 3 2 - 1 A V A I L A B I L I T Y - S C I E N C E APPLIATIONS, INC.,

1701 EAST WOODFIELD R D , SUITE 819, SCHA;JMBURG, ILL . 60195

SCA

8905 Date May 1979 111130 111400 112130 220000 794000 793000 845000 Predicting Probability of Early Mortality from Acute Expo-

sure to Mixed LET Radiation. Kaul, D. S A I - 1 2 1 - 1 3 2 - 4 - 7 9 A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, INC.,

1701 EAST WOODFIELD RD., SUITE 819, SCHAUMBURG, ILL. 60195

SAI

8930 Date 1974 000000 220000 SAFE H A N D L I N G OF RADIAT ION SOURCES. Oberhofer, M. BOOK A V A I L A B I L I T Y - M U N C H E N , VERLAG TH IEMIG G E R M A N

„8974 Date June 1979 220000 845000 Internal Dosimetry Data and Methods of I C R P - - P a r t 1. Ford, M.R.; Bernard, S.R.; Dillman, L.T.; Watson, S.B. NUREG/CR-0789; O R N L / N U R E G / T M - 3 1 5 A V A I L A B I L I T Y - N T I S O A R N L


Recommendations. Dobson, R.L. UCRL-81774; CONF-790316-1 A V A I L A B I L I T Y - D E P . , NTIS L A L L

8993 Date February 1, 1979 111110 220000 511110 632110 820000 842000 853100 Depth-Dose Distribution for Fission Neutron Spectra

Degraded Through Low Z Shields. Singh, D.; Bisht, J.S.; Madhvanath, U. NUCL. INSTRUM. METHODS, 159(1), 229-234 I N D I A

8995 Date Apri l 1, 1979 220000 521210 522210 Statistical Errors of Dose Estimation in Personnel Neutron

Monitoring with Albedo Dosimeters. Burgkhardt, B.; Heinselmann, M.; Piesch, E.; Viragh, E. NUCL. INSTRUM. METHODS, 160(3), 533-540 G E R M A N

115

9027 Date June 1979 112930 220000 222000 795304 AIRDOS-EPA: A Computerized Methodology for Esti-


Moore, R.E.; Baes, C.F., I I I ; McDowell-Boyer, L.M.; Watson, A.P.; Hoffman, F.O.; Pleasant, J.C.; Miller, C.W.

ORNL-5532 A V A I L A B I L I T Y - D E P . , NTIS O A R N L

9044 Date December 1978 112BOO 329000 220000 845000 Realistic Calibration of Whole- Body Counters for Measur-

ing Plutonium. Parkinson, W.W.,Jr.; Goans, R.E.; Good, W.M. STI/PUB - 471 ( VOL.2),PP. 155 -166;

CONF-771209 - P2,PP. 155 -166; A V A I L A B I L I T Y - I N T E R N A T I O N A L ATOMIC

ENERGY AGENCY, V IENNA (AUSTRIA) OARNL

9031 Date July 1979 111210 220000 223000 420000 423140 717000 Neutron Personnel Dosimetry Considerations for Fusion

Reactors. Barton, T.P.; Easterly, C.E. ORNL /TM-6756 A V A I L A B I L I T Y - N T I S O A R N L


try. Seltzer, S.M.; Hubbell, J.H.; Berger, M.J. STI/PUB-471(VOL.2),PP.3-43;

CONF-771209-P2.PP.3-43; A V A I L A B I L I T Y - I N T E R N A T I O N A L ATOMIC

ENERGY AGENCY, V IENNA (AUSTRIA) NABS

9039 Date December 1978 020000 220000 423210 430000 Wall Effects in Gamma-Ray Dosimetry. Jarrett, R.D.; Brynjolfsson, A.; Wang, C.P. STI/PUB-471(VOL.2),PP.91 -102;

CON F - 771209 - P2,PP.91-102; AVA ILAB IL ITY - INTERNATIONAL ATOMIC

ENERGY AGENCY, V IENNA (AUSTRIA) A R M Y

9046 Date December 1978 020000 220000 430000 Quelques Ameliorations en Spectrometrie Gamma a Basse

Activite. Bailar, J.; Caboret, J. STI/PUB -471 (VOL.2),PP. 189 - 198;

CON F - 771209 - P2,PP. 189 - 198; A V A I L A B I L I T Y - I N T E R N A T I O N A L ATOMIC

ENERGY AGENCY, V IENNA (AUSTRIA) CANADA

9061 Date June 1979 220000 Quality Factor Calculations! for Neutron Spectra Below 4

MeV. i Borak, T.B.; Stinchcomb, T.G'^ HEALTH PHYS., 36(6), 687^693 U - C O

9070 : Date June 1979 111500 329000 220000 845000 Calculation of Fast Neutron Depth-Dose in the 1CRU

Standard Tissue Phantom and the Derivation of Neutron Fluence-to-Dose-Index Conversion Factors.

Chen, S.-Y. ; Chilton, A.B. RADIATION RES., 78(3), 335-370 U - I L

9042 Date December 1978 020000 112710 220000 Standardized Radioactive Decay Data Sets for Use in Radi-

ation Dosimetry. Kocher, D.C.; Ewbank, W.B.; Martin, M.J. STI/PUB - 471 (VOL.2), PP. 139 -145;

CONF - 771209 -P2,PP. 139-145; A V A I L A B I L I T Y - I N T E R N A T I O N A L ATOMIC

ENERGY AGENCY, VIENNA (AUSTRIA) OARNL

9111 Date August 1979 112930 220000 222000 795304 INGDOS - A Conversational Computer Code to Imple-

ment U.S. Nuclear Regulatory Commission Regulatory Guide 1.109 Models for Estimation of Annual Doses from Ingestion of Atmospherically Released Radionu-clides in Foods.

Pleasant, J.C. ORNL/TM-6571 ^ A V A I L A B I L I T Y - N T I S OARNL

116

9112 Date July 1979 112930 220000 222000 The Evaluation of Selected Predictive Models and Parame-

ters for the Environmental Transport and Dosimetry of Radionuclides.

Miller, C.W.; Dunning, D.E.,Jr.; Etnier, E.L.; Hoffman, F.O.; Little, C.A.; Meyer, H.R.; Shaeffer, D.L.; Ti l l , J.E.

ORNL /TM-6663 A V A I L A B I L I T Y - N T I S O A R N L

9165 Date April 15, 1979 010000 220000 Quantitative Concepts and Dosimetry in Radiobiology. Wyckoff, H.O. (Ch.) ICRU-30 A V A I L A B I L I T Y - I C R U PUBLICATIONS, P.O. BOX


9179 Date August 1979 020000 220000 222000 The Estimation of Derived Limits. Harrison, N.T.; Bryant, P.M.; Clarke, R.H.; Morley, F. NRPB-DL1 A V A I L A B I L I T Y - H M S O ENGLAN

9196 Date December 1978 , 020000 220000 430000 Dissemination en France des Unites'des Grandeurs Utilisees

en Metrologie des Rayonnements Ionisants. Guiho, J.-P.; Simoen, J. -P. STI /PUB-471 (VOL.1), PP.3-19; CONF-771209-P1,

PP.3-19; A V A I L A B I L I T Y - I A E A FRANCE

9197 Date December 197.8 020000 220000 430000 Etudes Dosimetriques Menees au LMRI dans le Domaine

des References Primaires et des Procedures de Transfert. Simoen, J. -P. ST I /PUB-47 l (VOL. 1), PP.21 -32;

CONF-771209-P1, PP.21-32; A V A I L A B I L I T Y - I A E A FRANCE

G

}J 9198 Date December 1978 020000 220000 430000 Current Work in the Field of Standardization in Dosimetry

of Photons and Electrons in the Federal Republic of Ger-many.

Reich, H. STI /PUB-471 (VOL. 1), PP.33-52;

CONF-771209-PI , PP.33-52; A V A I L A B I L I T Y - I A E A GERMAN

9199 Date December 1978 020000 220000 430000 A Primary Standard for Determination of Absorbed Dose in

Water for X-Rays Generated at Potentials of 7.5 to 30 kV.

Bohm, J.; Hohlfeld, K.; Reich, H. STI /PUB-471 (VOL.1), PP.53-63;

CONF-771209-PI , PP.53-63; A V A I L A B I L I T Y - I A E A GERMAN

9200 Date December 1978 020000 220000 430000 Traceability in Ionizing Radiation Measurements Systems. Cavallo, L.; Ehrlich, M.; Hutchingson, J.M.R. STI /PUB-471 (VOL.1), PP.65-87;

CONF-771209-P1, PP.65-87; AVAI L A B I L I T Y - I A E A NABS

9201 Date December 1978 020000 220000 430000 Dosimetry Standards for Industrial Radiation Processing. McLaughlin, W.L. STI/PUB - 471 (VOL. 1), PP.89-106;


9202 Date December 1978 020000 220000 430000 Primary and Secondary Standards of Dosimetry; Calibra-

tion Methods in Hungary. Zsdanszky, K. STI /PUB - 471 (VOL. 1), PP.107-117;

CONF-771209-P1, PP.107-117; A V A I L A B I L I T Y - I A E A HUNGAR

9203 Date December 1978 020000 220000 430000 Standardization in Radiation Dosimetry in the United King-

dom. Jennings, W.A. STI /PUB-471 (VOL.1), PP.119-131;

CONF-771209-P1, PP.119- 131; A V A I L A B I L I T Y - I A E A

117

E N G L A N


cal Field. Rossiter, M.J. STI /PUB -471 (VOL. 1), PP.133-138;

CONF-771209-PI , PP.133-138; A V A I L A B I L I T Y - I A E A E N G L A N ,

9205 Date December 1978 020000 220000 430000 Current Work on Dosimetry Standards in Japan. Moriuchi, Y. STI /PUB-471(VOL. l ) , PP.139-158;

CONF-771209-P1, PP.139-158; A V A I L A B I L I T Y - IAEA JAPAN

9206 Date December 1978 020000 220000 430000 Medical Dosimetry Standards Programme of the National

Bureau or Standards. Loevinger, R. S T I / P U B - 471 (VOL. 1), PP.159-174;

CONF-771209-P1, PP.159-174; > A V A I L A B I L I T Y - IAEA NABS

9209 Date December 1978 020000 220000 430000 The Austrian Dosimetry Laboratory: A National Standard

and Routine Calibration Centre. Duftschmid, K.E. STI /PUB-471 (VOL. 1), / ) PP.199-212;

CONF-771209-P1, PP.199-212; A V A I L A B I L I T Y - I A E A AUSTRI

9210 Date December 1978 020000 220000 430000 Exposure Intercomparison with Ionization Chambers -

Based on Three Intercompared Check Sources. Nette, P.; Reis, D.; Eckerl, H.; Drexler, G.; Pychlau, P. STI /PUB-471 (VOL.1), PP.213-218;

CONF-771209-P1, PP.213-218; A V A I L A B I L I T Y - I A E A BRAZIL

9211 Date December 1978 020000 220000 430000 The Regional Calibration Laboratory at the M.D. Anderson

Hospital. Humphries, L.J.; Shalek, R.J. STI /PUB-471 (VOL.1), PP.219-227;

CONF-771209-PI , PP.219-227; A V A I L A B I L I T Y - I A E A U - T X

9207 Date December 1978 020000 220000 430000 The Secondary Standard Dosimetry Laboratory — A

Necessary Link in the Dissemination Chain. Julius, H.W.; van der Lugt, G. STI /PUB-471 (VOL.I) , PP.189-192;

CONF-7712Q9-P1, PP.189-192; A V A I L A B I L I T Y - I A E A NETHER

9212 Date December 1978 020000 220000 430000 Primary Dosimetric Standards at the Memorial

Sloan-Kettering Cancer Center. Holt, J.G.; McDonald, J.C.; Buffa, A.; Perry, D.; Ma, L;

Laughlin, J.S. STI /PUB-471 (VOL.1), PP.229-240;

CONF-771209-P1, PP.229-240; A V A I L A B I L I T Y - I A E A SLOAN

9208 Date December 1978 020000 220000 430000 Evaluation of the Need for Radiotherapy Calibrations in the

United States of America. Lanzl, L.H.; Rozenfeld, M. STI /PUB -471 (VOL. 1), PP.193-197;

CONF-771209-P1, PP.193-197; A V A I L A B I L I T Y - I A E A ° U - I L

9213 Date December 1978 020000 220000 410000 430000 The Organization and Opera C:''!;of the Regional Calibration

Laboratory at Victores" ' '..yeland. Simon, W.E. STI /PUB-471 (VOL.I) , PP.241-249;

CONF-771209-P1, PP.241-249; A V A I L A B I L I T Y - I A E A VICTOR

118

9214 Date December 1978 020000 220000 430000 The Role of the Secondary Standards Dosimetry Laboratory

in a Nuclear Power Util ity. Clarke, R.W.; Thompson, I.M.G. STI /PUB -471 (VOL. I) , PP.251-263;

CONF-771209-P1, PP.251-263; A V A I L A B I L I T Y - I A E A E N G L A N

9219 Date December 1978 020000 113100 220000 430000 The Need for Repeated Intercomparisons and Standardiza-

tion of X - R a y Dosimetry for the Co-Ordination of Late-Effects Research in Europe.

Zoetclief, J.; Broerse, J.J.; Puite, K.J. STI /PUB-471 (VOL.I ) , PP.305-317;

CONF-771209-P1, PP.3057317; A V A I L A B I L I T Y - I A E A NETHER

9215 Date December 1978 020000 220000 430000 Organization of a Secondary Standard Dosimetry Labora-

tory for the Indian'Region. Subrahmanian, G.; Sundararao, I.S. STI /PUB-471 (VOL.1), PP.265-272;

CONF-771209-PI , PP.265-272; A V A I L A B I L I T Y - I A E a I N D I A

9216 Date December 1978 020000 112720 220000 430000 Evaluation of Dosimetric Accuracy and Uniformity for

60-Co Radiation Therapy. Sundararao, I.S.; Naik, S.B.; Pushpandpangadan, K.D.;

Vadiwala, R.; Subrahmanian, G. STI /PUB-471( VOL.1), PP.273-280;

CONF-771209-P1, PP.273-280; A V A I L A B I L I T Y - IAEA IND IA

922 0 r f.. Date December 1978 020000 220000 430000 " Evaluation of the 1977 IAEA Pilot Study of Postal Dose

Intercomparison (TLD) for Orthovoltage X - R a y Ther-apy.

Bjarngard, B.E.; Ruden, B. - I . ; Eisenlohr, H.H.; Girzi-kowsky, R.; Haider, J.

STI /PUB-471 (VOL. I ) , PP.319-333; CONF-771209-PI , PP.319-333;

A V A I L A B I L I T Y - I A E A U - M A -

922 1 Date December 1978 020000 220000 430000 Dosimetric Primary and Secondary Standardization within

the European Communities. Oberhofer, M. STI /PUB-471 (VOL.1), PP.335-340;

CONF-771209-P1, PP.335-340; A V A I L A B I L I T Y - I A E A I T A L Y

9217 Date December 1978 020000 220000 The Role of ICRU in International Radiation Standards. Wyckoff, H.O. STI /PUB-471 (VOL.I ) , PP.283-289;

CONF-771209-PI , PP.283-289; A V A I L A B I L I T Y - I A E A ICRU



Thompson, I.M.G. f / STI /PUB-471(VOL. l ) , PP.343-365;

CONF-771209-P1, PP.343-365; A V A I L A B I L I T Y - IAEA ENGLAN

9218. Date December 1978 020000 220000^430000 Implications of Dosimetry Intercomparisons for Standard-

ization in Neutron Dosimetry for Biological and Medical Applications.

Broerse,,,J.J.; Burger, G.; Coppola, M. STI/P/.'/B- 471 (VOL. 1), PP.291-304;

; G'JNF - 771209 - P1, PP. 291 -,304; — A V A I L A B I L I T Y - I A E A ° v- 0

NETHER -o O-

9224 Date December 1978 020000 220000 430000 Use of a Phantom in Personnel Dosimetry Photon Calibra-

tions: « Bartlett, W.T.; Holland, J.P.; Hooker, C.D.; Mulhern, O.R.;

Fleming, D.M. STI /PUB-471(VOL. l ) , PP.465-474;

CONF-771209-P1, PP.465-474; A V A I L A B I L I T Y - I A E A BANW "

119

9225 Date December 1978 020000 111110 220000 430000 Personnel Dosimetry Intercomparison Studies at the ORNL

Health Physics Research Reactor. Dickson, H.W.; Gilley, L.W. STI /PUB - 471 (VOL. 1), PP.491-509;

CONF-771209-P1, PP.491-509; A V A I L A B I L I T Y - IAEA O A R N L

O 9227 Date December 1978

020000 220000 430000 Accuracy and Precision in Calibration of Low-Level Radi-

ation Monitors. Ackers, J.G. STI /PUB-471 (VOL.1), PP.527-532;

CONF-771209-PI , PP.527-532; A V A I L A B I L I T Y - IAEA NETHER

9281 Date 1978 111500 121100 220000 810000 Influence of Nuclear Data on Calculations of Neutron

Energy Deposition. Caswell, R. S.; Coyne, J. J. EUR-5848.PP.29-43; CONF-770597.PP.29-43 AVAILABIL ITY-OFFICE FOR OFFICIAL PUBLICA-


NABS „ 9284 Date 1978

111500 32A000 220000 551110 552210 795203 845000 Recent Results in Neutron Depth Dose Calculations. Burger, G.; Morhart, A.; Schraube, H. EUR - 5848.PP. 125 -143; C O N F - 770597,PP. 125 -143 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


G E R M A N />

a 9289 Date 1978

111220 220000 329000 421130 511120 820000 In-Phantom Neutron Spectrometry: A Comparison of

Experiment and Calculation. Harrison, K.G.; Taylor, A.J.; Holt, P.D.; Boot, S.J. EUR-5848,PP.411 -423; CONF-770597,PP.411 -423 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-

TIONS OF T H E EUROPEAN COMMUNITIES, BOITE POSTALE 1003 - LUXEMBOURG ISBN 92-825-0256-2

E N G L A N

9290 Date 1978 111220 220000 421140 421200 760000 842000 845000 Determination of Neutron and Gamma Spectra in a Mixed

(n, gamma)-Field. Schmidt, R.; Magiera, E. E U R - 5848,PP.443 -454; C O N F - 770597,PP.443 - 454 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


GERMAN

9291 Date 1978 111220 220000 760000 Radiation Quality Studies in Mixed Neutron-Gamma

Fields. Menzel, H.G.; Waker, A.J.; Grillmaier, R.; Bihy, L.; Hart-

mann, G. EUR - 5848,PP.481 -497; C O N F - 770597,PP.481-497 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


GERMAN 0

9293 Date 1978 111110 220000 421150 511120 Evaluation of Results of the European Neutron Dosimetry

Intercomparison Project (ENDIP). Broerse, J.J.; Burger, G.; Coppola, M.; Schraube, H.; Zoete-

lief, J. EUR-5848,PP.899-915; CONF-770597,PP.899-915 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


NETHER

9330 Date July 1979 112760 220000 329000 845000 Monte Carlo Calculations of the Response of an External

Detector to a Photon Source in the Lungs of a Heteroge-neous Phantom.

Bhati, S.; Sharma, R.C.; Somasundaram, S. HEALTH PHYSICS, 37(1), 145-159 IND IA

9375 Date July 1979 112930 220000 713000 845000 ^ The Radiological Consequences of Notional Accidental

Releases of Radioactivity from Fast Breeder Reactors: Sensitivity to the Dose-Effect Relationships Adopted for Early Biological Effects. .

Kelly, G.N.; Simmonds, J.R.; Smith, H.f Stather^ J.W.

0 120

NRPB-R87 A V A I L A B I L I T Y - H M S O ISBN 0 85951 HO 3 E N G L A N




NUREG/CR-0150,VOL.2; ' c

O R N L / N U R E G / T M -190/ V2 A V A I L A B I L I T Y - N T I S OARNL

9378 Date August 1978 220000 420000 Health Physics Instrument Manual. Gupton, E.D. ORNL-332(REV.5) 0

A V A I L A B I L I T Y - N T I S OARNL

9382 ?Date September 1979 111110 111210 111220 220000 420000 430000 European Workshop on Neutron Dosimetry for Radiation

Protection. Alberts, W.G.; Cosack, M.; Kluge, H.; Lesiecki, H.; Wag-

ner, S.; Zill, H.W. P T B - N D - 1 7 A V A I L A B I L I T Y - I N S T I T U T BERLIN DER PHYSI-

KALISCH - TECHNISCHEN BUNDESANSTALT,. ABBESTRABE 2-12, 1000 BERLIN 10 (CHAR-LOTTENBURG), ISSN 0572-7170

GERMAN

9525 Date September 1979 112710 112120 220000 222000 A General Model for the Transfer of Radioactive Materials

in Terrestrial Food Chains. Simmonds, J.R.; Linslcy, G.S.; Jones, J.A. NRPB-R89 A V A I L A B I L I T Y - H M S O P1.50 E N G L A N


Dose-Equivalent Index Presented in ANSI N13 . l l . Yoder, R.C.; Bartlett, W.T.; Courtney, J.W.; Hooker, C.D.;

Holland, J.A.; Hogan, B.T. NUREG/CR-1057; PNL-3219 AVA ILAB IL ITY -DEP. , NTIS, PC A05 /MF A01 PANL

9532 Date February 1979 111500 112B00 220000 32A000 551110 552110 552210

793000 795276 845000 ,v

Development of a Mid-Head Radiation? Hose Response Function.

Trubey, D.K.; Knight, J.R.; Bartine, D.E.; Pace, J.V.,III O R N L / T M - 6 6 3 4 A V A I L A B I L I T Y - N T I S S4.50 O A R N L


Below 20 MeV. Singh, M.S. UCP.L-52,850 A V A I L A B I L I T Y - N T I S L A L L

9394 Date October 1979 220000 329000 Monte-Carlo Simulation of Photon Transport in a Hetero-

geneous Phantom—I. Application to Chest Counting of Pu and Am.

Goans, R.E.; Warner, G.G. H E A L T H PHYS., 37(4), 533-542 O A R N L

9568 Date 1978 010000 020000 220000 SI Units in Radiation Protection. Jain, V.K.; Soman, S.D. BARC-964 AVAILABIL ITY-DEP. , NTIS (U.S. SALES ONLY),

PC A03/MF A01 IND IA

9466 Date November 15, 1979 220000 430000 The Response of a Spherical Neutron Survey Meter. Harrison, K.G. NUCL. INSTRUM. METHODS, 166(2), 197-201 E N G L A N c' <•

9609 Date December 1978 220000 223000 423135 423250 Radiation Dose to Construction Workers at Operating

Nuclear Power Plant Sites. Vol.2. Appendices A - F. Final Report, Sept. 1 9 7 S e p t . 1978.

Endres, G.W.R.; Shipler, D.B.

121

NUREG/CR-0426, VOL.2; PNL-2773, VOL.2 A V A I L A B I L I T Y - N T I S $9.00 PANL

9611 Date January 1980 112730 112730 220000 222000 Estimated Radiological Doses to the Maximumly Exposed

Individual and Downstream Populations from Releases of Tritium, Strontium-90, Ruthenium -106, and Cesi-um-137 from White Oak Dam.

Little, C.A.; Cotter, S.j . ORNL/TM-7039 A V A I L A B I L I T Y - N T I S OARNL

9642 Date February 1979 010000 220000 222000 223000 Nuclear Risks. Newcoicbe, H.B. AECL-6477 AVAILABIL ITY-DEP. , NTIS (U.S. SALES ONLY),

PC A03/MF A01 CANADA

9798 Date May 1980 020000 220000 Cost-Benefit Effects of Conversion to SI Units in Health

Physics. ^ Eichholz, G.G.; Poston, J.W.fFair, M.F.; Auxier, J.A. NUREG/CR-1419; ORNL/NUREG-68 A V A I L A B I L I T Y - N T I S ; GPO SALES PROGRAM,

DIV. OF TECHNICAL INFORMATION AND DOCUMENT CONTROL, U.S. NUCLEAR REGU-LATORY f iCOMMISSION, WASHINGTON, D.C. 20555 " ^

OARNL

9924 Date February 1980 112760 220000 222000 A Methodology for the Evaluation of the Collective Dose

from Radioactivity in Terrestrial Food Chains. Simmonds, J.R.; Linsley, G.S. NRPB-R97 A V A I L A B I L I T Y - H M S O ISBN 0 85951 124 3 ENGLAN

9926 Date May 1980 112930 220000 222000 795185

A Mathematical Model for Predicting the Probability of Acute Mortality in a Human Population Exposed to Accidentally Released Airborne Radionuclides. Final Report for Phase 1 of the Project: Early Effects of Inhaled Radionuclides.


NUREG/CR-1261; PNL-3257 AVAILAB IL ITY-PACIF IC NORTHWEST LAB.,

RICHLAND, WASH. PANL

9921 Date June 1980 112760 220000 222000 Uncertainties in the Calculation of Long-Term Collective

Dose and Health Effects - A Preliminary Assessment. Kocher, D.C.; Leggett, R.W.; Dunning, D.E.,Jr.; Ryan,

M.T.; Eckerman, K.F. NUREG/CR-1303; ORNL/NUREG/TM-378 AVAILABIL ITY-GPO SALES PROGRAM, DIVI-

SION OF TECHNICAL I N F p R M A T I O N A N D DOCUMENT CONTROL, U.S'JNUCLEAR REGU-LATORY COMMISSION, WASHINGTON, D.C;.; 20555

OARNL

9928 ' Date May 1980 112760 220000 795310 845000 SFACTOR: A Computer Code for Calculating Dose Equiv-

alent to a Target Organ Per Microcurie - Day Residence of a Radionuclide in a Source Organ — Supplemen-tary Report.

Dunning, D.E.,Jr.; Pleasant, J.C.; Killough, G.G. NUREG/CR-1523; ORNL/NUREG/TM-85 /S1 AVAILABIL ITY-GPO SALES PROGRAM, DIVI-

SION OF TECHNICAL INFORMATION L'ND DOCUMENT CONTROL, U.S. NUCLEAR REGU-LATORY COMMISSION, WASHINGTON, D.C. 20555

OARNL

10001 Date August 1980 112B00 220000 311000 329000 795299 845000 Adjoint MC Techniques and Codes for Organ Dose Calcula-

tions. Koblinger, L. ORNL/RSIC-44, PP.203-217 AVA ILAB IL ITY -NT IS , PC A16/MF A01 HUNGAR

f.«

o 122

B e t a - R a y Dose


6696 Date April 1978 111110 112120 221000 532000 422200 430000 794000


mal-Neutron Fission of 239-Pu Between 2 and 14000 Seconds.


O R N L / N U R E G - 3 4 A V A I L A B I L I T Y - N T F S S6.00 OARNL

Environmental Dose ' I

CATEGORY NUMBER 22200ft

6320 Date January 1977 112120 222000 632110 719A00 Development of a Model for the Assessment of Radiation

Fields Around Nuclear Power Plant Components. Lauridsen, K. RISO REPORT NO.353 A V A I L A B I L I T Y - S A L E S DISTRIBUTORS: JUL.

GJELLERUP, 87, SOLVGADE, DK-1307 COPEN-H A G E N K, D E N M A R K

D E N M A R

-6470 Date Dec. 1977 421200 112770 222000 719A00 In Situ Measurements with a Mobile Ge(Li) Spectrometer

Around a Nuclear Power Plant. Finck, R.; Liden, K.; Persson, R.B.R. CONF-770401, PP.897-904 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE



Material Releases^ Russo, A.J.; Wayland, J.R.; Ritchie, L.T. SAND-76-0534 A V A I L A B I L I T Y - N T I S SANDIA

6637 Date February 1978 112930 222000 A Model to Estimate Radiation Dose Commitments to the

World Population from the Atmospheric Release of Radionuclides (LWBR Development Program).

Rider, J.L.; Beal, S.K. W A P D - T M - 1 2 7 4 A V A I L A B I L I T Y - B E T T I S ATOMIC POWER LAB. BETTIS


Aspects of Disposal of High-Level Waste in Geologic Formations.

Hil l, M.D.; Grimwood, P.D. NRPD-R69 A V A l L A B I L I T Y - H M S O ENGLAN

6938 Date April 1978 020000 122000 223000 Environmental Radiation Protection Standards: An Appre-

ciati'"<i.' Richings, L.D.G.; Morley, F.; Kelly, G.N. NRPB-R71 A V A l LA BIL ITY ~ H MSO ENGLAN

6945 Date March 1978 112930 222000 329000 Monte Carlo Simulation of Turbulant Atmospheric Trans-

port and Comparisons with Experimental Data. Alsmitler, F.S.; Alsmiller, R.G.,Jr.; Bertini, H.W.; Begovich,

C.L. O R N L / T M - 6 2 9 1 AVAILABIL ITY-DEP. , NTIS $5.25 OARNL

6946 ' Date May 1978 U2760 112930 222000 717000 Assessment of Radiological Releases to the Environment

from a Fusion Reactor Power Plant. < Shank, K.E.; Oakes, T.W.; Easterly, C.E.

ORNL /TM-6368 A V A I L A B I L I T Y - N T I S $5.25 O A R N L

6982 Date March 1978 222000 230000 795304 A Radiological Assessment of Reprocessing Advanced Liq-

uid-Metal Fast Breeder Reactor Fuels. Til l, J.E.; Bomar, E.S.; Morse,. L.E.; Tennery, V.J.

u

123

NUCL. TECHNOLOGY, 37(3), 328-339 O A R N L

6997 Date 1977 112930 222000 Point Source Modeling - Sta<e-of- the-Art Assessment

of Computer Simulation of Localized Air Pollutant Emissions.

Fabrick, A.J. BOOK A V A I L A B I L I T Y - W E S T L A K E VILLAGE, CALIF.,

FORM A N D SUBSTANCE FORM



RATORY OARNL

n 7092J, .; Date January 1975

112930 220006\22000 795185 795304 870092 870094 A Comparison of the Potential Radiological Impact of Recy-


Till, J.E. O R N L - T M - 4 7 6 8 A V A I L A B I L I T Y - O A K RIDGE N A T I O N A L LABO-

RATORY O A R N L

8088 Date Mid-August 1978 112930 222000 719A00 795211 Potential Radiological Consequences of a Multiple Stream

Generator Tube Rupture. Fray, R.R. NUCL. TECHNOLOGY, 40(1), 52-61 PAGE

8090 Date September 1978 222000 717000 Calculation of Radiological Dose Due to Release of Trit ium

Oxides from Controlled Thermonuclear Reactors. McKone, T.E.; Kastenberg, W.E. NUCL. TECHNOLOGY, 40(2), 170-184 U - C A

8121 Date September 1978 222000 223000 Weldon Spring Dose Calculations. Dickson, H.W.; Hil l, G.A.; Perdue, P.T. ORNL /TM-6272 A V A I L A B I L I T Y - N T I S S4.50 O A R N L

8251 Date November 1978 222000 717000 859999 Trit ium Pathways and Handling Problems in a Laser Fusion

Reactor. Larsen, E.M.; Abdel-Khalik, S.I.; Ortman, M.S. NUCL. TECHNOLOGY, 41(1), 12-26 U - W I

8025 Date July 1978 112930 220000 222000 717000 810000 Application of Probabilistic Consequence Analysis to the

Assessment of Potential Radiological Hazards of Fusion Reactors.

Sawdye, R.W.; Kazimi, M.S. M I T N E - 2 2 0 A V A I L A B I L I T Y - M A S S A C H U S E T T S INSTITUTE


8048 Date June 1978 112930 222000 Methods for Calculating Population Dose from Atmospheric

Dispersion of Radioactivity. Cohen, B.L.; Jow, H.N.; Lee, I.S. H E A L T H PHYS., 34(6), 569-572 U - P A

0

8269 Date August 1978 010000 112120 222000 870092 870094 Needs and Accuracy Requirements for FPND in the Assess-

ment of Environmental Aspects. a Lindberg, L. IAEA-213, PP.33-39 A V A I L A B I L I T Y - I A E A , V IENNA (MF O N L Y ) SWEDEN



Kocher, D.C. ORNL /TM-6526 A V A I L A B I L I T Y - N T I S $6.00 O A R N L

124

8404 Date September 1977 222000 329000 Derivation of the Probability Density Function for a Sto-

chastic Nonlinear Advection Equation. Meyers, R.E.; O'Brien, E.E.; Scott, L.R. BNL-50732 A V A I L A B I L I T Y - N T I S $4.00 BROOKH

8434 Date November 1978 010000 220000 222000 223000 230000 Radiation Exposure of the UK Population. Taylor, F.E.; Webb, G.A.M. NRPB-R77 A V A I L A B I L I T Y - H M S O E N G L A N

8436 Date January 1979 112930 222000 870092 Potential Radiological Impacts of Recovery of Uranium

from Wet-Process Phosphoric Acid. Davis, W., Jr.; Haywood, F.F.; Danek, J.L.; Moore, R.E.;

Wagner, E.B.; Rupp, E.M. O R N L / E P A - 2 A V A I L A B I L I T Y - N T I S $8.00 OARNL

8547 Date December 15, 1978 222000 Calculation of the Radioactive Releases from the I ran-1

and I ran -2 Nuclear Power Plants. Azimi-Garakani, D.; Gaviri, A. NUCL. INSTRUM. METHODS, 157(3), 601-606 I R A N



Hil l, G.S. O R N L / O E P A - 7 A V A I L A B I L I T Y - N T I S O A R N L

NUREG-0016 (REV. l ) A V A I L A B I L I T Y - N T I S NURC

8784 Date March 1979 222000 HOTSED: A Discrete Element Model for Simulating

Hydrodynamic Conditions and Adsorbed and Dissolved Radioisotope Concentrations in Estuaries.

Fields, D.E.; Hetrick, D.M. NUREG/CR-0440; O R N L / N U R E G / T M - 2 6 6 A V A I L A B I L I T Y - N T I S O A R N L

8835 Date 1978 112930 220000 222000 610000 Manual of Dose Evaluation from Atmospheric Releases. Shirvaikar, V.V.; Abrol, V. B.A.R.C./ I -503 A V A I L A B I L I T Y - B H A B H A A T O M I C RESEARCH

CENTRE, BOMBAY, INDIA I N D I A

8973 Date April 1979 112710 223000 222000 719A00 Gamma Dose Measurements at Zion and Fort Calhoun Sta-


Kynaston, R.L.; Mclsaac, C.V.; Underwood, D.R. NUREG/CR-0755 A V A I L A B I L I T Y - N T I S $7.25 IDNEL

9005 Date 1979 112120 222000 230000 Generic Methodology for Assessment of Radiation Doses

from Groundwater Migration of Radionuclides in LWR Wastes in Shallow Land Burial Trenches.

Aikens, A.E.,Jr.; et al. A IF /NESP-013 A V A I L A B I L I T Y - D A M E S A N D MOORE, BETHES-

DA, M A R Y L A N D ATIF

8781 Date December 1978 112930 112710 112760 222000 719AOO Calculation of Releases of Radioactive Materials in Gaseous



9027 Date June 1979 112930 220000 222000 795304 AIRDOS-EPA: A Computerized Methodology for Esti-


Moore, R.E.; Baes, C.F., I I I ; McDowell-Boyer, L.M.; Watson, A.P.; HofTman, F.O.; Pleasant, J.C.; Miller, C.W.

ORNL-5532

125

A V A I L A B I L I T Y - D E P . , NTIS O A R N L

9111. . . Date August 1979 112930 220000 222000 795304 INGDOS - A Conversational Computer Code to Imple-

ment U.S. Nuclear Regulatory Commission Regulatory Guide 1.109 Models for Estimation of Annual Doses from Ingestion of Atmospherically Released Radionu-clides in Foods.

Pleasant, J.C. O R N L / T M - 6 5 7 1 A V A I L A B I L I T Y - NTIS O A R N L

9112 Date July 1979 112930 220000 222000 The Evaluation of Selected Predictive Models and Parame-

ters for the Environmental Transport and Dosimetry of Radionuclides.

Miller, C.W.; Dunning, D.E.,Jr.; Etnier, E.L.; Hoffman, F.O.; Little, C.A.; Meyer, H.R.; Shaeffer, D.L.; Ti l l , J.E.

O R N L / T M - 6 6 6 3 A V A I L A B I L I T Y - N T I S O A R N L

9130 Date June 1979 112930 222000 719A00 A I R W A Y - A FORTRAN Computer Program to Esti-


! Rider, J.L. W A P D - T M - 1 2 7 5 A V A I L A B I L I T Y - B E T T I S A T O M I C POWER LABO-

RATORY, WEST M I F F L I N , PA. BETTIS

9140 Date July-August 1979 010000 222000 An Analysis of NRC Methods for Estimating the Effects of

Dry Deposition in Environmental Radiological Assess-ments.

Miller, C.W.; Hoffman, F.O. NUCL. SAFETY, 20(4), 458-467 O A R N L

9179 Date August 1979 020000 220000 222000 The Estimation of Derived Limits. Harrison, N.T.; Bryant, P.M.; Clarke, R.H.; Morley, F. N R P B - D L 1 A V A I L A B I L I T Y - HMSO

ENGLAN

952 5 Date September 1979 112710 112120 220000 222000 A General Model for the Transfer of Radioactive Materials

in Terrestrial Food Chains. Simmonds, J.R.; Linsley, G.S.; Jones, J.A. NRPB-R89 A V A I L A B I L I T Y - H M S O P1.50 ENGLAN

952 6 Date September 1979 112710 112120 112930 222000 A Model for Short and Medium Range Dispersion of

Radionuclides Released to the Atmosphere. Clarke, R.H. NRPB-R91 A V A I L A B I L I T Y - H M S O P2.00 E N G L A N

9611 Date January 1980 112730 112730 220000 222000 Estimated Radiological Doses to the Maximumly Exposed

Individual and Downstream Populations from Releases of Trit ium, Strontium - 90, Ruthenium -106, and Cesi-um-137 from White Oak Dam.

Little, C.A.; Cotter, S.J. ORNL /TM-7039 A V A I L A B I L I T Y - N T I S OARNL

9642 Date February 1979 010000 220000 222000 223000 Nuclear Risks. Newcombe, H.B. AECL-6477 AVAILABIL ITY-DEP. , NTIS (U.S. SALES ONLY) ,

PC A03 /MF A01 CANADA

0

9738 Date M i d - A p r i l 1980 222000 631000 731200 Effects of Indoor Residence on Radiation Doses from Rou-

tine Releases of Radionuclides to the Atmosphere. Kocher, D.C. NUCL. TECHNOLOGY, 48(2), 171-179 OARNL

9849 Date January 1980 112710 222000 230000 887000 The Effects of Actinide Separation on the Radiological Con-

sequences of Disposal of High-Level Radioactive Waste on the Ocean Bed.

126

Camplin, W.C.; Grimwood, P.D.; White, I.F. NRPB-R94 A V A l L A B I L I T Y - H M S O ISBN 0 85951 121 9 E N G L A N

9924 Date February 1980 112760 220000 222000 A Methodology for the Evaluation of the Collective Dose

from Radioactivity in Terrestrial Food Chains. Simmonds, J.R.; Linsley, G.S. NRPB-R97 A V A I L A B I L I T Y - H M S O ISBN 0 85951 124 3 E N G L A N

9926 Date May 1980 112930 220000 222000 795185 A Mathematical Model for Predicting the Probability of

Acute Mortality in a Human Population Exposed to Accidentally Released Airborne Radionuclides. Final Report for Phase 1 of the Project: Early Effects of Inhaled Radionuclides.


NUREG/CR-1261; PNL-3257 A V A I L A B I L I T Y - P A C I F I C NORTHWEST LAB..

R I C H L A N D , WASH. PANL

9927 Date June 1980 112760 220000 222000 Uncertainties in the Calculation of Long-Term Collective

Dose and Health Effects - A Preliminary Assessment. Kocher, D.C.; Leggett, R.W.; Dunning, D.E,Jr.; Ryan,

M.T.; Eckerman, K.F. NUREG/CR-1303 ; O R N L / N U R E G / T M - 3 7 8 A V A I L A B I L I T Y - G P O SALES PROGRAM, DIVI-

S ION OF T E C H N I C A L I N F O R M A T I O N A N D D O C U M E N T CONTROL, U.S. NUCLEAR REGU-LATORY COMMISSION, WASHINGTON, D.C. 20555

O A R N L

Occupational Exposure



NUPE

6400 Date Dec. 1977 223000 719COO Design Measures to Minimize Radiation Exposure of Staff

for a Commercial Nuclear Power Plant. Keenan, F.; Pugh, I.G.; Youell, F.P. CONF-770401, PP.300-308; ATOMKERNENERGIE,


DR., PRINCETON, NJ 08540 SCOTLA

6401 Date Dec. 1977 223000 719C00 Design Worth of Radiation Exposure Reduction. Collins, R.; James, R.A. CONF-770401, PP.309-316 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 C A N A D A

6402 Date Dcc. 1977 223000 719A00 Radiation Exposure in the Operating PWR Plants and Spe-

cific Design Features for Occupational Dose Reduction. Mani, V.; Lingappan, K.G. CONF-770401, PP.317-324 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 U N E C I

6403 Date Dec. 1977 223000 719AOO Experience with Occupational Radiation Exposure in PWRs

Built by Kraftwerk Union. Hccht, G. CONF-770401, PP.325-332; ATOMKERNENERGIE,


D R , PRINCETON, NJ 08540 G E R M A N

5399 Date Dec. 1977 010000 223000 719A00 Radiation Exposure and Protection Problems in Nuclear

Power Plants U.S. Overview. Verna, B.J. CONF-770401, PP.288-299; ATOMKERNENERGIE,

30(4), 282-286(1977)

6404 Date Dec. 1977 223000 719AOO Radiological Experience in Swedish Boiling Water Reactors. Elkert, J. CONF-770401, PP.333-341 A V A I L A B I L I T Y r S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 SWEDEN

127

6405 Date Dec. 1977 112770 223000 719C00 Measurement and Prediction of Gamma-Ray Sources and

Dose Rates in the Vicinity of the Winfr i th SGHWR. Mil ler, P.C.; Avery, A.F.; Carter, M.D.; Chestnutt, M.M. CONF-770401, PP.342-352 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


Criteria for Uses of Bu i l t - i n Exposure Rate and Airborne Radio-activity Monitoring Systems in Nuclear Power Plants.

Todd, T.E. j, CONF-770401, PP.425-433 'if A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE 1

DR., PRINCETON, NJ 08540 TV A

6406 Date Dec. 1977 223000 719A00 Radiation Safety of Nuclear Power Plants with Large Chan-

nel-Type Reactors. Egorov, Yu.A.; Polushkin, K.K.; Sklyarov, V.P.; Cerkaskov,

Yu.M. CONF-770401, PP.353-363 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 RUSSIA

6414 Date Dec. 1977 223000 719AOO Digital Radiation Monitoring System Employing Distrib-

uted Microprocessors. Warman, E.A.; Ingeneri, S.M.; Newman, B.M.; Sowdon,

T.L. CONF-770401, PP.434-441 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 STONE

6409. .'.' Date Dec. 1977 112760 719A00 223000 EPRI Programs in Power Reactor Radiation Control. Shaw, R.A.; Uhl, D.L. CONF-770401, PP.392-400 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 EPRI

6415 Date Dec. 1977 010000 223000 RSIC After 14 Years--Where Do We Go From Here? Trubey, D.K.; Maskewitz, B.F.; Roussin, R.W. CONF-770401, PP.442-447; ATOMKERNENENER-

GIE, 30(4), 303-304(1977) A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6410 Date Dec. 1977 112120 223000 719C00 The Contribution of Fission Products to Radiation Fields in

a Pressurized Heavy Water Reactor. Neil, B.C.J. CONF-770401, PP.401-408 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6411 Date Dec. 1977 112760 223000 719A00 Analysis of Dose Rates Near the Circuit of a PWR After

Shutdown. Beslu, P.; Frejaville, G.; Lalet, A.; Devillers, C. CONF-770401, PP.409-415 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6413 Date Dec. 1977 223000 719AOO

6457 Date Dec. 1977 223000 " Analysis of External Exposures of the Personnel Operating

the RA Reactor at Vinca. Ninkovic, M.M. CONF-770401, PP.785-794 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 YUGOSL

6477 Date September 1974 223000 719AOO Compilation and Analysis of Data on Occupational Radia-

tion Exposure Experienced at Operating Nuclear Power Plants.

Pelletier, C.A.; Simmons, L.; Barbier, M.; Keller, J.H. NESP REPORT A V A I L A B I L I T Y - A T O M I C I N D U S T R I A L FORUM,

INC., 475 PARK AVENUE SOUTH, N E W YORK, NEW YORK 10016 $7.00

SCA

128

6938 Date April 1978 020000, 222000 223000 Environmental Radiation Protection Standards: An Appre-

ciation. Richings, L.D.G.; Morley, F.; Kelly, G.N. NRPB-R71 A V A I L A B I L I T Y - H M S O E N G L A N

8459 Date October 1978 111210 112760 112930 220000 223000 521130 531000



7042 Date September 1976 010000 111210 112760 223000 210000 521130 522130



8121 Date September 1978 222000 223000 Weldon Spring Dose Calculations. Dickson, H.W.; Hi l l , G.A.; Perdue, P.T. O R N L / T M - 6 2 7 2 A V A I L A B I L I T Y - N T I S S4.50 O A R N L

8264 Date May 1977 010000 223000 Survey of Decontamination and Decommissioning Tech-

niques. Kusler, L.E. A R H - C D - 9 8 4 A V A I L A B I L I T Y - N T I S ATRA

8434 Date November 1978 010000 220000 222000 223000 230000 Radiation Exposure of the UK Population. Taylor, F.E.; Webb, G.A.M. NRPB-R77 A V A I L A B I L I T Y - H M S O E N G L A N

8476 Date January 1979 112720 631000 223000 719A00 An Empirical Formula Predicting Shutdown Dose Rate of

the Recirculation Pipes in Boiling Water Reactors. (Tech. Note)

Uchida, S.; Kitamura, M.; Kukuchi, M.; Yusa, H.; Ohsumi, K.; Matsushima, Y.

NUCL. SCL ENG., 69(1), 78-85 JAPAN




8567 Date 1977 111210 223000 521130 522130 717000 795217 795254

793000 810000 Structure Activation in an Experimental Power Reactor. Smith, R.D.; Parish, T.A. CONF-771029,VOL.11, PP.1718-1722 A V A I L A B I L I T Y - I E E E SERVICE CENTER, SINGLE


U - T X


a Portable Smelter and to the Surrounding Population. Randolph, M.L.; Watson, A.P.; O'Donnell, F.R. O R N L / T M - 6 4 4 2 A V A I L A B I L I T Y - NTIS O A R N L

8649 Date October 1978 220000 223000 423135 423250 Radiation Dose to Construction Workers at Operating

Nuclear Power Plant Sites. Final Report, Sept. 1975 -Sept. 1978.

Endres, G.W.R.; Shipler, D.B. NUREG/CR-0426; PNL-2773 AVA ILAB IL ITY -DEP. , NTIS PANL

129

Date November - December 1978

Exposure at Power Reactors,

8692. 223000 Occupational Radiation

Light-Water-Cooled Nuclear 1969--1976.

Johnson, L.A. NUCL. SAFETY, 19(6), 760-765 NURC

8757 Date March 1979 111700 112940 223000 230000 Radiological Implications of Plutonium Recycle and the Use






NUREG/CR-0134; O R N L / N U R E G / T M - 2 1 5 AVA ILAB IL ITY -DEP. , NTIS O A R N L

8791 Date February 1979 010000 111110 223000 719A00 721100 722100 Radiation Streaming in Power Reactors. Lahti, G.P.; Lee, R.R.; Courtney, J.C. (Eds.) ORNL/RSIC-43 ; ANS/SD-79 /16 A V A I L A B I L I T Y - N T I S $9.25 ORANL

8792 Date February 1979 010000 111110 223000 32A000 521110 522110 610000

719A00 722100 853100 861000 Neutron Flux Determination in the Reactor Cavities of

LWRs. Rahn, F.; Til l, H. ORNL/RSIC-43,PP. 1 -21; ANS/SD-79/16,PP. 1-21 A V A I L A B I L I T Y - N T I S EPRI

ORNL/RSIC-43,PP.22-27; ANS/SD-79/16,PP.22-27

A V A I LABI L ITY - NTIS SCA

8794 Date February 1979 111110 223000 32A000 329000 719A00 721100 722100

795276 810000 Applications of Monte Carlo and Discrete Ordinates Tech-

niques to PWR Cavity Shield Design. Cavanaugh, G.P. ORNL/RSIC -43,PP.28 -42;

ANS/SD-79/16,PP.28-42 AVA ILAB IL ITY - NTIS COE

8795 Date February 1979 111110 223000 32AOOO 721100 722100 795198 719A00 Reactor Cavity Radiation Streaming. Cardito, J.M.; Eastman, E.A.B.; Allen, P.R.; Wainio, K.M. ORNL/RSIC-43,PP.43-53;

ANS/SD - 79/16,PP.43 - 53 A V A I L A B I L I T Y - N T I S STONE

8796 Date February 1979 111110 223000 32A000 521130 522130 551110 552210

721100 722100 719A00 795254 795203 795276 810000 Methodology for the Analysis and Design of a PWR Reactor

Cavity Shield System. Celnik, J. ORNL/RSIC-43,PP.54-67;

ANS/SD -79/16,PP.54 - 67 A V A I L A B I L I T Y - N T I S BURNS

8798 Date February 1979 111110 223000 329000 721100 721200 722100 620000

719A00 422110 ° Reactor Cavity Streaming--The Problem and Engineer-

ing Solutions. Iotti, R.C.; Yang, T.L. ORNL/RSIC-43,PP.76-109;

ANS/SD -79/16,PP. 76 -109 A V A I L A B I L I T Y - N T I S EBASCO

,*8793 Date February 1979 111110 32A000 329000 223000 719AOO 721100 722100

795276 795203 793000 Analysis of Reactor Cavity Streaming: Some Practical Con-

siderations. Simmons, G.L.

8799 Date February 1979 111110 223000 721200 719A00 Measured Distribution of Neutrons Inside Containment of

a PWR. Butler, H.M.; Ohnesorge, W.F.; Auxier, J.A. ORNL/RSIC-43,PP.110-113;

ANS/SD-79/16, PP.110-113

130


8821 Date 1978 112930 223000 719A00 810000 An Approach of the Skode Works to the Forecasting and


Hep, J.; Valenta, V.; Veverka, O. ZJE-199 A V A I L A B I L I T Y - S K O D A WORKS, NUCLEAR

POWER CONSTRUCTION DEPARTMENT, INFORMATION CENTRE, PLZEN - CZECHO-SLOVAKIA

CZECHO

Barton, T.P.; Easterly, C.E. ORNL /TM-6756 A V A I L A B I L I T Y - N T I S OARNL


Nuclear Data Aspects. " Kusters, H.; et al. KFK-2833 AVAILAB IL ITY-KERNFORSCHUNGSZENTRUM

KARLSRUHE, GMBH, KARLSRUHE (F.R. GER-M A N Y )

GERMAN

892 7 Date June 1979 223000 719A00 Occupational Radiation Exposure at French Power Plants:

Measurement and Prediction. Beslu, P.; Frejaville, G.; Jeanson, P. NUCL. TECHNOLOGY, 44(1), 84-90 FRANCE

892 8 Date June 1979 223000 Quantifying Plant Availability, ALARA, and Occupational

Radiation Exposure Relationships. Garrett, P.M. NUCL. TECHNOLOGY, 44(1), 91-96 ATIF

8929 Date June 1979 112720 223000 719A00 Getting at the Source: Reducing Radiation Fields. Shaw, R.A. NUCL. TECHNOLOGY, 44(1), 97-103 EPRI

8973 Date Apri l 1979 112710 223000 222000 719A00 Gamma Dose Measurements at Zion and Fort Calhoun Sta-

tions. c Dyer, N.C.; Bunting, R.L.; Nicschmidt, E.B.; Croney, S.T.;

Kynaston, R.L.; Mclsaac, C.V.; Underwood, D.R. NUREG/CR-0755 A V A I L A B I L I T Y - N T I S $7.25 IDNEL


Reactors.

131 <> J ' r. 1 C O \ JI Q


Nuclear Power Plant Sites. Vol.2. Appendices A - F. Final Report, Sept. 1975-Sept. 1978.

Endres, G.W.R.; Shipler, D.B. NUREG/CR-0426, VOL.2; PNL-2773, VOL.2 A V A I L A B I L I T Y - N T I S $9.00 PANL

9642 Date February 1979 010000 220000 222000 223000 Nuclear Risks. Newcombe, H.B. AECL-6477 n AVA ILAB IL ITY-DEP. , NTIS/ (U.S. SALES ONLY) ,

PC A03/MF A01 ' CANADA

o

Radioactive Waste Management


6309 Date June 1977 010000 112600 112710 230000 Regulation of Naturally Occurring and Accelera-



NUREG-0301 A V A I L A B I L I T Y - N T I S NURC


Aspects of Disposal of High-Level Waste in Geologic Formations.

Hil l, M.D.; Grimwood, P.D. NRPD-R69 A V A I L A B I L I T Y - H M S O ENGLAN

6982 Date March 1978 222000 230000 795304 A Radiological Assessment of Reprocessing Advanced Liq-

uid-Metal Fast Breeder Reactor Fuels. Til l, J.E.; Bomar, E.S.; Morse, L.E.; Tennery, V.J. NUCL. TECHNOLOGY, 37(3), 328-339 OARNL


870006 810000 ^ Neutronic Performance of Graphite/I-usion Reactor Blan-

kets Containing Sr-90 and 1-129. Parish, T.A.; Davidson, J.W.; Draper, E.L.,Jr. CONF-760935-P3, PP. 873-882 A V A I L A B I L I T Y - N T I S U - T X

8033 Date August 1978 111110 230000 325000 551110 713000 887000 793000

794000 ^ Preliminary Neutronic Study of Actinide Transmutation in

a Fast Reactor. Williams, M.L.; McAdoo, J.W.; Flanagan, G.F. ORNL /TM-6309 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

BAMI

8272 Date August 1978 010000 112120 230000 870092 870094 Needs and Accuracy Requirements for FPND in the

Out -o f -P i le Fuel Cycle. McKay, H.A.C. IAEA-213, PP.91-104 A V A I L A B I L I T Y - I A E A , V IENNA ( M F O N L Y ) ENGLAN

8273 Date August 1978 010000 112120 230000 870092 870094 A Review of FPND Requirements for Investigation of Irra-

diated Nuclear Fuel: Burnup Measurements, Neutron , Dosimetry, Nuclear Safeguards. Maeck, W.J. fAEA-213, PP.105-108 A V A I L A B I L I T Y - I A E A , V IENNA ( M F O N L Y ) ALCC

>!

8434 Date November 1978 010000 220000 222000 223000 230000 Radiation Exposure of the UK Population. Taylor, F.E.; Webb, G.A.M. NRPB-R77 A V A I L A B I L I T Y - H M S O ENGLAN

8481 .'- Date January 1979 230000 793000 794000 717000 Preliminary Design and Neutronic Analysis of a Laser

Fusion Driven Actinide Waste Burning Hybrid Reactor. Berwald, D.H.; Duderstadt, J.J. NUCL. TECHNOLOGY, 42(1), 34-50 U - M I

8036 Date June 1978 111210 230000 717000 810000 Fusion Fuel Cycle Solid Radioactive Wastes. Gore, B.F.; Kaser, J.D.; Kabele, T.J. PNL-2719 A V A I L A B I L I T Y - N T I S BANW

8216 Date June 1978 112120 230000 853100 A Review of Radioactive Waste Immobilization in Concrete. Lokken, R.O. PNL-2654 A V A I L A B I L I T Y - B A T T E L L E PACIFIC NORTH-

WEST LAB.

8531 Date December 1978 230000 Radiological Safety Assessment for a Low-Level Radioac-

tive Solid Waste Storage Facility: Preliminary Risk Evaluation by Reliability Techniques.

Morisawa, S.; Inoue, Y.; Wadachi, Y.; Kato, K. HEALTH PHYS., 35(6), 817-834 JAPAN

& 8555 Date February 1979

230000 717000 A Neutronic Assessment of Strontium -90 Transmutation

in Fusion Reactors. Parish, T.A. NUCL. TECHNOLOGY, 42(2), 180-194

132

o U - T X

8691 Date March 1979 111210 230000 329000 717000 887000 Inertial Confinement Fusion and Long-Term Nuclear

Waste Management. (Tech. Note) Meldner, H. NUCL. SCL ENG., 69(3), PP.438-441 L A L L

8757 Date March 1979 U 1700 112940 223000 230000 Radiological Implications of Plutonium Recycle and the Use



9005 . . Date 1979 112120 222000 230000 Generic Methodology for Assessment of Radiation Doses

from Groundwater Migration of Radionuclides in LWR Wastes in Shallow Land Burial Trenches.

Aikens, A.E.,Jr.; et al. A IF /NESP-013 A V A I L A B I L I T Y - D A M E S A N D MOORE, BETHES-

DA, M A R Y L A N D AT IF

9015 Date Apri l 1979 111110 230000 887000 Transmutation of Waste Actinides in Light Water Reactors. Gorrell, T.C. DP -1518 A V A I L A B I L I T Y - D U PONT DE NEMOURS (E.I.),

A N D CO., A IKEN, S.C., S A V A N N A H RIVER LAB-ORATORY

DUPONT

9083 Date 1978 111210 230000 717000 Effects of Waste Management on the Impact of Fusion

Power. Botts, T.; Powell, J. BNL-24566; CONF-780508,VOL.2,PP.903-909 A V A I L A B I L I T Y - N T I S BROOKH


Nuclear Data Aspects.

Kusters, H.; et al. KFK-2833 A V A I L A B I L I T Y - K E R N F O R S C H U N G S Z E N T R U M

KARLSRUHE, GMBH, KARLSRUHE (F.R. GER-M A N Y )

GERMAN

9558 Date February 1980 112120 230000 Radionuclide Transport Through Heterogeneous Media. Hadermann, J. NUCL. TECHNOLOGY, 47(2), 312-323 SWITZE

9559 Date February 1980 230000 Reduction in the Toxicity of Fission Product Wastes

Through Transmutation with Deuterium-Trit ium Fusion Neutrons.

Parish, T.A.; Davidson, J.W. NUCL. TECHNOLOGY, 47(2), 324-342 U - T X ^

9613 Date August 1979 112760 230000 GETOUT - A Computer Program for Predicting Radionu-

clide Decay Chain Transport Through Geologic Media. DeMier, W.JA; Cloninger, M.O.; Burkholder, H.C.; Liddell,

P.J. PNL-2970 A V A I L A B I L I T Y - B A T T E L L E - P A C I F I C NORTH-

WEST LAB., R ICHLAND, WA PANL

9617 Date March 1978 , 010000 230000 Determination of a Radioactive Waste Classification Sys-

tem. Cohen, J.J.; King, W.C. UCRL-52535 A V A I L A B I L I T Y - C A L I F O R N I A UNIV., LIVER-

MORE, LAWRENCE LIVERMORE LAB. L A L L

9639 Date March 1980 112120 230000 Boundary Conditions for the Geospheric Transport Equa-

tion. (Tech. Note) Zurkinden, A. NUCL. TECHNOLOGY, 47(3), 494-495 SWITZE

133



Camplin, W.C.; Grimwood, P.D.; White, I.F. ^ . NRPB-R94 — A V A I L A B I L I T Y - H M S O ISBN 0 85951 9 ENGLAN

9886 Date June 1980 112120 230000 0

A Model for the Transport of Radionuclides and Their Decay Products Through Geologic Media.

Burkholder, H.C.; Rosinger, E.L.J. NUCL. TECHNOLOGY, 49(1), 150-158 B A M I

10080 Date August 1980 112760 230000 532000 851000 i| Expected Environments in High-Level Nuclear Waste and

Spent Fuel Repositories in Salt. \ Claiborne, H.C.; Rickertsen, L.D.; Graham, R.F. ORNL /TM-7201 A V A I L A B I L I T Y - N T I S , PC A I 0 / M F A01 O A R N L

General Treatment of Transport Theory


6574 Date March 1978 310000 The C /sub N / Method of Solving the Transport Equation:

Application to Cylindrical Geometry. Kavenoky, A. NUCL. SCI. ENG., 65(3), 514-531 FRANCE

6647 c Date April 1978 310000 A Semi-Analytic Solution to the Transport Equation in

Spherical Geometry. (Tech. Note) Dubi, A.; Horowitz, Y.S. NUCL. SCI. ENG., 66(1), 118-121 ISRAEL

Cacuci, D.G. ORNL /TM-6378 A V A I L A B I L I T Y - N T I S $10.75 O A R N L

7066 Date January L977 111110 310000 511110 713000 870092 870094 Stochastic Method of Calculations for Fast Systems. Godwal, B.K.; Navalkar, M.P. NBS SPEC. PUB. 461, PP. 97-99 ° A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

WASHINGTON, D.C. 20402 INDIA

7068 Date January 1977 010000 112B00 310000 522110 522210 610000 810000 Backscattering of Gamma Rays. Hyodo, T. NBS SPEC. PUB. 461, PP. 110-118 AVAILAB IL ITY-SUPT. OF DOCUMENTS, GPO,

WASHINGTON, D.C. 20402 JAPAN

7103 Date July 1976 111110 112B00 310000 632200 Applying Methods from Photometry and the Theory of

Radiant Heat Exchange to the Transfer of Ionizing Radiation.

Mironov, V.N. ERDA-TR-125 , PP. 46-53 A V A I L A B I L I T Y - N T I S RUSSIA

8094 Date September 1978 310000 Comment on Pahicle Collision Method in Spherical Geome-

try by Escape Probabilities. (Tech. Note) Milgram, M.S. NUCL. SCI. ENG., 67(3), 339-340 CANADA

8099 Date September 1978 310000 Symmetrized Neutron Transport Equation and the Fast

Fourier Transform Method. (Tech. Note) Sinh, N.Q.; Kisynski, J.; Mika, J. NUCL. SCI. ENG., 67(3), 363-370 POLAND

6701 Date April 1978 111500 310000 324000 511110 Analytical Calculations of Neutron Slowing Down, the

Transport and Transport in the Cons-tant-Cross-Section Problem.

8146 Date October 1978 310000 Two-Media Problems in Two-Group Neutron Transport

Theory. (Tech. Note)

134

Ishiguro, Y.; Garcia, R.D.M. A V A I L A B I L I T Y - I N T E R N A T I O N A L ATOMIC NUCL. SCI. ENG., 68(1), 99-110 ENERGY AGENCY, V I E N N A B R A Z I L IAEA

8550 Date February 1979 310000 The F sub N Method in Neutron-Transport Theory. Part

I: Theory and Applications. Siewert, C.E.; Benoist, P. NUCL. SCI. ENG, 69(2), 156-160 FRANCE

8551 Date February 1979 310000 The F sub N Method in Neutron-Transport Theory. Part

II: Applications and Numerical Results. Grandjean, P.; Siewert, C.E. NUCL. SCI. ENG, 69(2), 161-168 FRANCE

8666 Date February 1979 111110 311000 310000 312000 Sensitivity Theory for Reactor Thermal-Hydraulics Prob-

lems. Oblow, E.M. ORNL/RSIC-42 , PP.251-279 A V A I L A B I L I T Y - N T I S O A R N L „

8754 Date Apri l 1979 020000 310000 Three Basic Neutron-Transport Problems in Spherical

Geometry. (Tech. Note) Siewert, C.E.; Grandjean, P. NUCL. SCI. E N G , 70(1), 96-98 FRANCE

9008 Date June 1979 010000 121100 310000 An Index to the Literature on Microscopic Neutron Data. IAEA C I N D A - 7 9 (1977-1979) A V A I L A B I L I T Y - I N T E R N A T I O N A L ' ATOMIC

ENERGY AGENCY, V IENNA IAEA

^ 9009 Date May 1979 010000 121100 310000 An Index to the Literature on Microscopic Neutron Data.

Vol.1. Z Less than or Equal to 50. IAEA C I N D A - A (1935-1976) VOL.1

9010 Date May 1979 010000 121100 310000 An Index to the Literature on Microscopic Neutron Data.

Vol.2. Z Greater than or Equal to 51. IAEA C I N D A - A (1935-1976) VOL.2 A V A I L A B I L I T Y - I N T E R N A T I O N A L ATOMIC

ENERGY AGENCY, V I E N N A IAEA

9064. Date August 1979 310000 Factorized Kernels and the DKPL Solution to the Third

Form of the Neutron Transport Equation in a Rectangu-lar Parallelepiped.

Bassini, A.; Premuda, F.; Wassef, W.A. NUCL. SCI. E N G , 71(2), 87-99 ITALY

9250 Date October 1979 310000 An Application of the Transmission Probability Method to

the Calculation of Neutron Flux Distributions in Hexag-onal Geometry.

Wasastjerna, F. NUCL. SCI. E N G , 72(1), 9 -18 * F I N L A N

940 1 Date November 1979 310000 321000 Discrete Eigenvalues of the Neutron Transport Equation

with Anisotropic Scattering. Dawn, T . -Y . ; Chen, I . -J . NUCL. SCI. ENG, 72(2), 237-243 CHINA

940 2 Date November 1979 310000 The Derivation of Neutron Generation Time for Reflected

Systems and Its Physical Interpretation. Yamane, Y.; Shinkawa, M.; Nishina, K. NUCL. SCI. E N G , 72(2), 244-255 JAPAN

9732 Date Apri l 1980 310000 540000 Application of the Multigroup Collision Probability Method

to Selengut's Theory of Overlapping Neutron Spectra.

135

Ol Lll

Kamelander, G.; Putz, F. N U C L . SCI. ENG., 74(1), 13-22 A U S T R I

9743 Date 1979 010000 111110 310000 32A000 325000 Modem Coarse-Mesh Methods - A Development of the

•70's. Doming, J.J. CONF-790402 ,VOL. I , P P . 3 - 1 - - 3 - 3 1 A V A I L A B I L I T Y - H C - - A N S V I R G I N I A SECTION,

P.O. " B O X 1260, L Y N C H B U R G , VA . 24505; M F - - N . T I S

U - I L

9749 Date 1979 111110 310000 510000 511110 Time-Dependent Continuous-Energy Benchmark Solu-

tions in Neutron Transport Theory. Ganapol, B.D.; Roybal, J.A.; Peddicord, K.L. ; Henninger,

R.J. CONF-790402,VOL.11, P P . 4 - 7 9 - - 4 - 9 4 A V A I L A B I L I T Y - H C - - A N S V I R G I N I A SECTION,

P.O. BOX 1260, L Y N C H B U R G , VA. 24505; M F — N T I S

U - A Z

6695 Date Apr i l 1978 111110 122310 311000 312000 719A00 795217 870092

870094 Sensitivity and Uncertainty Analysis for Func t iona l of

Time-Dependent Nuclide Density Field. Will iams, M.L. ; Weisbin. C.R. O R N L - 5 3 9 3 ; E N D E - 2 6 3 A V A I L A B I L I T Y - N T I S S6.00 „

O O A R N L

8143 Date October 1978 » 311000 329000 Monte Carlo Aspects of Contributions. Dubi, A.; Gerstl, S.A.W.; Dudziak, D.J. f)

N U C L . SCL ENG., 68(1), 19-30 L O A S L

8233 Date January 1968 111110 122110 311000 325000 Interface Conditions for Few Group Equations wi th

F lux -Ad jo in t Weighted Constants ( L W B R q Develop-ment Program).

Buslik, A.J. W A P D - T M - 7 3 3 A V A I L A B I L I T Y ^ - DEP., NT IS BETTIS

9751 Date 1979 111110 310000 32A000 325000 551110 A Nodal Discrete-Ordinates Method for the Numerical

Solution of the Multidimensional Transport Equation. Wagner, M .R . CONF-790402,VOL.11, P P . 4 - 1 1 7 - - 4 - 1 3 3 A V A I L A B I L I T Y - H C - - A N S V I R G I N I A SECTION,

P.O. BOX 1260, L Y N C H B U R G , VA. 24505; M F - - N T I S

G E R M A N

Method of Solution - Adjoint (includes channel theory)

CATEGORY NUMBER 311000 -

6455 Date Dec. 1977 311000 Spatial Channel T h e o r y - - A Technique for Determining

the Directional Flow of Radiation through Reactor Sys-tems.

Wil l iams, M.L. ; Engle, W.W.,Jr. CONF-770401 , PP.770-776 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 B R O O K S T O N E

DR., P R I N C E T O N , NJ 08540 O A R N L

8666 Date February 1979 i l l 110 311000 310000 312000 Sensitivity Theory for Reactor Thermal-Hydraul ics Prob-

lems. Oblow, E.M. O R N L / R S I C - 4 2 , PP.251-279 A V A I L A B I L I T Y - N T I S O A R N L

9707 Date January 1980 111210 311000 329000 551110870011 Application of Biasing Techniques to the Contributon Monte

Carlo Method. Dubi, A.; Gerstl, S.A.W. L A - 8 2 0 1 - MS A V A I L A B I L I T Y - D E P . , NTIS, PC A 0 3 / M F A01 L O A S L <j

9750 Date 1979 111110 311000 326000 511110 Refinements for Spatial Channel Theory Computations. Abu-Shumays, I .K.; Selva, R.J.; Shure, K. CONF-790402,VOL.11, P P . 4 - 9 5 - - 4 - 1 1 5 A V A I L A B I L I T Y - H C - - A N S V I R G I N I A S E C T I O N ,

P.O. BOX 1260, L Y N C H B U R G , V A . 24505; M F - - N T I S

136

BETTIS

10001 Date August 1980 112BOO 220000 311000 329000 795299 845000 Adjoint M C Techniques and Codes for Organ Dose Calcula-

tions. Koblinger, L. ORNL/RSIC-44 , PP.203-217 A V A I L A B I L I T Y - N T I S , PC A16/MF A01 HUNGAR



Ueki, K. ORNL/RSIC-44 , PP.329-344 A V A I L A B I L I T Y - N T I S , PC A16/MF A01 JAPAN

10015 Date June 1980 111110 311000 32AOOO 329000 511110 842000 870094

870094 795254 795203 Calculation of the Response of Cylindrical Targets to Colli-

mated Beams of Particles Using One-Dimensional Adjoint Transport Techniques.

Dupree, S.A. SAND-80-0432 A V A I L A B I L I T Y - S A N D I A N A T I O N A L LABORATO-

RIES, ALBUQUERQUE, NM, THEORETICAL DIV.

SANDIA

M e t h o d of So lu t i on - P e r t u r b a t i o n T h e o r y a n d S e n s i t i v i t y


6376 Date Dec. 1977 010000 312000 A Survey of Cross-Section Sensitivity Analysis as Applied

to Radiation Shielding. Goldstein, H. CONF-770401, PP.75-90; ATOMKERNENERGIE,



637 7 Date Dec. 1977 312000 A Computational Scheme for Energy Group Boundary

Selection Using Sensitivity Theory. Herrnberger, V. CONF-770401, PP.91-100 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 SWITZE

637 8 Date Dec. 1977 312000 Sensitivity Profiles for Secondary Energy and Angular Dis-

tributions. Gerstl, S.A.W. CONF-770401, PP.101-111 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


637 9 Date Dec. 1977 312000 Three-Dimensional Effects in Sensitivity Studies. Ruf , H. CONF-770401, PP.112-119 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


638 0 Date Dec. 1977 010000 020000 312000 A Review of Progress in the N E A / I A E A Collaborative Pro-

gram of Sensitivity Studies and Shielding Benchmarks. Butler, J. CONF-770401, PP.120-131 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


638 1 Date Dec. 1977 312000 713000 Spatio-Energetic Sensitivity of the Equivalent Thermal

Flux on the Intermediate Heat Exchanger of a Typical Fast Breeder Reactor.

Boioli, A.; Fiorini, L.; Moreau, J.; Suntinger, G. CONF-770401, PP.132-139 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


638 2 Date Dec. 1977 312000 713000 861000 870011 Fast Reactor Shield Sensitivity Studies for

Steel-Sodium-Iron Systems.

137

Oblow, E.M.; Weisbin, C.R. CONF-770401, PP.140-148 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6450 Date Dec. 1977 620000 717000 883000 312000 Optimal I ron-Water Shields for Fusion Reactors. Gilai, D.; Greenspan, E.; Levine, P.; Price, W.G.,Jr. CONF-770401, PP.731-738 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 U - N J

6456 Date Dec. 1977 312000 Sensitivity Analysis for Shielding Data Evaluation by Inter-

active Graphics Computing. Parvez, A.; Becker, M. CONF-770401, PP.777-784 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6576 Date March 1978 312000 531000 717000 794000 795254 Neutron Heating Sensitivity to Cross-Section Variations in

a Controlled Thermonuclear Reactor Blanket. (Tech. Note)

Arcipiani, B.; Palmiotti, G.; Salvatores, M. NUCL. SCI. ENG., 65(3), 540-544 I T A L Y

6627 Date March 1978 122310 312000 521130 719AOO 870092 870013 870001

870008 810000 A Compendium of Energy-Dependent Sensitivity Profiles

for the T R X - 2 Thermal Lattice. Tomlinson, E.T.; Lucius, J.L.; Drischler, J.D. ORNL-5336 ; ENDF-253 A V A I L A B I L I T Y - N T I S S8.00

_ O A R N L rt,

6629 Date March 1978 111110 325000 312000 551110 713000 810000 The Code PERTUBAT for Processing Neutron Diffusion

Theory Neutronics Results for Perturbation Analyses. Vondy, D.R.; Fowler, T.B. ORNL-5376 A V A I L A B I L I T Y - N T I S S6.00 O A R N L

6645 Date Apri l 1978 312000 329000 A Monte Carlo Perturbation Source Method for Reactivity

Calculations. Hoffman, T.J.; Petrie, L.M.; Landers, N.F. NUCL. SCI. ENG., 66(1), 60-66 O A R N L


Calculations. Dekker, J.W.M.; Dragt, J.B.; Janssen, A.J.; Heijboer, R.J.;



NETHER

6695 Date Apri l 1978 111110 122310 311000 312000 719A00 795217 870092

870094 Sensitivity and Uncertainty Analysis for Functional of

Time-Dependent Nuclide Density Field. Williams, M.L.; Weisbin, C.R. ORNL-5393; ENDF-263 A V A I L A B I L I T Y - N T I S $6.00 O A R N L

6801 Date June 1978 312000 Recent Developments in Cross Section Adjustment Proce-

dures. Salvatores, M. CONF-780401, PP.269-283 A V A I L A B I L I T Y - N T I S FRANCE

6878 ' Date July 1978 312000 Higher Order Time-Dependent Generalized Perturbation

Theory. Gandini, A. NUCL. SCI. ENG., 67(1), 91-106 I T A L Y

6901 Date August 1977 000000 111110 312000 Use of Perturbation Theory in the Physics of Nuclear Reac-

tors. Stumbar, E.A.

138

E R D A - T R - 2 9 7 A V A I L A B I L I T Y - D E P . , NTIS RUSSIA

7031 Date September 1976 111210 122310 312000 32AOOO 511110 870003 717000 Neutronic Data Consistency Analysis for Lithium Blanket

Shield Design. Reupke, W.A.; Muir, D.W. CONF-760935-P3, PP. 861-871; L A - U R - 7 6 - 2 0 9 2 A V A I L A B I L I T Y - N T I S U - G A



mental Power Reactor. Simmons, E.L.; Gerstl, S.A.W.; Dudziak, D.J. LA-6942- r f rS A V A I L A B I L I T Y - N T I S $5.00 LOASL

7096 Date October 1976 111110 312000 325000 713000 795217 The Spatial Variation of the Damage Energy and Gas Pro-

duction in the Experimental Volume of a L i (D,N) Neutron Radiation Damage Facility.

Alsmiller, R.G,Jr.; Barish, J. O R N L / T M - 5 5 5 4 A V A I L A B I L I T Y - N T I S O A R N L

8032 Date September 1978 111210 122100 312000 32A000 511110 512210 717000


Rcactor Shielding Experiments. Seki, Y.; Santoro, R.T.; Oblow, E.M.; Lucius, J.L. ORNL-5467 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8098 Date September 1978 312000 Implicit and Explicit Higher Order Perturbation Methods

for Nuclear Reactor Analysis. (Tech. Note) Gandini, A. NUCL. SCI. ENG., 67(3), 347-355 ITALY

8119 Date September 1978 111110 312000 Development of Depletion Perturbation Theory for Coupled

Neutron/Nuclide Fields. Williams, M.L. O R N L / T M - 5 9 5 8 A V A I L A B I L I T Y - N T I S $5.25 O A R N L

8141 Date October 1978 312000 Second-Order Generalized Perturbation Theory for

Source-Driven Systems. Greenspan, E.; Gilai, D.; Oblow, E.M. NUCL. SCI. ENG., 68(1), 1 -9 ISRAEL

7104 Date July 1976 112B00 312000 552110 810000 Using Perturbation Theory for Problems Concerning Scat-

tered Gamma-Radiation, Petrov, E.Ye.; Shemetenko, B.P. E R D A - T R - 1 2 5 , PP. 54-72 A V A I L A B I L I T Y - N T I S RUSSIA


Reactor Benchmarks. Marable, J.H.; Lucius, J.L.; Weisbin, C.R. ORNL-5262; ENDF-234 A V A I L A B I L I T Y - E R D A , TIC, P.O. BOX 62, OAK


8509 Date July 1978 111110 312000 32AOOO 521130 795042 810000 Sensitivity Studies of One-Dimensional Neutronics Calcu-

lations for Prompt Burst Excursion (PBE) Experiments in the Annular Core Pulse Reactor (ACPR).

Varela, D.W.; Williams, D.C. NUREG/CR-0262; SAND78-0I43 A V A I L A B I L I T Y - N T I S SANDIA

8650 Date February 1979 010000 122310 312000 A Review of the Theory and Application of Sensitivity and

Uncertainty Analysis. Proceedings of a Semi-nar-Workshop, Oak Ridge, Tennessee, August 22-24, 1978.


139

O R N L / R S I C - 4 2 A V A I L A B I L I T Y - N T I S $13.00 OARNL

8652 Date February 1979 111110 122310 312000 713000 794000 521130 32AOOO Advances in Fast Reactor Sensitivity and Uncertainty Anal-

ysis. Marable, J.H.; Weisbin, C.R. ORNL/RSIC-42 , PP.25-48 A V A I L A B I L I T Y - N T I S O A R N L

8654 Date February 1979 111110 329000 312000 430000 551110 795203 810000 Sensitivity Analysis Applied to the Calculation of Detec-

tor-Response Kernels. Scott, W.H.,Jr.; McDaniel, P.J.; Renken, J.H.; Wright, S.A. ORNL/RSIC-42 , PP.61-74 A V A I L A B I L I T Y - N T I S SCA

8661 Date February 1979 111110 122310 32AOOO 312000 210000 521130 810000



8662 Date February 1979 111 110 32AOOO 312000 421130 511110 870041 794000

793000 795254 795204 Sensitivity Analysis Applied to an Integral Test of Niobium

Cross Sections. Ingersoll, D.T.; Wehring, B.W. ORNL/RSIC-42 , PP.179-189 A V A I L A B I L I T Y - N T I S O A R N L

8664 Date February 1979 111110 122310 32A000 312000 717000 810000 Uncertainty Analysis for Secondary Energy Distributions. Gerstl, S.A.W. ORNL/RSIC-42 , 219-229 A V A I L A B I L I T Y - N T I S LOASL

8665 Date February 1979 111110 122310 32AOOO 312000 521130 795248 High Order Effects in Cross-Section Sensitivity Analysis. Greenspan, E.; Kami, Y.; Gilai,,D. ORNL/RSIC-42 , PP.231-249' A V A I L A B I L I T Y - N T I S ISRAEL

8666 Date February 1979 111110 311000 310000 312000 Sensitivity Theory for Reactor Thermal-Hydraulics Prob-

lems. Oblow, E.M. v ORNL/RSIC-42 , PP.251-279 A V A I L A B I L I T Y - N T I S OARNL

8670 Date February 1979 111110 329000 312000 430000 713000 795203 Fuel-Motion Unfolding Based on Point Detector

Responses. McDaniel, P.J.; Wright, S.A. ORNL/RSIC-42, PP.319-327 A V A I L A B I L I T Y - N T I S SANDIA

8673 Date February 1979 111110 122310 312000 First and Higher Order Perturbation Techniques and Their

Application in System Analysis and Data Adjustments. Gandini, A. ORNL/RSIC-42, PP.351-361 A V A I L A B I L I T Y - N T I S ITALY

8663 Date February 1979 111210 122310 32A000 312000 521130 551110 717000


Fusion Reactor Design. Wu, T.; Maynard, C.W. ORNL/RSIC-42 , PP.191 -217; U W F D M - 2 9 0 A V A I L A B I L I T Y - N T I S U - W I

8674 Date February 1979 111110 122310 32A000 312000 521130 713000 719A00

795204 795254 861000 810000 The Use of Error Files in Uncertainty Analysis and Data

Adjustment. Chestnutt, M.M.; MCracken, A.K. ORNL/RSIC-42, PP.363-373 A V A I L A B I L I T Y - N T I S ENGLAN

140

8715 Date February 1979 111110 122310 312000 719A00 Sensitivity of Nuclear Fuel Cycle Cost to Uncertainties in

Nuclear Data. Becker, M.; Harris, D.R. EPRI -NP-985 A V A I L A B I L I T Y - R E N S S E L A E R POLYTECHNIC

INSTITUTE, DEPT. OF NUCLEAR ENGINEER-ING, TROY, NEW YORK 12181

U - N Y

8751 Date April 1979 312000 Development of Depletion Perturbation Theory for Coupled

Neutron/Nuclide Fields. Williams, M.L. NUCL. SCI. ENG., 70(1), 20-36 OARNL

8818 Date February 1979 111210 122310 312000 717100 A Separation Method for the Transport Equation and Sensi-

tivity Theory in Fusion-Fission Hybrid Analysis. Youssef, M.Z.; Conn, R.W. UWFDM-289 A V A I L A B I L I T Y - N U C L E A R ENGINEERING

DEPARTMENT, UNIVERSITY OF WISCONSIN, M A D I S O N 53706

U - W I

8895 Date December 1978 010000 111210 122310 312000 717000 Cross-Section Sensitivity and Uncertainty Analysis for

Fusion Reactors (A Review). Dudziak, D.J. L A - U R - 7 9 - 1 6 8 A V A I L A B I L I T Y - L O S ALAMOS SCIENTIFIC LAB.,

UNIVERSITY OF CALIFORNIA, LOS ALAMOS, NEW MEXICO 87544

LOASL

9255 Date October 1979 312000 Inverse Perturbation Theory. (Tech. Note) Ronen, Y. NUCL. SCI. ENG., 72(1), 110-113 ISRAEL

9305 Date July 1979 111110 312000 325000 32AOOO 551110 TP2 - A Computer Program for the Calculation of Reactiv-

ity and Kinetic Parameters by the Two-Dimensional Neutron Transport Perturbation Theory.

Kobayashi, K. KFK-2787 A V A I L A B I L I T Y - K E R N F O R S C H U N G S Z E N T R U M

KARLSRUHE (GERMANY, F.R.), INST. FUER NEUTRONENPHYSIK UND REAKTORTECH-N I K

G E R M A N

9316 Date October 1979 112120 312000 719AOO Sensitivity Theory Applied to a Transient Ther-

mal-Hydraulics Problem. Weber, C.F.; Oblow, E.M. O R N L / T M -6900 A V A I L A B I L I T Y - N T I S O A R N L

9551 Date February 1980 312000 Time-Dependent Generalized Perturbation Theory for

Coupled Neutron-Nuclide Problems. (Tech. Note) Greenspan, E.; Williams, M.L.; Marable, J.H. NUCL. SCI. ENG., 73(2), 210-218 O A R N L

9633 Date March 1980 312000 325000 Homogenized Diffusion Approximations to the Neutron

Transport Equation. Larsen, E.W.; Hughes, R.P. NUCL. SCI. ENG., 73(3), 274-285 LOASL



RESEARCH FOUNDATION ECN, P.O. BOX 1, 1755 ZG PETTEN (NH) , T H E NETHERLANDS

NETHER

9787 Date December 1979 010000 111210 312000 32AOOO 717000 810000 Cross-Section Sensitivity and Uncertainty Analysis for

Fusion Reactors - A Review. (Review Paper No.Bl ) Dudziak, D.J. IAEA-TECDOC-223 , PP.121-138 A V A I L A B I L I T Y - M F ONLY - IN IS MICROFICHE


141

LOASL

9929 Date May 1980 111110 32A000 312000 795320 DOS Perturbation Modules DGRAD/VIP/TPERT. Tomlinson, E.T.; Childs, R.L.; Lillie, R.A. O R N L / C S D / T M -116 A V A I L A B I L I T Y - N T I S O A R N L

9988 Date August 1980 010000 312000 329000 521130 810000 Monte Carlo Perturbation Theory in Neutron Transport

Calculations.' Hall, M.C.G. ORNL /RS IC -44 , PP.47-62 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01

- E N G L A N

9998 Date August 1980 010000 312000 329000 717000 810000 The Recursive Monte Carlo Method for Deep-Penetration

Problems. Goldstein, M.; Greenspan, E. ORNL /RS IC -44 , PP.169-187 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 O A R N L

6448 Date Dec. 1977 32AOOO 795274 795266 Application of the ONETRAN and T I M EX Codes to

Shielding Problems. Hill, T.R. CONF-770401, PP.719-723 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6449 Date Dec. 1977 32A000 795320 The DOT IV Variable Mesh Discrete Ordinates Transport

Code. Rhoades, W.A. CONF-770401, PP.724-730 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6800 > Date June 1978 010000 32A000 325000 \ Computational Procedures for.Multidimensional Core Anal-

ysis. Lathrop, K.D. CONF-780401, PP.93-105 A V A I L A B I L I T Y - NTIS LOASL

M e t h o d of S o l u t i o n - C a r l s o n S„ a n d D i s c r e t e - O r d i n a t e s

C A T E G O R Y N U M B E R 32A000

. 6440 Date Dec. 1977 329000 32A000 532000 719A00 Evaluation of Uncertainties in the Gamma-Ray Heating

Analysis of a PWR. West, J.T.,III CON'F-770401, PP.652-659 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6447 Date Dec. 1977 32A000 Exponential Supplementary Equations for SN Methods: The

Two-Dimensional Case. Barbucci, P.; Di Pasquantonio, F. CONF-770401, PP.711-718 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


7028 Date September 1976 010000 111210 210000 32A000 329000 531000 532000


Reactors. Dudziak, D.J. CONF-760935-P3, PP. 819-832; L A - U R - 7 6 - 2 0 8 6 A V A I L A B I L I T Y - N T I S LOASL



kets Containing Sr-90 and 1-129. Parish, T.A.; Davidson, J.W.; Draper, E.L.,Jr. CONF-760935-P3, PP. 873-882 A V A I L A B I L I T Y - N T I S U - T X


Reactor Benchmarks.

142

Marable, J.H.; Lucius, J.L.; Weisbin, C.R. ORNL-5262; ENDF-234 A V A I L A B I L I T Y - E R D A , TIC, P.O. BOX 62, OAK


8032 Date September 1978 111210 122100 312000 32A000 511110 512210 717000


Reactor Shielding Experiments. Seki, Y.; Santoro, R.T.; Oblow, E.M.; Lucius, J.L. ORNL-5467 A V A I L A B I L I T Y - N T I S $4.50 OARNL :>

8034 Date August 1978 111110 220000 32AOOO 551110 552210 820000 861000


with Experimental Data. Santorc, R.T.; Alsmiller, R.G.,Jr.; Barnes, J.M. ORNL /TM-6401 /R1 A V A I L A B I L I T Y - N T I S $.4.00 OARNL

8190 Date October 1977 111110 111210 32AOOO 521130 717100 810000 795254 Neutronics and Thermal Hydraulics of a Tokamak Hybrid

Blanket. Perry, R.T.; McKinnon, M.A.; Teofilo, V.L.; Aase, D.T. BNWL-SA-6420 ; CONF-771029-221 AVA ILAB IL ITY -DEP. , NTIS BANW

8248 Date November 1978 210000 32A000 717000 795254(03) Sputtering Calculations with Discrete-Ordinates Method. Hoffman, T.J.; Dodds, H.L.,Jr.; Robinson, M.T.; Holmes,

D.K. NUCL. SCL ENG., 68(2), 204-211 O A R N L

8515 Date January 1979 111110 122110 32A000 521130 522130 794000 122210 Sample Problems for the Novice User of the A M P X - I I

System. Ford, W.E.,III; Roussin, R.W.; Petrie, L.M.; Diggs, B.R.;

Comolander, H.E. O R N L / C S D / T M - 7 2 ( A M P X - 7 ) A V A I L A B I L I T Y - N T I S $9.25 O A R N L

8517 Date February 1979 020000 111210 122310 312000 32AOOO 551U0 552U0




ORNL /TM-6588 A V A I L A B I L I T Y - N T I S $4.50 OARNL

8518 Date January 1979 111210 122310 32A000 521130 551110 717000 793000


Cross-Section , Sensitivity Calculations for a Fusion Reactor Shielding Experiment.

Seki, Y.; Santoro, R.T.; Oblow, E.M.; Lucius, J.L. ORNL /TM-6667 " A V A I L A B I L I T Y - N T I S $4.00 O A R N L

8563 Date 1977 111210 32A000 521130 717000 795254 810000 A Practical Blanket Design for'a Toroidal Fusion Reactor. Bettis, E.S.; Barnes, J.M.; Huxford, T.J.; Liu, K.C.; Santoro,

R.T.; Watts, H.L. CONF-771029,VOL.11, PP.1453-1458 A V A I L A B I L I T Y - I E E E SERVICE CENTER, SINGLE


OARNL

8496 Date January 1978 111210 329000 32A000 551110 552110 793000 717000

810000 GAC - A N L TNS Scoping Studies. Volume V. Support

Engineering, Trit ium and Neutronics. Project Staff - Argonne National Lab. GA-A14614,VOL.V; ANL/FPP/77-6 ,VOL.V A V A I L A B I L I T Y - N T I S $8.00 GEAC

8652 Date February 1979 111110 122310 312000 713000 794000 521130 32AOOO Advances in Fast Reactor Sensitivity and Uncertainty Anal

ysis. Marable, J.H.; Weisbin, C.R. ORNL/RSIC-42 , PP.25-48 A V A I L A B I L I T Y - N T I S OARNL

143

8661 Date February 1979 111110 122310 32A000 312000 210000 521130 810000



8662 Date February 1979 111110 32A000 312000 421130 511110 870041 794000


Cross Sections. Ingersoll, D.T.; Wehring, B.W. ORNL/RSIC-42 , PP.179-189 A V A I L A B I L I T Y - N T I S O A R N L



Fusion Reactor Design. Wu, T.; Maynard, C.W. ORNL/RSIC-42 , PP.191 -217; UWFDM-290 A V A I L A B I L I T Y - N T I S U - W I

8664 Date February 1979 111110 122310 32A000 312000 717000 810000 Uncertainty Analysis for Secondary Energy Distributions. Gerstl, S.A.W. ORNL/RSIC-42 , 219-229 A V A I L A B I L I T Y - NTIS LOASL

8665 Date February 1979 111110 122310 32AOOO 312000 521130 795248 High Order Effects in Cross-Section Sensitivity Analysis. Greenspan, E.; Kami, Y.; Gilai, D. ORNL/RSIC-42 , PP.231-249 A V A I L A B I L I T Y - N T I S ISRAEL

" 8795 Date February 1979 111110 223000 32AOOO 721100 722100 795198 719A00 Reactor Cavity Radiation Streaming. Cardito, J.M.; Eastman, E.A.B.; Allen, P.R.; Wainio, K.M. ORNL/RSIC-43,PP.43-53;

ANS/SD -79/16,PP.43 - 53 A V A I L A B I L I T Y - N T I S

STONE

& 8802 Date February 1979

111110 32A000 551110 719A00 710000 721100 810000 A Low Pressure Drop Reactor Cavity Shield System. Klotz, R.J.; Cavanaugh, G.P.; Kassawara, R.P.;

McLaughlin, D.J.; Pilver, A.B. ORNL/RSIC-43,PP. 137-148;

ANS/SD-79/16,PP.137-148 A V A I L A B I L I T Y - N T I S COE

8885 Date March 1979 111500 32A000 329000 551110 552210 853100 861000

795203 793000 The SAI /EPRI Albedo Information Library. Simmons, G.L. EPRI-NP-1017 A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, INC.,

1200 PROSPECT ST., LA JOLLA, CALIFORNIA 92038

SCA

8950 Date May 1978 111210 122310 32A000 521130 522130 620000 717000 A Minimum-Thickness Blanket/Shield with Optimum

Tritium Breeding and Shielding Effectiveness. Gerstl, S.A.W. CONF-780508,VOL.1, PP.269-278 AVAILABIL ITY-DEP. , NTIS LOASL

8954 Date May 1978 111210 32A000 795493 TRIDENT-CTR: A Two-Dimensional Transport Code

for CTR Applications. Seed, T.J. CONF-780508,VOL.1, PP.394-401 AVAILABIL ITY-DEP. , NTIS LOASL

8998 Date July 1979 32A000 512110 861000 A Finite Moments Algorithm for Particle Transport Prob-

lems. Vaidyanathan, R. NUCL. SCI. ENG., 71(1), 46-54 INDIA

9066 Date August 1979 32AOOO

144

Computational Efficiency of Numerical Methods for the Multigroup, Discrete-Ordinates Neutron Transport Equations: The Slab Geometry Case.

Alcouffe, R.E.; Larsen, E.W.; Miller, W.F.,Jr.; Wienke, B.R.

NUCL. SCI. ENG., 71(2), 111-127 LOASL

9093 Date 1979 122110 32A000 794000 870079 Range Calculations Using Multigroup Transport Methods. Hoffman, T.J.; Robinson, M.T.; Dodds, H.L.,Jr. CONF-790125-57 AVA ILAB IL ITY-DEP. , NTIS OARNL


810000 Discrete Transfer Cross Section Expansion for Time Depen-

dent Neutron Transport. Beranek, F.; et al. UWFDM-304 A V A I L A B I L I T Y - N U C L E A R ENGINEERING

DEPARTMENT, UNIVERSITY OF WISCONSIN, MADISON, W1

U - W I

9144 Date September 1979 32A000 An Improvement of the PALLAS Discrete-Ordinates

Transport Code. (Tcch. Note) 0

Sasamoto, N.; Takeuchi, K. NUCL. SCI. ENG., 71(3), 330-342 JAPAN

9278 Date, 1979 32A000 The Nation's Nuclear Waste - Proposals for Organization

and Siting. E M D - 7 9 - 7 7 A V A I L A B I L I T Y - G A O DISTRIBUTION SECTIONS,

WASHINGTON, D.C. LOASL

A V A I LABI L IT Y - KERN FORSCHUN GSZENTRUM KARLSRUHE (GERMANY, F.R.), INST. FUER NEUTRONENPHYSIK U N D REAKTORTECH-N I K

GERMAN

9310 Date August 1979 111210 32A000 521130 522130 717000 810000 The Reversed-Field Pinch Reactor (RFPR) Concept. Hagenson, R.L.; Krakowski, R.A.; Cort, G.E. L A - 7 9 7 3 - M S A V A I L A B I L I T Y - N T I S LOASL

9380 Date October 1979 111110 32A000 551110 795320 The Stability of the Mesh-Cornered Synthetic Method of

Diffusion Acceleration of the D O T - I V Transport Code.

Aull, J. ORNL /TM-7097 A V A I L A B I L I T Y - N T I S OARNL

9743 Date 1979 010000 111110 310000 32AOOO 325000 Modern Coarse-Mesh Methods - A Development of the

'70's. Doming, J.J. CONF-790402,VOL.1, P P . 3 - 1 - - 3 - 3 1 A V A I L A B I L I T Y - H C — A N S V IRGINIA SECTION,


U - I L

9744 Date 1979 111110 32A000 551110 795222 795320 A Timing Comparison of Two-Dimensional Dis-

crete-Ordinates Codes for Criticality Calculations. Miller, W.F.,Jr.; Alcouffe, R.E.; Bosler, G.E.; Brinkley,

F.W.,Jr.; O'Dell, R.D. CONF-790402,VOL.11, P P . 4 - 1 - - 4 - 1 8 A V A I L A B I L I T Y - H C - - A N S V IRGINIA SECTION,


LOASL

9305 Date July 1979 H I 110 312000 325000 32A000 551110 TP2 - A Computer Program for the Calculation of Reactiv-


Kobayashi, K. KFK-2787

9745 Date 1979 111110 32AOOO 551110 795222 795320 A Comparison of Codes for Deep Penetration Transport

Studies. Rhoades, W.A.; Tomlinson, E.T. CONF-790402,VOL.11, PP.4-19- - 4 - 3 3

145

A V A I L A B I L I T Y - H C - - A N S V IRGIN IA SECTION, P.O. BOX 1260, LYNCHBURG, VA. 24505; M F - - N T I S

O A R N L

9746 Date 1979 111110 32A000 551110 713000 795230 Continuous Four-Point Triangular Mesh Difference

Schemes for the Multigroup Neutron Transport Equa-tion.

Kufner, K.; delMarmol, B.; Minsart, G. CONF-790402,VOL.11, PP.4-35- - 4 - 4 7 A V A I L A B I L I T Y - H C - - A N S V IRGIN IA SECTION,


GERMAN

Dudziak, D.J. IAEA-TECDOC-223 , PP.121 -138 A V A I L A B I L I T Y - M F ONLY - IN IS MICROFICHE


LOASL

9862 Date Apri l 1978 ' 121200 122210 32A000 810000 Definition of Two Band Parameters for Use in Photon Trans-

port Calculations. Cullen, D.E. UCID-17774 A V A I L A B I L I T Y - N T I S , PC A 0 2 / M F A01 L A L L

974 7 Date 1979 111110 32AOOO 551110 795293 A Three-Dimensional Hexagonal-Z Difference Scheme

for Discrete-Ordinates Codes. Walters, W.F.; O'Dell, R.D. CONF-790402,VOL.11, P P . 4 - 4 9 - - 4 - 6 3 A V A I L A B I L I T Y - H C - - A N S VIRGINIA SECTION,


LOASL

974 8 Date 1979 111110 32A000 551110 Convergence of Two-Dimensional Discrete-Ordinates for

Regions with Imbedded Vacuums. Nelson, P. CONF-790402,VOL.11, P P . 4 - 6 5 - - 4 - 7 8 A V A I L A B I L I T Y - H C - - A N S V IRGIN IA SECTION,


U - T X

9751 Date 1979 111110 310000 32A000 325000 551110 A Nodal Discrete-Ordinates Method for the Numerical

Solution of the Multidimensional Transport Equation. Wagner, M.R. CONF-790402,VOL.11, PP .4 -117 - -4 -133 A V A I L A B I L I T Y - H C - - A N S V IRGINIA SECTION,


GERMAN

9787 Date December 1979 010000 111210 312000 32A000 717000 810000 Cross-Section Sensitivity and Uncertainty Analysis for

Fusion Reactors - A Review. (Review Paper No.Bl)

9929 Date May 1980 111110 32A000 312000 795320 DOS Perturbation Modules DGRAD/VIP/TPERT. Tomlinson, E.T.; Childs, R.L.; Lillie, R.A. O R N L / C S D / T M -116 A V A I L A B I L I T Y - N T I S OARNL

10015 Date June 1980 111110 311000 32AOOO 329000 511110 842000 870094



Dupree, S.A. SAND-80-0432 A V A I L A B I L I T Y - S A N D I A N A T I O N A L LABORATO-

RIES, ALBUQUERQUE, N M , THEORETICAL DIV.

SANDIA u

M e t h o d of So lu t ion - C a r l s o n S„ a n d D i s c r e t e - O r d i n a t e s - P l a s m a A p p l i c a t i o n s

CATEGORY NUMBER 32A100

6242 Date 1977 121300 122115 32A100 514110 717000 Neutral Hydrogen Transport in a Two-Dimensional Toroi-

dal Plasma Using Multigroup, Discrete Ordinates Methodology.

Wienke, B.R.; Miller, W.R.,Jr.; Seed, T.J.; Rood, P.L. L A - U R - 7 7 - 8 3 9 A V A I L A B I L I T Y - T H E O R E T I C A L DIV., UNIV . OF

CALIF., LOS ALAMOS SCIENTIFIC LABORATO-RY I OS ALAMOS, NEW MEXICO 87545

146

LOASL Method of Solution - Variational

6765 Date September 1977 32A100 717000 795254 Multigroup Calculations of Low Energy Neutral Transport

in Tokamak Plasmas. Gilligan, J.G.; Gralnick, S.L.; Price, W.G.,Jr.; Kammash, T. PPPL-1384 A V A I L A B I L I T Y - N T I S U - N J

8230 Date September 1978 32A100 SPUDNIT: A Transport Code for Neutral Atoms in Plas-

mas. Audenaerde, K.; Emmert, G.A.; Gordinier, M. UWFDM-259 A V A l L A B I L I T Y - F U S I O N RESEARCH PROGRAM,


U - W I

8755. Date March 1979 32A100 f, Hydrogen Transport in a Toroidal Plasma Using Multigroup

Discrete-Ordinates Methodology. Wienke, B.R.; Miller, W.F.,Jr.; Seed, T.J. NUCL. TECHNOLOGY, 42(3), 272-288 LOASL

CATEGORY N U M B E R 32B000

9821 , Date May 1980 32BOOO 717000 Application of Generalized Variational Principles to Con-

trolled Thermonuclear Reactor Neutronics Analysis. (Tech. Note)

Cheng, E.T. NUCL.SCI . ENG., 774(2), 147-153 GEAC

ft

Method of Solution - Finite Element

CATEGORY NUMBER 32C000

6933 Date March 1978 32C000 632200 INGEN: A General-Purpose Mesh Generator for Finite

Element Codes. Cook, W.A. L A - 7 1 3 5 - M S A V A I L A B I L I T Y - N T I S LOASL

9527 Date September 1978 32A100 794000 A Method of Generating Multigroup Transfer Matrices

Using an Analytic Angular Integration Free of Trunca-tion Error.

Bucholz, J.A. NUREG/CR-0295 A V A I L A B I L I T Y - N T I S $4.50 OARNL

8777 Date February 1978 111110 32C000 The Finite Element Method for Neutron Transport. Part IV.

A Variational Principle Giving an Upper Bound for the Lowest Eigenvalue of the Boltzmann Equation.

Ackroyd, R.T. N D - R - 9 3 ( R ) A V A I L A B I L I T Y - U K A E A , RISLEY NUCLEAR

POWER DEVELOPMENT ESTABLISHMENT, RISLEY, WARRINGTON, UK

ENGLAN

10014. . . . Date July 1980 32A100 Acceleration of the Inner Iteration of the D O T - I V Trans-

port Code Using a New Source Correction Scheme. Aull, J.E. O R N L / T M - 7 4 0 4 A V A I L A B I L I T Y - N T I S , PC A05 /MF A01 OARNL

8931 Date 1977 32COOO T H E FINITE ELEMENT METHOD. (3rd Expanded and

Rev. Ed.) Zienkiewicz, O.C. BOOK A V A I L A B I L I T Y - L O N D O N , NEW YORK,

M C G R A W - H I L L ENGLAN

147

9106 Date May 1979 111210 32C000 717000 795293 T R I D E N T - C T R User's Manual. Seed, T.J. L A - 7 8 3 5 - M A V A I L A B I L I T Y - NTIS LOASL

M e t h o d of S o l u t i o n - R e s p o n s e - M a t r i x o r T r a n s f e r M a t r i x

CATEGORY NUMBER 32D000

9011 Date 1979 111110 32D000 551110 Mathematical Behavior and Computation of Transmission

Probabilities for Annular Regions. Hwang, R.N.; Toppel, B.J. CONF-790402-21 A V A I L A B I L I T Y - D E P . , NTIS ARGONN

9726 Date January 19,80 32DOOO 540000 Some Results of Transfer Matrix Calculations for Thermal

Neutrons. Kim, S.-Y. ; Aronson, R. NUCL. SCI. ENG., 73(1), 56-65 U - N Y

M e t h o d of S o l u t i o n - O n e - V e l o c i t y


7064 Date January 1977 111500 321000 Neutron Transport Problems in Spherical Geometry. Sahni, D.C. NBS SPEC. PUB. 461, PP. 87-90 A V A I LABI L IT Y - SUPT. OF DOCUMENTS, GPO,


7101 Date July 1976 111500 321000 323000 511110 861000 870006 Asymptotic Characteristics of the Distribution of Fast Neu-

tron fluxes in Heterogeneous Shielding. Germogenova, T.A.; Konovalov, N.V.; Suvorov, A.P. ERDA-TR-125 , PP. 25-34 A V A I L A B I L I T Y - N T I S RUSSIA

7102 Date July 1976 111500 321000 511110 551110 820000 861000 Spatial and Angular Distributions of Fast Neutrons in Coni-

cal Shielding. Bass, L.P.; Germogenova, T.A.; Dubinin, A.A.; Khmylev,

A.N. ERDA-TR-125 , PP. 35-45 A V A I L A B I L I T Y - N T I S RUSSIA

Method of Solution - Spinney (Removal-Diffusion)

CATEGORY NUMBER 32F000

6446 Date Dec. 1977 32FOOO 010000 The Use of Removal Diffusion Theory for Calculating the

Effectiveness of Neutron and Gamma-Ray Shields for Nuclear Reactors and Chemical Plants.

Richardson, B.L.; Burstall, R.F. CONF-770401, PP.703-710 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


8144 Date October 1978 321000 Some Fundamental Relations Between Classical Problems

© of Transport Theory. Benoist, P. NUCL. SCL ENG., 68(1), 31-37 FRANCE

8393 Date December 1978 321000 The One-Group Neutron Transport Equation and Angular

Flux Separability. Shalitin, D.; Wagschal, J.J.; Yeivin, Y. NUCL. SCL ENG., 68(3), 243-248 ISRAEL

8473 Date January 1979 321000 325000 717000 Angular Effects in Toroidal Diffusion. 6

c 148 o

Pomraning, G.C. NUCL. SCI. ENG., 69(1), 6 -13 U - C A

8479 Date January 1979 321000 Eigenvalue Spectrum of Multiplying Slabs and Spheres for

Monoenergetic Neutrons with Anisotropic Scattering. (Tech. Note)

Dahl, E.B.; Sjostrand, N.G. NUCL. SCI. ENG., 69(1), 114-125 SWEDEN

9401 Date November 1979 310000 321000 Discrete Eigenvalues of the Neutron Transport Equation

with Anisotropic Scattering. Dawn, T . - Y . ; Chen, I . - J . NUCL. SCI. ENG., 72(2), 237-243 C H I N A

9895 Date June 1980 321000 Time-Independent One-Speed Neutron Transport Equa-

tion with Anisotropic Scattering in Absorbing Media. Hengelbroek, R.J. A N L - 8 0 - 6 0 A V A I L A B I L I T Y - N T I S , PC A04 /MF A01 ARGONN

M e t h o d of S o l u t i o n - S t r a i g h t - A h e a d -A p p r o x i m a t i o n


7072 Date January 1977 112720 322000 722100 Gamma Ray Streaming Through Annular Cylindrical Duct. Murthy, K.P.N.; Vaidyanathan, R.; Singh, R.S. NBS SPEC. PUB. 461, PP. 132-135 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

WASHINGTON, D.C. 20402 I N D I A

7099 Date July 1976 112B00 111500 322000 330000 521130 522130 820000 Using Korobov's Method in Radiation Shielding Calcula-

tions. Gogotova, L.G.; Niki t in, A.V. E R D A - T R - 1 2 5 , PP. 11-16 A V A I L A B I L I T Y - N T I S . RUSSIA

9900 Date 1978 111110 112120 322000 712000 795142 810000 Calculation of Gamma-Rays and Fast Neutrons Fluxes

with the Program MERCURE-4 . -Baur, A.; Dupont, C.; Totth, B. CEA-CONF-4493 ; CONF-7811158-1 A V A I L A B I L I T Y - N T I S (U.S. SALES ONLY) , PC

A03 /MF A01 FRANCE

M e t h o d of S o l u t i o n - A s y m p t o t i c


6854 Date February 1977 111110 323000 540000 719A00 Neutron Spectrum Calculating Module of the Program

BETTY. Gado, J. K F K l - 7 7 - 1 4 A V A I L A B I L I T Y - D E P . , NTIS (U.S. SALES O N L Y ) GERMAN


tron fluxes in Heterogeneous Shielding. Germogenova, T.A.; Konovalov, N.V.; Suvorov, A.P. ERDA-TR-125 , PP. 25-34 A V A I L A B I L I T Y - N T I S RUSSIA

M e t h o d of S o l u t i o n - F e r m i - A g e o


6701 Date Apri l 1978 111500 310000 324000 511110 Analytical Calculations of Neutron Slowing Down the

Transport and Transport - in the Cons-tant-Cross-Section Problem.

Cacuci, D.G. ORNL /TM-6378 A V A I L A B I L I T Y - N T I S $10.75 O A R N L

6803 Date 1975 111110 324000 32A000 511110 861000 870092 Multigroup Formalism for Evaluation of Continuous Slow-

ing Down Theory Parameters. Parvez, A.; Becker, M.

149

COO-2458-18 . A V A I L A B I L I T Y - D E P . , NTIS U - N Y

A V A I L A B I L I T Y - N T I S $6.00 O A R N L

8500 . . Date June 1977 111110 122110 324000 326000 327000 820000 861000

870013 870092 511110 521130 Moments of the Fourier-Transformed Neutron Slow-

ing-Down Kernel: The Computer Code "MAGGIE" . Gado, J.; Keresziuri, A. „ K F K I - 1 9 7 7 - 4 4 A V A I L A B I L I T Y - K O Z P O N T I F I Z I K A I KUTATO

INTEZET, BUDAPEST ( H U N G A R Y ) ISBN 9633712637

H U N G A R

Method of Solution - Mult igroup-Diffusion


6575 Date March 1978 325000 ^ Iterative Solution of the Neutron Transport Equation by

Means of Diffusion Techniques. Michelini, M. i-NUCL. SCI. ENG., 65(3), 532 -53^ I T A L Y

6580 Date March 1978 325000 540000 870017 Expansion About a Local Maxwellian for Evaluating the

Spatially Dependent Neutron Spectrum. (Tech. Note) Molinari, V.G.; Simonini, R. NUCL . SCI. ENG., 65(3), 560-565 I T A L Y

6581 Date December 1976 111130 111400 325000 830000 551110 552210 795179 An Evaluation of Mass Integral Scaling as Applied to the

Atmospheric Radiation Transport Problem. Shulstad, R.A. A F W L - T R - 7 6 - 2 2 1 AV A I L A B I L I T Y - NTIS A IR


Theory Neutronics Results for Perturbation Analyses. Vondy, D.R.; Fowler, T.B. ORNL-5376

6800 Date June 1978 010000 32A000 325000 Computational Procedures for Multidimensional Core Anal-

ysis. Lathrop, K.D. CONF-780401, PP.93-105 A V A I L A B I L I T Y - N T I S ^ LOASL

6943 Date June 1978 111110 325000 551110 713000 810000 Test of the Diffusion Theory Difference Equations in Slab

Geometry (Computer Code VANCER). Vondy, D.R.; Fowler, T.B. ORNL-5381 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

6975 Date August 1978 111110 325000 551110 The Application of the Symmetric SOR and the Symmetric

SIP Methods for the Numerical Splution of Neutron Diffusion Equation.

Wang, H.H.. , NUCL. SCL ENG., 67(2), 162-1;71 IBM

<£1 •7(396 Date October 1976

111110 312000 325000 713000 795217 The Spatial Variation of the Damage Energy and Gas,Pro-

duction in the Experimental Volume of a Li(D,Ij l) Neutron Radiation Damage Facility. &

Alsmiller, R.G.,Jr.; Barish, J. O R N L / T M - 5 5 5 4 A V A I L A B I L I T Y - N T I S OARNL

<3n

\ 7098. . r Date July 1976 111110 112110 112400 112500 325000 521130 522130

632110 820000 An Integrated Method of Calculating Reactor Shielding. Veselkin, A.P.; .Gur'yeva, N.A.; Netecha, M.Ye; Nikitin,

A.V. E R D A - T R - 1 2 5 , PP. 6 - 1 0

' A V A I L A B I L I T Y - N T I S RUSSIA

150

8233 Date January 1968 111110 122110 311000 325000 Interface Conditions for Few Group Equations with

Flux-Adjoint Weighted Constants (LWBR Develop-ment Program).

Buslik, A.J. W A P D - T M - 7 3 3 A V A I L A B I L I T Y - D E P . , NTIS BETTIS

9006 Date June 1978 111110 325000 551110 719A00 810000 A Nodal Method for Solving Transient Fewgroup Neutron

Diffusion Equations. Shober, R.A. A N L - 7 8 - 5 1 A V A I L A B I L I T Y - N T I S S6.00 ARGONN "

8473 Date January 1979 321000 325000 717000 Angular Effects in Toroidal Diffusion. Pomraning, G.C. NUCL. SCI. ENG., 69(1), 6 -13 U - C A

8474 Date January 1979 325000 Fick's Law and the Neutron Slowing Down Length in

Hydrogenous Moderators. Gago, C.B. NUCL. SCI. ENG., 69(1), 55-64 VENEZU

8603 Date 1977 111110 325000 719A00 793000 810000 Neutron Flux Computational Model of the Oak Ridge

Research Reactor. Allen, E.J.; Kerr, H.T. EUR-5667E/F,PT.I, PP.414-423;



O A R N L

8688 Date March 1979 325000 540000 820000 882000 Neutron Diffusion in Water Containing 1/v and N o n - l / v

Absorbers. Bansal, R.M.; Tewari, S.P.; Kothari, L.S. NUCL. SCI. ENG., 69(3), PP.367-374 IND IA

8786 Date February 1979 111110 325000 713000 Exposure Calculation Code Module for Reactor Core Analy-

sis: BURNER. Vondy, D.R.; Cunningham, G.W. r ORNL-5180 A V A I L A B I L I T Y - N T I S $9.25 O A R N L

9072 o Dale April 1979 111110 325000 329000 521130 713000 Monte Carlo-Based Validation of the

E N D F / M C * * 2 - I I / S D X Cell Homogenization Path. Wade, D.C. A N L - 7 9 - 5 A V A I L A B I L I T Y - N T I S $5.25 A R G O N N

9095 Date September 1976 111110 325000 551110 810000 Exact and Approximate Interior Corner Problem in Neutron

Diffusion by Integral Transform Methods. Bareiss, E.H.; Chang, K.S.J.; Constatinescu, D.A. COO-2280-28 A V A I L A B I L I T Y - N T I S U - I L

9174 Date June 1979 111110 325000 H E X A G A - I I - 1 2 0 , -60, - 30 Two-Dimensional

Mult i -Group Neutron Diffusion Programmes for a Uniform Triangular Mesh with Arbitrary Group Scat-tering.

Woznicki, Z. KFK-2789 A V A I L A B I L I T Y - K E R N F O R S C H U N G S Z E N T R U M

KARLSRUHE (F.R. GERMANY) , INSTITUT FUER NEUTRONENPHYSIK U N D REAKTOR-TECHNIK

GERMAN

9305 Date July 1979 111110 312000 325000 32A000 551110 TP2 - A Computer Program for the Calculation of Reactiv-


Kobayashi, K. KFK-2787 AVA ILAB IL ITY -KERNFORSCHUNGSZENTRUM

KARLSRUHE (GERMANY, F.R.), INST. FUER NEUTRONENPHYSIK U N D REAKTORTECH-N I K

GERMAN

151

9403 Date December 1979 325000 713000 Improved Treatment of the Neutron Streaming Through

Control Rod Followers in a Sodium-Cooled Fast Reac-tor. (Tech. Note)

Yoshida, T. NUCL. SCL ENG., 72(3), 361-365 GERMAN

9633 Date March 1980 312000 325000 Homogenized Diffusion Approximations to the Neutron

Transport Equation. Larsen, E.W.; Hughes, R.P. NUCL. SCI. ENG., 73(3), 274-285 LOASL

9743 Date 1979 010000 111110 310000 32A000 325000 Modern Coarse-Mesh Methods - A Development of the

'70's. Doming, J.J. CONF- 790402,VOL.1, PP.3 - 1 - - 3 - 31 A V A I L A B I L I T Y - H C - - A N S V IRGIN IA SECTION,


U - I L

9751 Date 1979 111110 310000 32AOOO 325000 551110 A Nodal Discrete-Ordinates Method for the Numerical

j Solution of the Multidimensional Transport Equation. Wagner, M.R. CONF-790402,VOL.11, PP.4- 117 - -4 -133 A V A I L A B I L I T Y - H C - - ANS V IRGIN IA SECTION,

P.O. BOX 1260. LYNCHBURG, VA. 24505; M F — N T I S

G E R M A N

10136 Date August 1980 111110 325000 551110 SEXI - A Fast Diffusion Program Based on Exponential

and Trigonometric Interpolation. Makai, M.; et ai. EIR-401 A V A I L A B I L I T Y - E I D G . INSTITUT FUER REAK-

TORSCHUNG WURENLINGEN, SWITZERLAND

G E R M A N

Method of Solut ion - Spher ica l -H a r m o n i c s and Po lynomia l Expans ions


6980 Date August 1978 111110 326000 Atlas of Gamma-Ray Spectra from the Inelastic Scattering

of Reactor Fast Neutrons. Siewert, C.E. NUCL. SCI. ENG., 67(2), 259-260 FRANCE

8004 Date March 1978 122210 326000 713000 Approximations of Gamma Cross Sections for Fast Nuclear

Reactors. Grimm, K.N.; Meneghetti, D. A N L - 7 7 - 8 8 A V A I L A B I L I T Y - N T I S S4.00 ARGONN

8026 Date October 1977 111110 326000 Solution of the Time-Dependent, Mul t i -Group Neutron

Transport Equation. Fletcher, J.K. N D - R - 3 0 ( R ) AVA ILAB IL ITY-DEP. , NTIS ENGLAN

8500 Date June 1977 111110 122110 324000 326000 327000 820000 861000


ing-Down Kernel: The Computer Code "MAGGIE" . Gado, J.; Keresziuri, A. KFKI -1977-44 A V A I LAB I L IT Y - KOZPONTI F I Z I K A I KUTATO

INTEZET, BUDAPEST (HUNGARY) ISBN 9633712637

HUNGAR

9017 Date March 1979 111110 326000 521130 795254 The DPN "Surface Flux" Integral Transport Method with

General P sub N Polynomial Approximation. Stepanek, J. EIR-365 AVAILABIL ITY-EIDGENOESSISCHES INST.

FUER REAKTORFORSCHUNG, WUERELINGEN (SWITZERLAND)

GERMAN

152

9548 Date February 1980 310000 326000 A Rigorous Treatment of Transverse Buckling Effects in

Two-Dimensional Neutron Transport Computations. Blomquist, R.N.; Lewis, E.E. NUCL. SCI. ENG., 73(2), 125-139 U - I L

9731 Date Apri l 1980 326000 A Transport Theoretic P„ Approximation. Ganguly, K.; Sengupta, A. 'NUCL. SCI. ENG., 74(1), 1 -12 I N D I A

Method of Solut ion - Success ive S c a t t e r i n g ( inc ludes s ing le s c a t t e r i n g )


8010 Date June 1978 111110 328000 551110 Fast Computation of the Neutron Flux Distribution in X - Y

Geometry Using the QPO First Collision Probability Method.

Stepanek, J.; Hager, H. E IR-344 AVAILABIL ITY-E IDGENOISSISCHES INST. FUER

REAKTORFORSCHUNG, WUERENLINGEN, SWITZERLAND

G E R M A N

9750 Date 1979 111110 311000 326000 511110 Refinements for Spatial Channel Theory Computations. Abu-Shumays, I.K.; Selva. R.J.; Shure, K. CONF-790402,VOL.11, P P . 4 - 9 5 - - 4 - 1 1 5 A V A I L A B I L I T Y - H C - - ANS V IRGIN IA SECTION,


BETTIS

Meil-Sod of Solut ion - M o m e n t s


9071 Date 1977 111110 112110 122110 328000 329000 511110 512110




M A A G

Method of Solut ion - Monte Car lo


8500 Date June 1977 111110 122110 324000 326000 327000 820000 861000


ing-Down Kernel: The Computer Code "MAGGIE" . Gado, J.; Keresziuri, A. KFK I -1977 -44 A V A I L A B I L I T Y - K O Z P O N T I F I Z I K A I KUTATO


H U N G A R

6234 Date 1976 111110 329000 511110 810000 Application of Collision Probability and Monte Carlo Meth-

ods on Analysis of Neutron Spectra Transformed by a Fission Converter.

Milosevicj, M.; Kocicj, A.; Altiparmarkov, D. I N I S - M F - 3 2 8 5 ( I N SERBIAN) A V A l L A B I L I T Y - I N S T I T U T ZA N U K L E A R N E

N A U K E BORIS KIDRIC, BELGRADE (YUGOSLA-V IA)

YUGOSL

8580 Date 1977 111110 122310 327000 511110 861000 870011 Neutron Slowing Down and Transport in Monoisotopic

Media with Constant Cross Sections or with a Square-Well Minimum.

Peng, W.H. COO-2509-6 A V A I L A B I L I T Y - D E P . , NTIS U - N Y

6293 Date October 1977 111110 020000 329000 719A00 Improvement of Reference Nuclear Data for Commercial

Power Reactor Analysis and Design. Levitt, L.; Magurno, B.; Rose, P. EPRI -NP-556 A V A I L A B I L I T Y - E L E C T R I C POWER RESEARCH

INSTITUTE, 3412 H I L L V I E W AVENUE, PALO ALTO, CALIFORNIA 94304

153

EPRI

6313 Date December 1977 329000 A Monte Carlo Method of Solving Heat Conduction Prob-• lems.

Fraley, S.K.; Hoffman, T.J. O R N L / N U R E G / C S D - 3 A V A I L A B I L I T Y - N T I S O A R N L

6322 Date July 1977 010000 329000 MOCARS: A Monte Carlo Code for Determining the Dis-

tribution and Simulation Limits. Matthews, S.D. TREE-1138 }; A V A I L A B I L I T Y - N T I S EDGERT

6365 Date 1977 010000 329000 Computational Methods for Data Analysis. Cuambers, J.M. BOOK A V A I L A B I L I T Y - N E W YORK, WILEY BELL

6396 Date Dec. 1977 719B00 329000 Neutron and Gamma-Ray Transport Studies in the

Helium Ducts and Turbogroups of a High Temperature Reactor with Helium Turbine ( H H T ) Using the Monte Carlo Method.

Taormina, A.; Kypreos, S. CONF-770401, PP.262-270 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6425 Date Dec, 1977 111210 717000 329000 795203 721100 Monte Carlo Analysis of the Effects of Penetrations on the

Performance of a Tokamak Fusion Reactor. Santoro, R.T.; Tang, J.S.; Alsmiller, R.G,Jr.; Barnes, J.M. CONF-770401, PP.527-535 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6431 Date Dec. 1977 329000 Simultaneous Global Calculation of Flux and Importance

with Forward Monte Carlo. Deutsch, O.L.; Carter. L.L. CONF-770401, PP.580-589 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 U - M

6432 Date Dec. 1977 329000 The Monte Carlo Track Rotation Estimator. Dubi, A.; Horowitz, Y.S. CONF-770401, PP.590-597 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 ISRAEL

6433 Date Dec. 1977 329000 Direction Dependent Exponential Biasing in Monte Carlo

Simulation of Radiation Transport in Thick Shields. Murthy, K.P.N. CONF-770401, PP.598-604 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 INDIA

6434 Date Dec. 1977 329000 32A000 Methods of Monte Carlo Biasing Using Two-Dimensional

Discrete Ordinates Adjoint Flux. Tang, J.S.; Hoffman, T.J.; Stevens, P.N. CONF-770401, PP.605-612 AVAILAB IL ITY -SCIENCE PRESS, 8 BROOKSTONE


6435 Date Dec. 1977 329000 122210 A Partial-Range Expansion for Multigroup Monte Carlo

Photon Transport. Ward, J.T,Jr.; Scudiere, M.B. CONF-770401, PP.613-621 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 U - V A

6436 Date Dec. 1977 329000 717000 Calculation of Toroidal Fusion Reactor Blankets by Monte

Carlo.

254

Macdonald, J.L.; Cashwell, E.D.; Everett, C.J. CONF-770401, PP.622-627 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6437 Date Dec. 1977 329000 717000 A Neutron/Photon/Electron Shielding Study for a

Laser-Fusion Facility. Thompson, W.L. CONF-770401, PP.628-635 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6438 Date Dec. 1977 329000 721100 A Study of Applicability of an Albedo Monte Carlo Method

for Neutron Streaming Calculation. Kawai, M.; Yamauchi, M,; Kadotani, H.; Suzuki, I. CONF-770401, PP.636-644 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


643 9 Date Dec. 1977 329000 721100 Neutron Streaming Through Conical Ducts, de Beer, G.P. CONF-770401, PP.645-651 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 SAFRIC

644 0 Date Dec. 1977 329000 32A000 532000 719AOO Evaluation of Uncertainties in the Gamma-Ray Heating

Analysis of a PWR. West, J.T.,III CONF-770401, PP.652-659 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


644 1 Date Dec. 1977 329000 712000 An Examination of Neutron Shielding for a Spent Fuel Ship-

ping Cask. Ueki, K.; Yamakoshi, H.; Takeuchi, K. CONF-770401, PP.660-667 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


JAPAN

6520 Date January 1978 220000 329000 A Conditioned Random Walk with Applications. Beyer, W.A.; Waterman, M.S. L A - 6 9 9 0 - M S A V A I L A B I L I T Y - N T I S $4.00 LOASL

6523 Date January 1978 329000 A New Probability Distribution with Applications in Monte

Carlo Studies. Johnson, M.E.; Johnson, M.M. L A - 7 0 9 5 - M S A V A I L A B I L I T Y - N T I S $4.00 LOASL

6619 Date March 1978 329000 632200 717000 "Sensing" the Elliptical Torus. Cashwell, E.D.; Everett, C.J. L A - 7 1 8 7 - M S A V A I L A B I L I T Y - N T I S LOASL

6620 Date March 1978 112B00 121200 329000 810000 A New Method of Sampling the Klein-Nishina Probability

Distribution for A l l Incident Photon Energies Above 1 keV. (A Revised Complete Account).

Everett, C.J.; Cashwell, E.D. L A - 7 1 8 8 - M S A V A I L A B I L I T Y - N T I S LOASL

6621 Date March 1978 329000 Cost of Splitting in Monte Carlo Transport. Everett, C.J.; Cashwell, E.D. L A - 7 1 8 9 - M S A V A I L A B I L I T Y - N T I S V LOASL

6645 Date Apri l 1978 312000 329000 A Monte Carlo Perturbation Source Method for Reactivity

Calculations. Hoffman, T.J.; Petrie, L.M.; Landers, N.F. NUCL. SCI. ENG., 66(1), 60-66 O A R N L

155

6648 Date April 1978 329000 General Formulation of Tract-Length-Type Estimators.

(Tech. Note) Lux, I. NUCL. SCL ENG., 66(1), 121-124 H U N G A R

7045 Date October 20, 1976 111110 329000 421120 422140 430000 Monte Carlo Efficiency Piedictions for a Portable 3 - H e

Neutron Detector. O'Dell, A.A. UCRL-52151 A V A I L A B I L I T Y - N T I S L A L L

6733 Date May 1978 111110 329000 Remark on the Efficiency of Track-Length Estimators in

Reaction Rate Estimations. (Tech. Note) Lux, I. NUCL . SCL ENG., 66(2), 258-264 H U N G A R


trons. Part I: Monte Carlo Calculations of Thick-Target Bremsstrahlung Spectrum.

Shin, K.; Hayashda, Y.; Nakamura, T. NUCL. INSTRUM. METHODS, 151(1,2), 271-276 JAPAN

6879 Date July 1978 329000 Unified Definition of a Class of Monte Carlo Estimators. Lux, 1. NUCL. SCL ENG., 67(1), 107-119 H U N G A R

7067 Date January 1977 111500 121100 329000 810000 A Random Sampling Technique for Choosing Scattering



NBS SPEC. PUB. 461, PP. 100-105 AV A I L AB IL ITY - SUPT. OF DOCUMENTS, GPO,


7085 Date January 1977 111110 329000 511110 521110 795171 795017 810000 Neutron Dose Evaluation Using Calculated Neutron Spec-

tra. Makra, S. NBS SPEC. PUB. 461, PP. 238-246 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

WASHINGTON, D.C. 20402 HUNGAR

6885 Date 1974 329000 T H E M O N T E CARLO METHOD. (Translated and

Adapted from the 2nd Russian Edition by Robert Messer, John Stone, and Peter Fortini)

Sobol', I .M. BOOK A V A I L A B I L I T Y - C H I C A G O , UNIVERSITY OF CHI-

CAGO PRESS RUSSIA

7108 Date July 1976 112B00 329000 512110 861000 Investigating the Field of Scattered Radiation at Great Dis-

tances From the Source. Zolotukhin, V.G.; Ksenofontov, A.I.; Panchenko, A.M.;

Sinev, V.N. ERDA-TR-125 , PP. 92-99 A V A I L A B I L I T Y - N T I S RUSSIA




7109 Date July 1976 112B00 329000 722100 810000 Passage of Gamma-Radiation from Point Sources with an

Arbitrary Angular Distribution of Quanta Through Curved Ducts in Shielding.

Zolotukhin, V.G.; Yefimenko, B.A.; Klimanov, V.A.; Kochanov, V.A.; Mashkovich, V.P.; Orlov, N.Yu.

ERDA-TR-125 , PP. 100-105 A V A I L A B I L I T Y - N T I S RUSSIA

156

7117 Date July 1976 112110 329000 532000 861000 870082 Investigation of Radioactive Heat Generation in Structural

Materials of Shielding Placed in Light Mediums. Avayev, V.N.; Yefimov, Ye.P. E R D A - T R - 125, PP. 169-175 A V A I L A B I L I T Y - N T I S RUSSIA

802 1 Date April 1978 329000 Electron Transport Code Theoretical Basis. Dubi, A.; Horowitz, Y.S. L A - 7 2 2 7 - M S A V A I L A B I L I T Y - D E P . NTIS LOASL

802 2 Date May 1978 111220 220000 329000 760000 795161 Calculation of Dosimetry Parameters for Fast Neutron

Radiotherapy. Wells, A.H. L A - 7 2 8 8 - T A V A I L A B I L I T Y - N T I S $13.25 LOASL

8046 Date May 1978 112760 329000 731200 795299 Calculation of Exposure Rates from Gainma Sources in

Walls of Dwelling Rooms. Koblinger, L. HEALTH PHYS., 34(5), 459-463 HUNGAR

Lux, I. NUCL. SCL ENG., 67(3), 317-325 HUNGAR

8116 Date July iy78 112130 121200 329000 512110 610000 830000 The Time Dependence of the Compton Current and Energy

Deposition from Scattered Gamma Rays. Malik, J.S.; Cashwell, E.D.; Schrandt, R.G. L A - 7 3 8 6 - M S A V A I L A B I L I T Y - L O S ALAMOS SCIENTIFIC LAB.,

P.O. BOX 1663, LOS ALAMOS, NEW MEXICO 87545

LOASL

8143 Date October 1978 311000 329000 Monte Carlo Aspects of Contributions. Dubi, A.; Gerstl, S.A.W.; Dudziak, D.J. NUCL. SCI. ENG., 68(1), 19-30 LOASL

8215 Date September 1978 112B00 121200 329000 820000 A Monte Carlo Code (PHOEL) for Generating Initial Ener-

gies of Photoelectrons and Compton Electrons Produced by Photons in Water.

Turner, J.E.; Modolo, J.T.; Sordi, G.M.A.A.; Hatnm, R.N.; Wright, H.A.

ORNL/TM-6515 A V A I L A B I L I T Y - N T I S $4.00 OARNL

8049 Date June 1978 329000 A Note on the Fluence Concept. (Notes) Chilton, A.B. HFA.LTH PHYS., 34(6), 715-716 U - I L

809 2 Date September 1978 329000 'A Monte Carlo Biasing Scheme for Adjoint Photon Trans-

port. De Matteis, A.; Simonini, R. &UCL. SCL ENG., 67(3), 309-316 ITALY

809 3 Date September 1978 329000 Systematic Study of Some Standard Variance Reduction

Techniques.

8228 Date May 1977 111210 329000 521130 717000 810000 Effect of Particle Histories Termination Parameters on

Monte Carlo Estimates in Fusion Reactor Blanket Scop-ing Studies.

Ragheb, M.M.H.; Gohar, Y.M.; Maynard; C.W. UWFDM-192 A V A I L A B I L I T Y - F U S I O N TECHNOLOGY PRO-

GRAM, NUCLEAR ENGINEERING DEPT., UNIVERSITY OF WISCONSIN, MADISON, WIS-CONSIN 53706

U - W I

8231 Date October 1978 111210 329000 521130 717100 810000 795203 Monte Carlo Statistical Weighting Methods for Exter-

nal-Source-Driven Multiplying Systems. Ragheb, M.M.H.; Maynard, C.W. UWFDM-265

157

A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM, NUCLEAR ENGINEERING DEPT., UNIVERSITY OF WISCONSIN, MADISON, WISCONSIN 53706

U - W I ''

8235 Date April 1975 111110 329000 719A00 870092 Monte Carlo Analysis of Direct Measurements of the Ther-

mal Eta(0.025 eV) for 233-U and 235-U (LWBR Development Program).

Ullo, J.J.; Goldsmith, M. WAPD-TM-1217 AVAILABIL ITY-DEP. , NTIS BETTIS

8236 Date April 1975 111110 329000 719A00 870092 Monte Carlo Analysis of Thermal Spectrum Averaged Mea-

, surements of Eta of 233-U and 235-U (LWBR Development Program).

Goldsmith, M.; Ullo, J.J. WAPD-TM-1218 AVAILABIL ITY-DEP. , NTIS BETTIS

8237 Date August 1978 111110 112110 329000 719A00 RCPOl - A Monte Carlo Program for Solving Neutron

and Photon Transport Problems in Three-Dimensional Geometry and Detailed Energy Description (LWBR Development Program).

Candelore, N.R.; Gast, R.C.; Ondis, L.A.,II WAPD-TM-1267 A V A I L A B I L I T Y - N T I S BETTIS

8404 Date September 1977 222000 329000 Derivation of the Probability Density Function for a Sto-

chastic Nonlinear Advection Equation. Meyers, R.E.; O'Brien, E.E.; Scott, L.R. BNL-50732 A V A I L A B I L I T Y - N T I S S4.00 BROOKH

8475 Date January 1979 329000 Monte Carlo Source Biasing Optimization. Hoffman, T.J. NUCL. SCL ENG. 69(1), 76-77

' . .OARNL

8496 Date January 1978 111210 329000 32A000 551110 552110 793000 717000


Engineering, Tritium and Neutronics. Project Staff - Argonne National Lab. GA - A14614.VOL.V; ANL/FPP/77 - 6.VOL. V A V A I L A B I L I T Y - N T I S $8.00 GEAC

8522 Date October 12, 1978 010000 329000 430000 On Some Statistical Problems Inherent in Radioac-

tive-Source Detection. Barnett, C.S. UCRL-52588 AVAILABIL ITY - N T I S LALL

8564 Date 1977 111210 329000 531000 532000 717000 795203 Nuclear Heat Deposition in Cryosorption Pumps of a Fusion

Reactor, lida, H.; Ide, T.; Seki, Y. CONF-771029,VOL.11, PP.1658-1662 AVAILABIL ITY- IEEE SERVICE CENTER, SINGLE


JAPAN


tor-Response Kernels. Scott, W.H.,Jr.; McDaniel, P.J.; Renken, J.H.; Wright, S.A. ORNL/RSIC-42, PP.61-74 A V A I L A B I L I T Y - N T I S SCA

8670 Date February 1979 111110 329000 .312000 430000 713000 795203 Fuel-Motion Unfolding Based on Point Detector

Responses. McDaniel, P.J.; Wright, S.A. ORNL/RSIC-42, PP.319-327 AVA ILAB IL ITY -NT IS SANDIA

8687 Date March 1979 329000 A Random Geometry Model in Criticality Calculations of

Solutions Containing Raschig Rings. Teng, S.; Lindstrom, D.G.

158

NUCL. SCL ENG., 69(3), PP.363-366 U - O K

8727 Date 1977 111210 329000 717000 795203 810000 Three-Dimensional Analysis of the Effects of Penetrations

on Radiation Shielding of a Tokamak Fusion Reactor. Ide, T. J A E R I - M - 7 3 6 0 A V A I L A B I L I T Y - J A P A N ATOMIC ENERGY

RESEARCH INSTITUTE, TOKAI , JAPAN JAPAN

8729 Date September 1978 111110 329000 810000 ,. The Application of Artificial Intelligence Techniques to the

Acceleration of Monte Carlo Transport Calculations. Mavdonald, J.L.; Cashwell, E.D. LA-7475 A V A I L A B I L I T Y - N T I S LOASL

874 9 Date Apri l 1979 329000 Optimal Choice of Parameters for Exponential Biasing in

Monte Carlo. Dubi, A.; Dudziak, D.J.

- NUCL. SCL ENG., 70( 1), 1-13 LOASL

875 0 Date Apri l 1979 329000 Bounded F lux-a t -a -Po in t Estimators for Multigroup

Monte Carlo Computer Codes. 0 Fraley, S.K.; Hoffman, T.J. NUCL. SCL ENG., 70(1), 14-19 O A R N L

8773 Date January 1979 329000 Analysis of Error in Monte Carlo Transport Calculations. Booth, T.E. LA-7636.-T; THESIS A V A I L A B I L I T Y - L O S ALAMOS SCIENTIFIC LABO-

RATORY, P.O. BOX 1663- LOS ALAMOS, NEW MEXICO 87545 Q

LOASL

8797 Date February 1979 111110 329000 721100 722100 793000 719A00 610000

861000 853100 An Improved Streaming Analysis Technique: Spherical

Harmonics Expansion.of Albedo Data.

Albert, T.E.; Simmons, G.L. ORNL/RSIC-43.PP.68-75;

ANS/SD-79/16.PP.68-75 A V A I LABI L IT Y - N T I S SCA

„ ' 8798 Date February 1979 111110 223000 329000 721100 721200 722100 620000

719A00 422110 Reactor Cavity Streaming—The Problem and Engineer-


ANS/SD - 79/16,PP.76 -109 A V A I L A B I L I T Y - N T I S o EBASCO

8804 Date February 1979 111110 329000 719A00 721100 810000 Radiation Shielding for BWR Shield Wall Penetrations. Gillett, T.C.; Warkentin, J.K. ORNL/RSIC-43,PP. 163 - 177;

ANS/SD - 79/16,PP. 163 - 177 A V A I L A B I L I T Y - N T I S BRAUN

8885 Date March 1979 111500 32AOOO 329000 551110 552210 853100 861000

795203 793000 The SAI /EPRI Albedo Information Library. Simmons, G.L. EPRI-NP-1017 A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, INC.,


SCA

8886 Date Apri l 1979 111110 329000 795187 Development of the Criticality Capability for the SAM - CE

Monte Carlo System. Lichtenstein, H.; Troubetzkoy, E.S.; Steinberg, H.; Cohen,

M.O. E P R I - N P - 1042 A V A I L A B I L I T Y - M A T H E M A T I C A L APPLICA-

TIONS GROUP, INC., 3 WESTCHESTER PLAZA, ELMSFORD, NEW YORK 10523

M A A G

8904 Date March 1979 111500 220000 329000 845000 793000 795203 Neutron ami Gamma Ray Response/Fiuence Factors for

Human Dosimetry Applications.

159

Kaul, D.; Chen, S.; Jarka, R. SAI -121 - 1 3 2 - 1 A V A I L A B I L I T Y - S C I E N C E APPLIATIONS, INC.,

1701 EAST WOODFIELD RD„ SUITE 819, SCHAUMBURG, ILL . 60195

SCA

8908 Date May 26, 1978 II1210 329000 717000 717100 810000 Nuclear Design of the L L L - G A U/sub 3/Si Blanket. Lee, J.D. UCRL-80588; CONF-780508-27 AVAILABIL ITY-DEP. , NTIS L A L L

8921 Date May 1979 329000 Optimum Biasing of Integral Equations in Monte Carlo Cal-

culations. Hoogenboom, J.E. NUCL. SCI. ENG., 70(2), 210-212 NETHER

8922 Date June 1979 329000 Prediction of Statistical Error and Optimization of Biased

Monte Carlo Transport Calculations. Sarkar, P.K.; Prasad, M.A. NUCL. SCI. ENG., 70(3), 243-261 I N D I A

8965 Date May 14, 1979 111110 329000 Thermal Neutron Scattering Treatment in the Monte Carlo

Code V IM. Milton, L.J. F R A - T M - 120 A V A I L A B I L I T Y - A P P L I E D PHYSICS DIVISION,

ARGONNE N A T I O N A L LABORATORY, 9700 SOUTH CASS AVENUE, ARGONNE, ILL. 60439

ARGONN

8969 Date May 1979 111110 329000 721100 870011 Contributon Monte Carlo. Dubi, A.; Gerstl, S.A.W. L A - 7 8 4 9 - M S A V A I L A B I L I T Y - N T I S LOASL

8997 Date July 1979 329000 Calculation of the Total Flux at a Point by the Monte Carlo

Track Rotation Estimator. Dubi, A.; Horowitz, Y.S. NUCL. SCI. ENG., 7L(L), 29-45 I T A L Y

9022 Date Apri l 1979 010000 329000 A Relativity Primer for Particle Transport. A LASL Mono-

graph. Everett, C.J.; Cashwell, E.D. L A - 7 7 9 2 - M S A V A I L A B I L I T Y - L O S ALAMOS SCIENTIFIC LABO-

RATORY, NEW MEXICO LOASL

9044.-. Date December 1978 112BOO 329000 220000 845000 Realistic Calibration of Whole- Body Counters for Measur-

ing Plutonium. Parkinson, W.W.,Jr.; Goans, R.E.; Good, W.M. STI /PUB-471 (VOL.2),PP. 155-166;

CONF-771209-P2,PP.155-166; A V A I L A B I L I T Y - I N T E R N A T I O N A L ATOMIC

ENERGY AGENCY, V IENNA (AUSTRIA) OARNL

9067 Date August 1979 329000 Analysis of Error in Monte Carlo Transport Calculations. Booth, T.E.; Cashwell, E.D. NUCL. SCI. ENG., 71(2), 128-142 LOASL

9071 Date 1977 111110 1121.10 122110 328000 329000 511110 512110

795203 830000 Order of Scattering Calculations of Photon ancl. Neutron

Transport. ° 0

De Gangi, N.L. THESIS A V A I L A B I L I T Y - M A T H E M A T I C A L APPLICA-


M A A G

9127 Date May 1979 111210 329000 717100 795203 810000 SOLASE-H - A Laser Fusion Hybrid Study.

160

Conn, R.W.; Abdel-Khalik, S.I.; Moses, G.A.; Cooper, G.W.; Howard, J.E.; Kulcinski, G.L.; Larsen, E.; May-nard, C.W.; Ragheb, M.M.H.; Sviatoslavsky, I.N.; Vogelsang, W.F.; Wolfer, W.G.; Ortman, M,; Smatlak, D.L.; Watson, R.; Youssef, M.Z.

UWFDM-270 A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-


U - W I

9185 Date August 1979 112720 512110 329000 820000 User's Manual for PHOEL-2, a Monte Carlo Computer



ORNL/TM-6954 ^ A V A I L A B I L I T Y - N T I S $4.50 OARNL

9254 Date October 1979 329000 On the Analysis of the Variance in Monte Carlo Calcula-

tions. (Tech. Note) C<i Dubi, A.

NUCL. SCI. ENG., 72(1), 108-110 LOASL

GERMAN

9506 Date December 5, 1979 329000 Epithermal Scattering in VIM. Gelbard, E.M. F R A - T M - 1 2 3 A V A l LABILITY-A.PPLIED PHYSICS DIV.,

ARGONNE NAT IONAL LABORATORY, 9700 SOUTH CASS AVENUE, ARGONNE, ILL INOIS 60439

ARGONN

9547 Date February 1980 329000 554110 Monte Carlo Treatment for Neutral Particle Transport

Problems in a Toroidal Plasma. Inoue, S.; Taji, Y.; Nakahara,()Y.; Suzuki, T. NUCL. SCI. ENG., 73(2), 119-124 JAPAN

9562 Date August 1979 111400 112130 329000 795203 731100 793000 810000 Radiation Shielding Properties of Selected Materials. Rainis, A.E.; Kinch, J.W.; Bowers, G.A. ARBRL-TR-02187 AVAILABIL ITY-DEFENSE DOCUMENTATION

CENTER, CAMERON STATION, ALEXANDRIA, VA 22314

A R M Y

9306 Date July 1979 111210 329000 521130 717000 793000 794000 795254

810000 Fast Rigorous Numerical Method for the Solution of the

Anisotropic Neutron Transport Problem and the Nitran System for Fusion Neutronics Applications. Part I.

Takahashi, A.; et al. KFK-2832/1 AVAILABIL ITY-KERNFORSCHUNGSZENTRUM

KARLSRUHE GMBH, KARLSRUHE (F.R. GER-M A N Y )

GERMAN

9438 Date October 1979 111210 -329000 521130 717000 793000 794000 795254


Anisotropic Neutron Transport Problem and the Nitran System for Fusion Neutronics Application. Part II.

Takahashi, A.; Rusch, D. KFK-2832 / I I AVAILABIL ITY-KERNFORSCHUNGSZENTRUM

KARLSRUHE (GERMANY, F.R.)

9600. . Date November 1979 111110 111500 112BOO 329000 MCNP - A General Monte Carlo Code for Neutron and

Photon Transport. L A - 7 3 9 6 - M , REV. A V A I L A B I L I T Y - L O S ALAMOS SCIENTIFIC LAB.,

NEW MEXICO LOASL

970 6 Date December 1979 329000 MCNP, a General Monte Carlo Code for Neutron and Pho-

ton Transport: A Summary. Thompson, W.L. LA -8176 -MS AVAILABIL ITY-DEP. , NTIS, PC A02/MF A01 LOASL

0

970 7 Date January 1980 111210 311000 329000 551110 870011 Application of Biasing Techniques to the Contributon Monte

Carlo Method. t-

161

Dubi, A.; Gerstl, S.A.W. LA-8201 - M S A V A I L A B I L I T Y - D E P . , NTIS, PC A03 /MF A01 LOASL

9727 Date January 1980 329000 ^ Variance Versus Efficiency in Transport Monte Carlo. Lux, I. NUCL. SCL ENG., 73(1), 66-75 HUNGAR Sf

9734 Date April 1980 329000 A Study of Variance in Energy-Dependent Monte Carlo

Transport Problems. (Tech. Note) " Sarkar, P.K.; Prasad, M.A. NUCL. SCI. ENG., 74(1), 52-60 I N D I A ' 1}

9758 Date 1979 010000 111110 329000 795187 A Comprehensive Survey of Continuous Energy

Three-Dimensional Monte Carlo Criticality Codes. Steinberg, H.A. CONF-790402,VOL.11, P P . 7 - 1 - - 7 - 8 A V A I L A B I L I T Y - H C - - ANS VIRGINIA.SECTION,

P.O. BOX 1260, LYNCHBURG, VA. 24505; M F - -NTIS,

M A A G ° a

9759 Date 1979 111110 329000 719B00 Monte Carlo Computation of Directional Diffusion Coeffi-

cients. Gelbard, E.M.; Pego, R. CONF-790402,VOL.11, P P . 7 - 9 - - 7 - 1 9 A V A I L A B I L I T Y - H C - - A N S V IRGINIA SECTION,

P.O. BOX 1260, LYNCHBURG, VX. 24505; M F — N T I S

ARGONN <f

9978 Date May 1980 010000 329000 32A000 521130 810030 The Status of Monte Carlo at Los Alamos. Thompson, W.L.; Cashwell, E.D.; Godfrey, T.N.K.; Sch-

randt, R.G.; Deutsch, O.L.; Booth, T.E. LA -8353 -MS; ORNL /RS IC-44 , PP.231-246* A V A I L A B I L I T Y - N T I S $5.25 LOASL

9985 Date August 1980 010000 329000 ^ A Review of the Theory and, Application of Monte Carlo

Methods - Proceedings of a Seminar-Workshop, Oak Ridge, Tennessee, Apri l 21-23, 1980.

Trubey, D.K.; McGill, B.L. (Eds.) ORNL/RSIC 7 44 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 OARNL

9986 Date August 1980 010000 111U0 111220 329000 713000 750000 810000 Monte Carlo Applications at Hanford Engineering Develop-

ment Laboratory. Carter, L.L.; Morford, R.J. ORNL/RSIC-44, PP.7-30 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 "J

HANFOR

9760 Date 1979 111210 329000 711100 717100 795203 Monte Carlo Statistical Weighting Methods for External

Source Driven Multiplying Systems. Ragheb, M.M.H.; Maynard, C.W. C O N F - 790402,VOL.II, PP.7 - 21 - - 7 - 35 A V A I L A B I L I T Y - H C - - A N S V IRGINIA SECTION,


U - W I

9987 Date August 1980 010000 329000 V I M - A Continuous Energy Monte Carlo Code at ANL . Blomquist, R.N.; Lell, R.M.; Gelbard, E.M. ORNL/RSIC-44 , PP.31-46 A V A I L A B I L I T Y - N T I S , I^C,A16/MF A01 ARGONN

9988 Date August 1980 010000 312000 329000 521130 810000 Monte Carlo Perturbation ..Theory in Neutron Transport

Calculations. Hall, M.C.G. ORNL/RSIC-44, PP.47-62 A V A I L A B I L I T Y - N T I S , PC A16 /MF A01 ENGLAN

9989 Date August 1980 010000 122310 329000 521130 795372 795254 Study of Perturbations Using Correlated Monte Carlo

Method. Dejonghe, G.; Gonnord, J.; Nimal, J.C. ORNL/RSIC-44, PP.63-93 A V A I L A B I L I T Y - N T I S , PC A16 /MF A01 FRANCE

o 162 a

9990 Date August 1980 111110 329000 719A00 TRIMARAN: A Threee Dimensional Multigroup P1 Monte

Carlo Code for Criticality Studies. Ermumcu, G.; Gonnord, J.; Nimal, J.C. ORNL/RSIC-44, PP.95-106 , . r f A V A I L A B I L I T Y - N T I S , PC Aie/MF^AOl ' FRANCE f y

9991 Date August .1980 ,1111 jO 122110 329000 711100 793000J734000 8,10000 KENO Calculations of Light Water Fiiel Lattices. Hebert, M.J.; Handschuh, J.A.; Pilat, E.E.; Harris, D.R.;

Mayer, J.A. ORNL/RSIC-44, PP. 107-120 A V A I L A B I L I T Y - N T I S , PC A16/MF A01 ^ YAAEC

9992 ^Date August 1980 . .010000 122110 329000 712000 Q

KENO V - The Newest KENO Monte Carlo Criticality Program.

Landers, N.F.; Petrie, L.M. ORNL/RSIC-44, PP.121-128 n

A V A I L A B I L I T Y - N T I S , PC A16/MF AOL OARNL

9996. . : Date August 1980 010000-329000 721100 719A00 795187 Radiation Streaming with SAM-CE. De Gangi, N,;,Cohen, M.O.; Waluschka, E.; Steinberg, H.A. ORNL/K,;';H:'-i44, PP. 151 -155 , A V A I L ^ f ^ i T Y - N T I S , PC A16/MF A01 ' "

ft

-o" V Date August 1980 ; 020000*329000 521130 795187 8'i0000

TRX, 'aife 7jl?p/sub 2/ Benchmark Criticality Calculations w:t h i.^A'lsi i C E. & 'r

Beer^M.i ^v-Mhcizkoy, E.S.; Lichtenstein, H.;' Rose, P.F. ORNL/RSIC-44* ' PP. 157 -167 A V A I L A B I L I T Y - N T I S , PC A16/MF A01 MAAG o o -

& , i/ 9998 f. . . . Date August 1980

010000 312000 329000 717000 810000 The Recursive Monte Carlo Method;for Deep-Penetration

Problems. Goldstein, M.; Greenspan, E. Q

ORNL/RSIC-44, PP.I69-187 AVA ' l LAB lL lTY-NTIS , PC A16 /MF A01 OARNL

9993 Date August 1980 111110 329000 795187 Geometry Modeling for S A M - C E Monte Carlo Calcula-

tions. Steinberg, H.A.; Troubetzkoy, E.S. ORNL/RSIC-44, PP.129-136 \\ A V A I L A B I L I T Y - N T I S , PC A16/MF A01 MAAG " " cv

9999 Date August 1980 010000 329000 719A00 795376 The Monte Carlo Lattice Program KIM.

i) Cupini, E.; De Matteis, A';; Simonini, R. ORNL/RSIC-44, PP.189-196 AVA ILAB IL ITY -NT IS , PC A16/MF A01 ITALY I i

9994 Date August 1980 010000 329000 795187 Nuclear Data Treatment for S A M - C E Monte Carlo Cal-" culations. Lichtenstein, H.; Troubetzko>VE-S.; Beer, M. ORNL/RSIC-44, PP.137-142 A V A I L A B I L I T Y - N T I S , PC A16/MF A01 MAAG

10001. Date August 1980 112B00 220000 311000 329000 795299 845000 Adjoint MC Techniques and Codes for Organ Dose Calcula-

tions. Koblinger, L. ORNL/RSIC-44, PP.203-217 AVA ILAB IL ITY-NT IS , PC A16/MF A01 ' HUNGAR

9995 Date August 1980 010000 329000 795187 Monte Carlo Methodology as Implemented in S A M - F . Troubetzkoy, E.S.; Steinberg, H.A. ORNL/RSIC-44, PP. 143-150 A V A I L A B I L I T Y - N T I S , PC A16/MF A01 MAAG

10003 Date August 1980 010000 329000 „-• 0

Geometry in MCNP. ~<' Godfrey, T.N.K. ORNL/RSIC-44, PP.247-252 AVAILABIL ITY-NT IS , PC A16/MF A01. LOASL O *

163

10004 Date August 1980 010000 329000 Flux at a Point in MCNP. Cashwell, E.D.; Schrandt, R.G. ORNL/RSIC-44 , PP.253-265 A V A I L A B I L I T Y - N T I S , PC A16 /MF A01 LOASL

10005 Date August 1980 010000 329000 721100 853100 870011 Deep-Penetration Calculations. ,

'Thompson, W.L.; Deutsch, O.L.; Booth, T.E. <••, ' '' ORNL/RSIC-44 , PP.267-294 ^ • A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 LOASL

Method of Solution - In tegra l Boltzmann Equation


( 6452 Date Dec. 1977 330000 The Direct-Coupled-Ray ' Method for

Three.^ Dimensional Shieling, Analysis. • _ t Bucholz, I ci ""'•">' ^ C O N F - 7 7 0 4 0 1 , PP.746-753^ATOMKERNENERGIE,

S ' (i -v30(4), 31^-316(1977) „ „ O ^AVAILAB IL ITY-SCIENCE PRESS, 8 BROOKSTONE

DR.^' PRINCETON, NJ 08540 OARNL

1( 10007 Date August 1980 010000 329000 795203 " MORSE: Current Status of the Two Oak Ridge Versions. Emmett, M.B.; West, J.T.,III ORNL/RSIC-44 , PP.305-312 '" A V A I L A B I L I T Y - N T I S , PC A16 /MF A01

' O A R N L

6453 Date Dec. 1977 330000 .. A Coarse-Mesh Algorithm to Solve the Neutron Transport

Equation in Thick Shields. Vaidyanathan, R. " CONF-770401, PP.754-761 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 INDIA

10008 Date August 1980 010000 329000 795372 Overview on TRIPOLI 2. Gonnord, J.; Baur, A.; Bourdet, L.; Dejonghe, G.; Monnier,

A.; Nimal, J.C.; Vergnaud, T. ORNL/RSIC-44 , PP.313-328 A V A I L A B I L I T Y - N T I S , PC A16 /MF A01 FRANCE

7063 Date January 1977 111500 112BOO 330000 Integral Equation Methods in Radiation Transport. Gopinath? D.V. " NBS SPEC. PUB. 461, PP. 79-86 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

WASHINGTON, D.C. 20402 0 INDIA



Ueki, K. ORNL/RSIC-44 , PP.329-344 A V A I L A B I L I T Y - N T I S , PC A16 /MF A01 JAPAN

7065 Date January 1977 "111110 330000 551110 870092 870094 Criticality Calculations by Source-Collision Iteration

Technique for Cylindrical Systems. Sundaram, V.K.; Gopinath, D.V. NBS SPEC. PUB. 461, PP. 94-96 , A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

-WASHINGTON, D.C. 20402 INDIA o

10010 Date August 1980 Q

111110 329000 711100 810000 Applicability of Monte Carlo Code KENO - I V . Yamakoshi, H. c

ORNL/RSIC-44 , PP.345-349 A V A I L A B I L I T Y - N T I S , PC A16 /MF A01 JAPAN


tions. ° ° Gogotovar; L.G.; Nikitin, A.V. ERDA-TR-125 , PP. 11-16 A V A I L A B I L I T Y - N T I S RUSSIA

IP

164 O

8394 Date December 1978 330000 Analytic Method for the Numerical Solution of the Integral

Transport Equation for a Homogeneous Cylinder. Milgram, M.S. NUCL. SCI. ENG., 68(3), 249-269 CANADA

8880 Date 1979 111110 330000 713000 Application of Integral Transport Theory with Linearly


Boehme, R. D O E - T R - 7 I ; KFK-2501 ( I N GERMAN) A V A I L A B I L I T Y - U S D O E TECHNICAL INFORMA-

TION CENTER, OAK RIDGE, TENN. GERMAN

9700 Date December 1979 111110 122110 330000 , M I C R O X - 2 : An Improved Two-Region Flux Spectrum

Code for the Efficient Calculation of Group Cross Sec-tions.

Mathews, D.; Koch, P. G A - A - 15009(VQL.l) AVA ILAB IL ITY -DEP. , NTIS, PC A09/MF A01 GEAC

9762 Date 1979 111110 330000 55i l'lo 795276 Improvements of the Integral Transport Theory Method. Kavenoky, A.; Lam-Hime, M.; Stankovski, Z. CONF-790402,VOL.11, P P . 7 - 5 5 - - 7 - 6 9 A V A I L A B I L I T Y - H C - - A N S V IRGINIA SECTION,


FRANCE

Description of Facilities


6809 Date 1978 010000 111110 410000 122200 511120 421140 770000

430000 Benchmark Neutron Fields for Reactor Dosimetry. Grundl, J.; Eisenhauer, C. IAEA-208, VOL.I, PP.53-104 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE

6827 Date 1978 010000 020000 111110 U :220 410000 Fast Neutron Standan' at the PTB. Wagner, S.R. IAEA-208, VOL.11, PP.15-27 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE GERMAN

6830 Date 1978 111110 020000 410000 421130 421140 511120 Spectral Characterization of the NISUS Neutron Field. Williams, J.G.; Hannan, A.H.M.A. IAEA-208, VOL.11, PP.63-76 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE ENGLAN

6831 Date 1978 111110 410000 421130 421140 511120 Spectrum Characterization and Threshold Reaction Rate

Measurements in the Neutron Field of VIPER. McTaggart, M.H. (Ed.) 1AEA-208, VOL.11, PP.77-88 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE ENGLAN

9763 Date 1979 111110 330000 719B00 794000 An Interface-Currents Integral Transport Model for £ Treating Doubly Heterogeneous, Multisystem Geome-

tries. Westfall, R.M.; Bjerke, M.A. CONF-790402,VOL.11, PP.7-71 - - 7 - 8 3 A V A I L A B I L I T Y - H C - - A N S V IRGINIA SECTION,

P.O.' MF,--

O A R N L o

BOX ° 1260, LYNCHBURG, VA. 24505; NTIS

sr /

6832 Date 1978 " 111110 421130 421140 410000 511120 Several Studies of Neutron Standard Field in the Fast

Source Reactor "YAYOI " . Sekiguchi, A.; Nakazawa, M.; Kosako, T.; Wakabayashi,

H.; Akiyama, M. IAEA-208, VOL.11, PP.89-106 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE <> JAPAN

165

6833 Date 1978 111110 421160 410000 540000 Thermal Neutron Standard Fields with the KUR Heavy

Water Facility. Kanda, K.; Kobayashi, K.; Shibata, T. IAEA-208, VOL.11, PP.107-116 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE JAPAN

6864 Date March 1978 111110 410000 421140 713000 7 70000 810000 Fission Product and Reactor Dosimetry Studies at Coupled

Fast Reactivity Measurements Facility. Harker, Y.D.; Rogers, J.W.; Millsap, D.A. TREE-1259; ENDF-266 A V A I L A B I L I T Y - N T I S $4.50 DOE

6834 Date 1978 111110 020000 410000 421140 511120 The Coupled Fast Reactivity Measurements Facility

(CFRMF). Rogers, J.W.; Harker, Y.D.; Millsap, D.A. IAEA-208, VOL.11, PP.117-176 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE EDGERT

6837 4 ' fca te 1978 111110 422130 410000 511120 Intercomparison of the Intermediate-Energy Standard

Neutron Fields at the NISUS and MOL-sigma sigma Facilities by Means of Absolute Fission Chambers.

Fabry, A.; Williams, J.G.; Hannan, A.H.M.A.; Azimi-Garakati i, D.


HOUSE BELGIU

6838 Date 1978 111110 410000 421140 511120 810000 Activation Foil Data for NISUS, MOL-s igma sigma and

235-U Fission Spectrum. Hannan,A.H.M.A.; Williams, J.G. IAEA-208, VOL.11, PP.209-225 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE ENGLAN

6843 Date 1978 111110 410000 422130 511120 Quality Control and Calibration of Minature Fission Cham-

bers by Exposure to Standard Neutron Fields. Application to the Measurement of Fundamental Inte-gral Cross Section Ratios.

Fabry, A.; Garlea, I. IAEA-208, VOL.11, PP.291-308 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE BELGIU

8112 Date 1978 010000 111110 111220 410000 423110 423120 423130

423135 423140 511120 An International Neutron Dosimetry Intercomparison. ICRU ICRU-27 A V A I L A B I L I T Y - I C R U PUBLICATIONS, P.O. BOX


o 8225 Date August 2, 1978

410000 430000 Determination of Continuous Gamma-Ray Spectra over

the Energy Range 0.1 to 8 MeV. Fuess, D.A.; Slaughter, D.R.; Strout, R.E.; Rueppel, D.W. UCRL-52513 A V A I L A B I L I T Y - N T I S L A L L 11

8247 Date November 1978 020000 410000 421160' Neutron Flux Monitoring and Data Analysis for Neutron

Standard Reaction Cross Sections. Wasson, O.A.; Schrack, R.A.; Lamaze, G.P. NUCL. SCI. ENG., 68(2), 170-182 NABS

8413 ' Date May 1978 010000 421200 410000 424000 DOE-Grand Junction Logging Model Data Synopsis. Mathews, M.A.; Koizumi, C.J.; Evans, H.B. GJBX-76(78) AVA ILAB IL ITY -DEP. , NTIS BENDIX

8414 Date May 1978 421200 410000 424000 Borehole Gamma-Ray Spectrometer for Uranium Explo-

ration. George, D.C.; Evans, H.B.; Allen, J.W.; Key, B.N.; Ward,

D.L.; Mathews, M.A. GJBX-82(78)

£> A V A I L A B I L I T Y - D E P . , NTIS BENDIX

166

8513 Date January 1978 112910 220000 410000 423210 The K F M , a Homemade yet Accurate and Dependable Fall-

out Meter. Kearny, C.H.; Barnes, P.R.; Chester, C.V.; Cortner, M.W. ORNL-5040 A V A I L A B I L I T Y - N T I S O A R N L

8733 Date February 1979 112120 410000 712000 863000 Safety Analysis Report for Packaging: The O R N L Tung-

sten-Shielded Cask. Addendum 1. Evans, J.H.; Mouring, R.W. O R N L / E N G / T M - 3 / A 1 A V A I L A B I L I T Y - N T I S 54.50 O A R N L

8523 Date December 1978 113100 410000 424000 870006 X - R a y Transmission/Scattering Technique for Thick-

ness-Independent Density Measurement. Giacomelli, E.J. Y-2166 A V A I L A B I L I T Y - N T I S UNCAR

8863 Date September 1978 111220 410000 The Rutherford Laboratory Spallation Neutron Source. Manning, G. CONF-780921, PP.829-847 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL ,


8595 Date 1977 111110 410000 421130 421120 430000 Neutron Spectrometry Techniques for the Energy Region

0.1 to 10 MeV. Werle, H.; Bluhm, H.; Fieg, G. EUR-5667E/F.PT.I, PP.209-220;



G E R M A N

8641 Date 1977 111110 410000 < Characteristics of H.F.R. Facilities. Tas, A.; Verspuy, C.A.; Zijp, W.L. EUR-5667E/F,PT.I I , PP.396-433;


T I O N S OF T H E EUROPEAN COMMUNITIES, BOITE POSTAL 1003 - LUXEMBOURG

NETHER

8726 Date May 1978 424000 410000 A Beta-Ray Thickness Gauge with 14-C Beta-Rays. Nonaka, I.; Sugai, I. I N S - J - 1 5 9 A V A I L A B I L I T Y - I N S T I T U T E FOR NUCLEAR

STUDY, UNIVERSITY OF TOKYO, T A N A S H I (JAPAN)

JAPAN

8870 Date September 1978 121100 410000 810000 Recent Advances in the Study of Some Neutron Threshold

Reactions. Qaim, S.M. CONF-780921, PP.1088-1107 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL ,


8910 Date 1979 410000 421130 430000 Neutron Spectrometry Using Scintillation Spectrometer and

Hydrogen-Filled Proportional Counters. Holman, M. ZJE-220 A V A I L A B I L I T Y - S K O D A WORKS, NUCLEAR

POWER CONSTRUCTION DEPART., INFORMA-T ION CENTRE, PLZEN - CZECHOSLOVAKIA

CZECHO

9047 i . . . Date December 1978 112760 410000 770000 A Technique to Compensate for Geometry-Induced Errors

in a Photon Irradiator Calibration. . Mulhern, O.R.; Hooker, C.D. ' STI /PUB -471 (VOL.2),PP.201 - 205;


ENERGY AGENCY, V IENNA (AUSTRIA) BANW

9051 113100 410000 760000

Date December 1978

167

Ionization-Chamber-Dependent Factors for Calibration of Megavoltage X - R a y and Electron Beam Therapy Machines.

Almond, P.R.; Mendez, A.; Behmard, M. STI/PUB-471(VOL.2), PP.271 -289;

CONF-771209-P2,PP.271 -289; A V A I L A B I L I T Y - I N T E R N A T I O N A L " ATOMIC

ENERGY AGENCY, V I E N N A (AUSTRIA) U - T X

9295 Date 1978 111110 410000 420000 511120 European Neutron Dosimetry Intercomparison Project

(ENDIP). Results and Evaluation. Broerse, J.J.; Burger, G.; Coppola, M. (Eds.) EUR-6004 A V A I L A B I L I T Y - D E P . , NTIS (U.S. SALES O N L Y ) NETHER

9052 Date December 1978 410000 750000 760000 A Simple Method of Energy Determination^ for Electron

Accelerators Used in Medicine. Liesem, H.; Pohlit, W. STI/PUB-471(VOL.2), PP.291 -300;

CONF-771209-P2,PP.291 -300; A V A I L A B I L I T Y - I N T E R N A T I O N A L ATOMIC


9367 Date September 1979 111110 410000 420000 511120 Calibration of Neutron Detectors in Radiation Protection. A

Report on the Karlsruhe Results of the European Neu-tron Dosimetry Intercomparison Program 1977/78.

Piesch, E.; Burgkhardt, B.; Hofmann, I. KFK-2847 A V A l L A B I L I T Y - K E R N F O R S C H U N G S Z E N T R U M

KARLSRUHE (F.R. GERMANY) GERMAN

9213 Date December 1978 020000 220000 410000 430000 The Organization and Operation of the Regional Calibration

Laboratory at Victoreen, Cleveland. Simon, W.E. STI /PUB-471(VOL. l ) , PP.241-249;

CONF-771209-P1, PP.241-249; A V A I L A B I L I T Y - IAEA VICTOR

9434 Date 1979 111110 410000 421140 719A00 I B R - 2 Reactor Physical Start-Up. The Results of Mea-

suring the I B R - 2 Leakage Neutron Spectrum. Arkhipov, V.A., et al. J INR-P13-12466 A V A I L A B I L I T Y - J O I N T INSTITUTE FOR

NUCLEAR RESEARCH, DUBNA RUSSIA

9231 Date Apri l 24, 1979 010000 020000 410000 511120 551120 Nuclear Criticality Experiments from 1943 to 1978, an

Annotated Bibliography: Volume 1, Main Listing. Koponen, B.L.; Wilcox,'T.P.; Hampel, V.E. UCRL-52769, VOL.1 A V A I L A B I L I T Y - N T I S L A L L

9488 Date 1979 010000 111220 210000 410000 717000 The Fusion Materials Irradiation Test Facility at Hanford. Pottmeyer, E.W,Jr. CONF-790125, PT.A, PP.463-465; J. NUCLEAR

M A T E R , 85 A N D 86, A V A I L A B I L I T Y - NORTH - H O L L A N D PUBLISH-


9232 Date April 24, 1979^ 010000 020000 410000 511120 551120 Nuclear Criticality Experiments from 1943 to 1978, an

Annotated Bibliography: Volume 2, Lookup Tables. Koponen, B.L.; Wilcox, T.P.; Hampel, V.E. UCRL-52769, VOL.2 A V A I L A B I L I T Y - N T I S L A L L ,

9737 Date M i d - A p r i l 1980 410000 Remodeling and Dosimetry on the Neutron Irradiation

Facility of the Musashi Institute of Technology Reactor for Boron Neutron Capture Therapy.

Aizawa, O.; Kanda, K.; Nozaki, T.; Matsumoto, T. NUCL. TECHNOLOGY, 48(2), 150-163 JAPAN u

168

Instruments - General Descriptions


6811 Date 1978 010000 420000 Remarks on Terminology and Symbols for Physical Quanti-

ties in Neutron Metrology. Wagner, S.R. iAEA-208 , VOL.1, PP. 141-143 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE G E R M A N

9003 Date 1979 010000 420000 Radiation Detection and Measurements. Knoll, G.F. BOOK A V A I L A B I L I T Y - W I L E Y PUB. U - M I

9031 Date July 1979 111210 220000 223000 420000 423140 717000 Neutron Personnel1 Dosimetry Considerations for Fusion

Reactors. Barton, T.P.; Easterly, C.E. O R N L / T M - 6 7 5 6 A V A I L A B I L I T Y - N T I S O A R N L


Energy Distributions in Nuclear Reactor Experiments. Yegorov, Yu.A.; Pankrat'yev, Yu.V. E R D A - T R - 1 2 5 , PP. 176-190 A V A I L A B I L I T Y - N T I S RUSSIA

0 o

8140 Date September 1, 1978 010000 111120 420000 424000 " A Review of the Delayed Fission Neutron Technique. Binney, S.E.; Scherpelz, R.I. NUCL. INSTRUM. METHODS, 154(3), 413-431 U' -OR

8505 Date 1978 010000 220000 420000 Instrumentation and Monitoring Methods for Radiation

Protection. NCRP NCRP-57 A V A I L A B I L I T Y - N C R P PUBLICATIONS, P.O. BOX


8506 Date 1978 112710 420000 610000 A Handbook of Radioactivity Measurements Procedures. NCRP NCRP-58 A V A I L A B I L I T Y - N C R P PUBLICATIONS, P.O. BOX


9049 Date December 1978 113100 420000 423300 A New Type of Standard Free-Air Chamber for High

Quantum Energies. Uotila, I.K. STI/PUB -471 (VOL.2),PP.229 -241;

CON F - 771209"- P2,PP.229 - 241; A V A I L A B I L I T Y - I N T E R N A T I O N A L ATOMIC

ENERGY AGENCY, V I E N N A (AUSTRIA) F INDLA

9050 i . . Date December 1978 112B00 420000 423210 Absorbed-Dose Determination with Ionization Chambers

in Electron and Photon Beams Having Energies Between 1 and 50 MeV.

« Johansson, K . -A . ; Mattsson, L.O.; Lindborg, L.; Svensson, H.

STI/PUB -471 (VOL.2),PP.243 - 270; CONF - 771209 - P2,PP.243 - 270;

A V A I L A B I L I T Y - I N T E R N A T I O N A L ATOMIC ENERGY AGENCY, V I E N N A (AUSTRIA)

SWEDEN

9063 Date June 1-15, 1979 010000 420000 Detectors in Nuclear Science. Part II. ° Bromley, D.A. (Ed.) NUCL. INSTRUM. METHODS, 162(1-3), 371-738 U - C T

0. >7

9166 Date May 1, 1979 010000 121100 121200 420000 Average Energy Required to Produce an Ion Pair. Wyckolf, H.O. I C R U - 3 1

169

A V A I L A B I L I T Y - I C R U PUBLICATIONS, P.O. BOX 30165, WASHINGTON, D.C. 20014

ICRU

9295 i.' Date 1978 111110 410000 420000 511120 European Neutron Dosimetry Intercomparison Project

(ENDIP). Results and Evaluation. Broerse, J.J.; Burger, G.; Coppola, M. (Eds.) EUR-6004 A V A I L A B I L I T Y - D E P . , NTIS (U.S. SALES O N L Y ) NETHER



Harrison, R.C. W W D NR.27 A V A I L A B I L I T Y - W E H R W I S S E N S C H A F T L I C H E

DIENSTSTELLE DER BUNDESWEHR FUR A B C - S C H U T Z , D 3042 MUNSTER, G E R M A N Y

G E R M A N „ o

9382 Date September 1979 111110 111210 111220 220000 420000 430000 European Workshop on Neutron Dosimetry for Radiation

Protection. Alberts, W.G.; Cosack, M.; Kluge, H.; Lesiecki, H.; Wag-

ner.,S.; Zil l, H.W. P T B - N D - 1 7 A V A I L A B I L I T Y - I N S T I T U T BERLIN DER PHYSI-

K A L I S C H - T E C H N I S C H E N BUNDESANSTALT, ABBESTRABE 2-12, 1000 BERLIN 10 (CHAR-LOTTENBURG). ISSN 0572-7170

G E R M A N

10040 , Date 1980 000000 420000 Radioactivity and Its Measurement - SI Units. 2nd Edition Mann, W.B. BOOK A V A I L A B I L I T Y - N E W YORK, PERGAMON PRESS,

1980 NABS

Instruments - Collimators




Piesch, E.; Burgkhardt, B.; Hofmann, I. KFK-2847 A V A I L A B I L 1 T Y - K E R N F O R S C H U N G S Z E N T R U M

KARLSRUHE (F.R. G E R M A N Y ) G E R M A N

9378 Date August 1978 220000 420000 Health Physics Instrument Manual. Gupton, E.D. O R N L - 332(REV.5) A V A I L A B I L I T Y - N T I S

\ O A R N L

6690 ". . Date February 1978 111220 122110 32A000 421000 521130 551,110 760000


Below 60 MeV. Wilson, W.B. L A - 7 1 5 9 - T A V A I L A B I L I T Y - N T I S LOASL

6948 .' Date August 1978 , 111210 421000 32A000 551110 795276 861000 Design Calculations for a 14-McV Neutron Collimator. Liilie, R.A.; Alsmiller, R.G.,Jr. O R N L / T M - 6 4 8 7 A V A I L A B I L I T Y - N T I S S4.50 O A R N L

i) o

q

170

I n s t r u m e n t s - E n e r g y S p e c t r a - N e u t r o n -e Li(n ,a) R e a c t i o n

CATEGORY NUMBER 421110 BELGIU

6814 Date 1978 010000 111110 421110 421120 421130 870092 In-Pile Neutron Spectrometry: Status. De Leeuw-Gieris, G.; De Leouw, S. IAEA-208, VOL.I, PP.197 - ?Ml A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE BELGIU

7087 Date January 1977 111110 421110 Neutron Spectrometry by Sandwich Surface Barrier Tech-

nique. Joneja, O.P. j;. NBS SPEC. PUB. 461, PP. 252-254 AVAILABIL ITY-SUPT. OF DOCUMENTS, GPO,


8592 Date 1977 111110 020000 421110 713000 ° Neutron Spectrometry Data in LMFBR Benchmark and

Standard Neutron Fields. De Leeuw-Gierts, G.;De Leeuw, S.; Helmick, H.H.; Rog-

ers, J.W. EUR-5667E/F,PT.I, PP.99-118; CONF-750935.PT.I,

PP.99-118 'XVAIUABIL ITY-OFFICE FOR OFFICIAL PUBLICA-


BELGIU

8594. . . . & i Date 1977 111110 421110 430000 Li thium-6 Neutron Spectrometry In-Core. De Leeuw-Gierts, G.;De Leeuw, S. EUR-5667E/F,PT.I, PP.176-208;

CONF-750935,PT.I, PP.176-208 AVA ILAB IL ITY -OFF ICE FOR OFFICIAL PUBLICA-


8619 Date 1977 111110 421110 540000 Flux Depression and the Absolute Measurements of the

Thermal Neutron Flux Density. Bensch, F. EUR-5667 E/F,PT.I, PP.738-746;

CONF-750935.PT.I, PP.738-746 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


AUSTRI


trometry. De Leeuw-Gierts, G.; De Leeuw, S.; Rogers, J.W.; John-

son, L.O. (

TREE-1358; BLG-525" A V A I L A B I L I T Y - N T I S $4.50 IDNEL

I n s t r u m e n t s - E n e r g y S p e c t r a - N e u t r o n -3 He(n ,p ) R e a c t i o n


6814 Date 1978 010000 111110 421110 421120 421130 870092 In-Pi le Neutron Spectrometry: Status. De Leeuw-Gierts, G.; De Lecuw, S. IAEA-208, VOL.1, PP.197-230 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE BELGIU

7045 Date October 20, 1976 111110 329000 421120 422140 430000 Monte Carlo Efficiency,,Predictions for a Portable 3 -He

Neutron Detector. „ =

O'Dell, A.A.

171

UCRL-52151 A V A I L A B I L I T Y - N T I S L A L L

7122 : Date July 1976 111110 329000 421120 430000 511120 810000 Matrix Method of Analyzing Spectra of Neutrons Measured

with He**3-Spectrometer in Shield Materials. Yegorov, Yu.A.; Zharkov, V.P.; Orlov, Yu.V. ERDA-TR-125 , PP. 225-230 A V A I L A B I L I T Y - N T I S RUSSIA

7123 Date July 1976 111110 32£000 42) 120 430000 511120 810000 Calculation of Instrument Line Form for He**3-Neutron

Spectrometer by Monte Carlo Method. Yegorov, Yu.A.; Zharkov, V.P.; Orlov, Yu.V. E R D A - T R - 1 2 5 , PP. 231-239 A V A I L A B I L I T Y - N T I S RUSSIA


0.1 to 10 MeV. Werle, H.; Bluhm, H.; Fieg, G. EUR-5667E/F,PT.I, PP.209-220;

CONF-750935';PT.I, PP.209-220 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-

TIONS OF CTHE EUROPEAN'COMMUNIT IES, BOITE POSTAL 1003 - LUXEMBOURG

G E R M A N

I n s t r u m e n t s - E n e r g y S p e c t r a - N e u t r o n -P r o t o n - R e c o i l P r o c e s s ( inc lud ing

s c in t i l l a t i on ) CATEGORY NUMBER 421130

6517 Date April 16, 1975 111220 421130 430000 521230 522230 853100 861000 Time-Dependent'Measurements of Fast-Neutron and ,

Secondary Gamma-Ray Transport Through a Thick Concrete and Steel Shield. Final Report.

Young, J.C.; Harris, L.,Jr.; Bryan, D.E.; Lurie, N.A.; Stein-man, D.K.; Friesenhahn, S.J.; Gober, W.E.; Schanzler, L.

IRT-8025-723 (

A V A I L A B I L I T Y - I N S T R U M E N T A T I O N RESEARCH TECHNOLOGY, 7650 CONVOY COURT, P.O. BOX 80817, SAN DIEGO, CALIFOR-N I A 92138)

IRT

6810 Date 1978 010000 210000 421130 42U40 511120 719A00 861000 Power Reactor Pressure Vessel Benchmarks. Rahn, F.J. IAEA - 208, VOL.1, PP. 105 - 140 <> A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING- )

HOUSE EPRI

6814 Date 1978 010000 111110 421110 421120 421130 870092 In-Pi le Neutron Spectrometry: Status. De Leeuw-Gierts, G.; De Leeuw, S. IAEA-208, VOL.1, PP.197-230 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE BELGIU

6830 .--f-:1. Date 1978 111110 020000 410000 421130 421140 511120 Spectral Characterization of the NISUS Neutron Field. Williams, J.G.; Hannan, A.H.M.A. IAEA-208. VOL.11, PP.63-76 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE ENGLAN

683 1 Date 1978 111110 410000 421130 421140 511120 Spectrum Characterization and Threshold Reaction Rate


HOUSE ENGLAN

{<

683 2 • .Date 1978 111110 421130 421140 410000 511120 Several Studies of Neutron Standard Field in the Fast

Source Reactor "YAYOI " . Sekiguchi, A.; Nakazawa, M.; Kosako, T.; Wakabayashi,


HOUSE JAPAN

6850 Date 1978 111110 421130 421140 430000 On the Possibility of Unfolding Simultaneously Data from

Multiple Foil, Proton Recoil and Other Neutron Spec-trometers by the S A N D - I I Type Unfolding Codes.

&

172 o

Najzer, M. !, IAEA-208, VOL.11, PP.411-422 Q » A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE YUGOSL

6853 Date February 1977 111110 421130 430000 870098 Unfolding Code System for the NE213 Liquid Scintillator. Sasamoto, N.; Tanaka, S. JAERI -M-6952 AVAILABIL ITY-DEP. , NTIS (U.S. SALES ONLY) JAPAN

6954 Date February 1978 11II10 111220 421130 421150 430000 511120 870098 Neutron Spectrum Measurements for Radiation Protection

Purposes. Slaughter, D.R.; Rueppel, D.W.; Fuess, D.A. UCRL-52,415 AVAILAB IL ITY-CAL IFORNIA UNIVERSITY,

LAWRENCE LIVERMORE LABORATORY L A L L

7086 Date January 1977 111500 112B00 421130 421200 430000 Utilization of Plastic Scintillator in the Measurement of

Uncharged Radiations. Sarkar, P.K.; Kirthi, K.N. NBS SPEC. PUB. 461, PP. 247-251 AVAILABIL ITY-SUPT. OF DOCUMENTS, GPO,


A V A I L A B I L I T Y - N T I S RUSSIA

7116 Date July 1976 111110 421130 521230 610000 810000 Investigation of the Field of Neutrons Reflected from

Screens with Various Thicknesses. Yegorov, Yu.A.; Zharkov, V.P.; Orlov, Yu.V. ERDA-TR-125, PP. 157-168 A V A I L A B I L I T Y - N T I S Q RUSSIA ,

U 0 7119 Date July 1976

111110 111220 421130 430000 Measurement of Different Forms of Neutron Energy Distri-

butions with Single-Crystal Scintillation Spectrometer. Trykov, L.A. ERDA-TR-125, PP. 191-198 A V A I L A B I L I T Y - N T I S RUSSIA


0.1 to 10 MeV. Werle, H.; Bluhm, H.; Fieg, G. EUR-5667E/F,PT.I, PP.209-220;



GERMAN

7110 Date July 1976 111110 421140 421130 521230 710000 719A00 Investigation of the Absolute Fluxes and Spectra of Fast

Neutrons Striking the Reactor Vessel in the Second Unit of the Novo-Voronezhskaya AES.

Barinov, A.L.; Vikin, V.A.; Glushchenko, A.I.; Yegorov, Yu.A.; Kovalenko, V.V.; Luk'yanov, M.A.; Orlov, Yu.V.; Razumovskiy, M.V.; Tsofin, V.L


8625 Date 1977 111110 421130 421140 511120 Neutron Intercomparisons on Nuclear Reactor in the

USSR. Vasilyev, R.D.; Grigoryev, E.I.; Jarina, V.P. EUR-5667E/F,PT.I, PP.823-847;



RUSSIA

7111. . ( ) Date July 1976 111110 421130 421*200 521230 522230 710000 719AOO

810000 Spectral Composition of the Radiation on the Premises of

the Novo-Voronezhskaya AES's Second Unit. Glushchenko, A.I.; Orlov, Yu.V.; Satarin, V.Ye. ERDA-TR-125 , PP. 119-126

'' 8744 Date January 1979 111210 421130 430000 Calculations of the Transverse Spatial Distribution of

NE102 Scintillation Light Made by Recoil Protons from Collimated 14-MeV Neutrons.^

Goosman, D.R. UCRL-52,651 0

173

A V A I L A B I L I T Y - L A W R E N C E LIVERMORE LAB., UNIVERSITY OF CALIFORNIA , LIVERMORE, CALIFORNIA

L A L L


Hydrogen - Filled Proportional Counters. Holman, M. ZJE-220 A V A I L A B I L I T Y - SKODA WORKS, NUCLEAR

POWER CONSTRUCTION DEPART., INFORMA-T I O N CENTRE, PLZEN - CZECHOSLOVAKIA

CZECHO

6658 Date March 1977 010000 421140 430000 511120 810000 Activation Detectors for Neutron Flux and Spectrum Deter-

mination. Boot, S.J. AERE-R-8654 AVAILABIL ITY-H .M.S .O . PRICE POUND1.50; NTIS

(U.S. SALES O N L Y ) ENGLAN

6667 Date 1977 111110 421140 430000 810000 Foil Activation Dosimetry at Energies Below 1 MeV. Stallmann, F.W.; Kam, F.B.K. CONF-771036-5 A V A I L A B I L I T Y - D E P . , NTIS U - T N

9193 Date Apri l 27, 1978 111110 111210 421130 430000 312000 32A000 522130

793000 795254 830000 NE-213 Detector Perturbations to Measured and Calcu-

lated Neutron and Gamma-Ray Fluences in Liquid Air.

Scott, W.H,Jr.; Gritzner, M.L.; Albert, T.E.; Hagan, W.K.; Schanzler, L.

S A I - 7 8 - 6 4 8 - L J A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, INC.,

P.O. BOX 2351, 1200 PROSPECT ST., LA JOLLA, CALIFORNIA 92037

SCA

9399 Date October 1, 1979 329000 430000 421130 The Response Function of Organic Scintillators to Fast Neu-

trons. Anghinolfi, M.; Ricco, G.; Corvisiero, P.; Masulli, F. NUCL. INSTRUM. METHODS, 165(2), 217-224 I T A L Y

Ins t ruments - Energy Spect ra - Neutron -Threshold and Resonance Reactions


6535 Date February 1978 010000 421140 430000 Contributions to Few-Channel Spectrum Unfolding. Perey, F.G. O R N L / T M - 6267; ENDF-259 A V A I L A B I L I T Y - N T I S $6.00 O A R N L o



H , IV ; Dierckx, R.; Gold, R. CONF-771036-6 AVA ILAB IL ITY-DEP. , NTIS ARGONN

6808 Date 1978 010000 111110 122200 210000 421140 430000 511120

810000 Neutron Cross Sections for Reactor Dosimetry -^Review

Papers. Summary Report. Vlasov, M.F. (Ed.) IAEA-208, VOL.I, PP.1-49 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE IAEA

6809 Date 1978 010000 111110 410000 122200 511120 421140 770000

430000 Benchmark Neutron Fields for Reactor Dosimetry. Grundl, J.; Eisenhauer, C. IAEA-208, VOL.1, PP.53-104 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE

6810 Date 1978 010000 210000 421130 421140 511120 719A00 861000 Power Reactor Pressure Vessel Benchmarks. Rahn, F.J. IAEA-208, VOL.1, PP. 105-140

C

174

A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-HOUSE

EPRI

6816 Date 1978 111110 122310 421140 511120 810000 870092 870098 Ratios of Measured and Calculated Reaction Rates fur

Some Known Spectra. Zijp, W.L.; Nolthenius, H.J.; Baard, J.H. IAEA-208, VOL.I, PP.265-300 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE „ NETHER

6818 Date 1978 010000 122310 210000 421140 Remarks Concerning the Accurate Measurement of Differ-

ential Cross Sections for Threshold Reactions Used in Fast-Neutron Dosimetry for Fission Reactors.

Smith, D.L. IAEA-208, VOL.I, 321-351 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE ARGONNE


Used in Reactor Neutron Dosimetry. Vlasov, M. IAEA-208, V O L I , PP.353-360 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE AUSTRI '

6820 Date 1978 010000 111210 421140 Status of Some Activation Cross Sections for Reactor Neu-

tron Dosimetry in the Range 13-15 MeV. Vonach, H. IAEA-208, VOL.I, PP.361-373 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE AUSTRI

6824 Date 1978 010000 111110 421 140 430000 810000 Foil Activation Detectors - Some Remarks on the Choice

of Detectors, the Adjustment of Cross-Sections a'iid the Unfolding of Flux Spectra.

McCracken, A.K.; Packwood, A. IAEA-208, VOL.I, PP.431 -442 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE ""

E N G L A N

6829 Date 1978 111110 421140 511120 795112 795233 Comparison of Neutron Spectrum Unfolding Codes. Zijp, W.L.; Baard, J.H.; Nolthenius, H.J. IAEA-208, VOL.11, PP.37-62 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE NETHER


HOUSE ENGLAN

6831 Date 1978 111110 410000 421130 421140 511120 Spectrum Characterization and Threshold Reaction Rate


HOUSE ENGLAN

6832 Date 1978 U l l 10 421130 421140 410000 511120 Several Studies of Neutron Standard Field in the Fast

Source Reactor "YAYOl " . Sckiguchi, A.; Nakazawa, M.; Kosako, T.; Wakabayashi,


HOUSE JAPAN

6834 Date 1978 111110 020000 410000 421140 511120 ° The Coupled Fast Reactivity, Measurements Facility

(CFRMF). Rogers, J.W.; Harker, Y.D.; Millsap, D.A. IAEA-208, VOL.I I , PP.117-176 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE EDGERT

175

6838 Date 1978 111110 410000 421140 511120 810000 Activation Foil Data for NISUS, MOL-s igma sigma and

t 2 3 5 - U Fission Spectrum. Hannan, A.H.M.A. ; Will iams, J.G. I A E A - 2 0 8 , VOL.11, PP.209-225 A V A I L A B I L I T Y - I N I S M ICROFICHE CLEARING-

HOUSE E N G L A N

6846 Date 1978 111110 421140 430000 511110 795112 Comparison of Integral Cross Section Values of Several

Cross Section Libraries in the S A N D - I I Format. Zijp, W.L.; Nolthenius, H.J. IAEA-208 , VOL.11. PP.327-348 A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE N E T H E R

6839 Date 1978 111110 421140 511120 870098 Measurement of Average Cross Sections with Regard to the

Low and High Energy Part of the Cali fornium-252 Neutron Spectrum.

Mannhart, W. IAEA-208 , VOL.11,,PP-227-246 A V A I L A B I L I T Y - I N I S M ICROFICHE CLEARING-

HOUSE G E R M A N

6840 Date 1978 111110 421140 511120 810000 Spectrum Averaged Cross-Section Measurements in the

Fast Neutron Field of a Uranium Fission Plate. Najzer, M.; Rant, J. IAEA-208 , VOL.11, PP.247-260 A V A I L A B I L I T Y - I N I S M I C R O F I C H E CLEARING-

HOUSE, YUGOSL

6842 Date 1978 010000 020000 111110 421140 511120 Measurement and Evaluation of Threshold Reaction Cross

Sections in Standard Neutron Fields. ' ; Kimura, I.; Kobayashi, K.; Hayashi, Shu A.; Yamamoto, S.;

Gotoh, H.; Yagi, H. IAEA-208 , VOL.11, PP.265-290 A V A I L A B I L I T Y - I N I S M ICROFICHE CLEARING-

HOUSE ,." JAPAN

6844 Date 1978 111110 421140 03: 422130 03: 511120 Measuring a Few Integral Data in the Sigma Sigma Neutron

Field. Garlea, I.; Miron, C.; Lupu, M. ; Ilie, P.; Thurzo, A.; Stanica,

N.; Popa, F.; Fodor, G. I A E A - 2 0 8 , VOL.11, PP.309-320 A V A I L A B I L I T Y - I N I S M I C R O F I C H E CLEARING-

HOUSE R O M A N I

6847 Date 1978 111110 122110 421140 Comparison of D E T A N - 7 4 and E N D F / B - I V Cross Sec-

tion Data in 620 Groups. u Zijp, W.L.; Nolthenius, H.J.; Rieffe, H.Ch.

IAEA-208 , VOL.11, PP.349-373 A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE NETHER

6849 Date 1978 010000 111110 210000 421140 Cross-Section Requirements for Reactor Neutron Flux

Measurements from the User's Point of View. Mas, M. ; Lloret, R. IAEA-28 , VOL.11, PP.387-394 ( I N FRENCH) A V A I L A B I L I T Y - I N I S M I C R O F I C H E CLEARING-

HOUSE i ;

FRANCE

6850. . Date 1978 111110 421130 421140 430000 On the Possibility of Unfolding Simultaneously Data from

Multiple Foil, Proton Recoil and Other Neutron Spec- o trometers by the S A N D - I I Type Unfolding Codes.

Najzer, M. IAEA-208 , VOL.11, PP.411-422 A V A I L A B I L I T Y - I N I S M I C R O F I C H E CLEARING-

HOUSE YUGOSL o

6864 Date March 1978 111110 410000 421140 713000 770000 810000 Fission Product and Reactor Dosimetry Studies at Coupled


<P IT'

6899 Date October 1977 111110 122110 421140 430000 521230 719A00 '795112

795233 810000

Neutron Metrology in the L.F.R. Neutron Flux Density Spectrum in the Inner Graphite Reflector of the L.F.R.

Zsolnay, E.M. E C N - 7 7 - 1 3 4 (RESTRICTED DISTRIBUTION) A V A I L A B I L I T Y - S T I C H T I N G ENERGIEONDER-

ZOEK C E N T R U M N E D E R L A N D (ECN), VOORTZETTING V A N DE STICHTING REAC-TOR C E N T R U M (RCN), WESTERDUINWEG 3, PETTEN (NH) , T H E NETHERLANDS

NETHER

7110 Date auly 1976 111110 421140.421130 521230 710000 719A00 Investigation of the Absolute Fluxes and Spectra of Fast


Barinov, A.L.; Vikin, V.A.; Glushchenko, A.I.; Yegorov, Yu.A.; Kovalenko, V.V.; Luk'yanov, M.A.; Orlov, Yu.V.; Razumovskiy, M.V.; Tsofin, V.L

E R D A - T R - 1 2 5 , PP. 106-118 A V A I L A B I L I T Y - N T I S RUSSIA

7112 Date July 1976 111110 421140 721100 721200 719A00 853800 861000 Passage of Neutrons with Intermediate Energies Through

Shielding with Complex Irregularities. Bolya;,ko, V.V.; Sakharov, V.M.; Suvorov, A.P.; Kharizo-

menov, Yu.V. E R D A - T R - 1 2 5 , PP. 127-139 A V A I L A B I L I T Y - N T I S RUSSIA

7133 Date October 1977 111220 421140 430000 794000 Least-Squares Dosimetry Unfolding: The Program Stay'sl. Perey, E.G. O R N L / T M - 6 0 6 2 ; ENDF-254 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

a O

8096 Date September 1978 421140 430000 882000 Neutron Attenuation Due to Boron-10 Shields. (Tech.

Note) Harvey, J.T.; Meason, J.L.; Wright, H.L. NUCL. SCI. ENG., 67(3), 343-344 U - A R

8186 . Date 1976 111110 210000 421140 810000 ' Damage Model and Neutron Spectrometry Applied in Reac-

tor Steel Irradiation Programmes. '

Weise, L. A E D - C O N F - 7 6 - 5 5 6 - 0 0 8 ( I N GERMAN) A V A I L A B I L I T Y - I N I S G E R M A N

'' 8412 Date August 1977 421140 422110 430000 Nuclear Data Guide for Reactor Neutron Metrology. (Edi-

tion 1977) Zijp, W.L. ECN-77-104 .. A V A I L A B I L I T Y - S T I C H T I N G ENERGIEONDER-

ZOEK CENTRUM NEDERLAND (ECN), VOORTZETTING V A N DE STICHTING REAC-TOR CENTRUM, NEDERLAND (RCN), WESTERDUINWEG 3, PETTEN (NH)

NETHER

(f 8485 Date September 1978

111220 122100 421140 717000 795112 810000 210000 Extrapolated Neutron Activation Cross Sections for Dosim-

etry to 44 MeV. Greenwood, L.R. A N L / F P P / T M - 1 1 5 A V A I L A B I L I T Y - N T I S $4.50 ARGONN

8584 Date 1977 010000 111 110 421140 Proceedings of the First A S T M - E U R ATOM Symposium

on Reactor Dosimetry. Held at Petten(Holland), Sept.22-26, 1975.

Commission of the European Communities EUR-5667E/F,PT.I; CONF-750935.PT.I A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-

TIONS OF T H E EUROPEAN COMMUNIT IES, BOITE POSTAL 1003 - LUXEMBOURG $24.00

NETHER

8585 Date 1977 010000 111110 210000 421140 430000 713000 717000

719A00 719B00 795112 810000 ' 0

Neutron Environmental Characterization Requirements for Reactor Materials Development and Surveillance Pro-grams. ^

McElroy, W.N.; Bennett, R.A.; Johnson, D.L. -EUR - 5667E/F,PT.I, PP.1-26; CONF-750935,PT.I,

PP.1-26 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-'


WEE

/ 177

858 6 Date 1977 010000 111110 210000 421140 713000 719AOO 810000 Dosimetry Methods for Structural Material Irradiation in

the European Countries. Farinclli, 'J. EUR-56J7E/F,PT.I, PP.27-40; CONF-750935,PT.I, "



I T A L Y ' ~ '

858 7 . Date 1977 111110 210000 421140 719A00 861000 Influence of Neutron Dosimetry on Radiation Damage Con-

siderations in LWR Pressure Vessels. •Serpan, C.Z.,Jr. EUR-5667E/F,PT.I, PP.41-51; CONF-750935,PT.I,

PP.41-51 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL,PUBLICA-


NURC <5

8589 : Date 1977 111110 210000 421140 32A000 551110 810000 ., Neutron Energy Spectrum Determination for Irradiation

Damage Study of Reactor Structural Materials. Takeuchi, K.; Miura, T.; Yamaji, A. t|

EUR-5667E/F,PT.I, PP.63-73; CONF-750935,PT.I, PP.63-73

A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-TIONS OF THE EUROPEAN COMMUNITIES, BOITE POSTAL 1003 - LUXEMBOURG ,

JAPAN

8590 Date 1977 111110 010000 020000 421140 Standardization of Neutron Measurements on. Nuclear

R.eactors in the USSR. Vasilyev, R.D.; Grigoryev, E.I.; Doropheev, G.A.; Jarina,

V.P. o EUR-5667E/F,PT.I, PP.74-83; CONF-750935,PT.I,

PP.74-83 v ' A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


RUSSIA

Jt 8591 Date 1977 111210 210000 421140 430000 717000 521130.795254

793000-795112 810000 Investigation of Neutron Flux Spectral Measurement for

Controlled Thermonuclear Reactor Radiation Damage Studies. j •)

Odette, G.R. EUR-5667E/F,PT.I, PP.84-97; CONF-750935.PT.I,

PP.84-97 '-i-AVA1LABIL ITY-OFF ICE FOR OFFICIAL PUBLICA-


U - C A

8597 Date 19,77 010000 111110 421140 430000 795108 795112 795233 Review of Activation Methods for the Determination of

' Neutron Flux Density Spectra. Zijp, W.L. EUR-5667E/F.PT.I, PP.233-300;

CONF-75Q935,PT.I, PP.233-300 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


NETHER

0 , ° o"

8599 Date 1977 111110 111220 421140 430000 A New Method for'the Unfolding of Pulse Height Distribu-

tions from Continuous Energy Spectra. Najzer, M.; Pauko, M. EUR-5667E/F.PT.1, * PP.310-S21-/

CONF-750935,PT.I, PP.310-321 V A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL P U B L I C / ^


YUGOSL

8600 Date 1977 010000 111110 421140c430000 795108 795112 795233 Unfolding C odes for Neutron Spectra Evaluation Possibili-

ties .andj/Limitations. Dierckx, R.; Sangiust, V.

r , E U R - 5 6 6 7 E / F , P T . I , PP.322-350; CONF-7501535,PT.I, PP.322-350

A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-TIONS OF THE EUROPEAN COMMUNIT IES, BOITE POSTAL 1003 - LUXEMBOURG

ITALY

8601 Date 1977 -111110 421140 430000 794000 The Experimental Data Processing Program RADAK. McCracken, A.K.; Grimstone, M.J. EUR-5667E/F,PT.I, PP.358-374;

CONF-750935,PT.I, PP.358-374 = 0

A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-TIONS OF THE EUROPEAN COMMUNIT IES, BOITE POSTAL 10.03 - LUXEMBOURG .

ENGLAN

O o 178'

8604 Date 1977 111110 210000 421140 422130 430000 870092 870094 Fission Rate Measurements for Materials Neutron Dosime-

try in Reactor Environments. Grundl, J.; Eisenhauer, C. EUR-5667E/F,PT. l , PP.425-454;

CONF-750935.PT.I, PP.425-454 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA- "

TIONS OFixTHE EUROPEAN COMMUNIT IES, BOITE POSTAL 1003 - LUXEMBOURG

NABS

8605 Date 1977 111110 421140 422130 430000 870092 870094 Techniques de Fission. Bouchard, J.; Menessier, P. EUR-5G67E/F,PT.I, PP.476-497(IN FRENCH);

CONF-750935,PT.I, PP.476-497(IN FRENCH) A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


FRANCE K

8606 Date 1977 111110 210000 421140 422130 870092 870094 Specimen Fission Rate Estimation in the JMTR. Mizuho, M.; Oyamada, R.; Sezaki, K. EUR-5667E/F,PT.I, PP.498-523;

CONF-750935,PT.I, PP.498-523 A V A I L A B I L I T Y -OFF ICE FOR OFFICIAL PUBLICA-


JAPAN

8610 Date 1977 111110 210000 42.1140 Absolute Measurements of Neutron Induced Reaction

Rates. Murphy' M.F.; Sweet, D.W.; Taylor, W.H. EUR-5667E/F.PT.I , PP.560-578;



E N G L A N /V

8611 Date 1977 111110 421140 430000 870047 795112 Reactor Neutron Dosimetry in the Energy Region Between

0.1 and 1.0 MeV with Silver. Kondo, I. EUR - 5 667E/F,PT. I, PP.579-590;

CONF-750935,PT.I, PP.579-590

A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-T IONS OF T H E EUROPEAN COMMUNIT IES, BOITE POSTAL 1003 - LUXEMBOURG

J A P A N

8615 Date 1977 111110 423135 423250 421140 531000 532000 ^ Reactor Dosimetry Using T L D and Rh-Activation'Tech-

niques. b Gomaa,,M.A.; Sayed, A.M.; Eid, A.M.; El-Kolaly, A.M. EUR-5667E/F,PT.I , PP.623-632;


T IONS OF T H E EUROPEAN COMMUNIT IES, BOITE POSTAL 1003 - LUXEMBOURG

EGYPT

8625 : . . Date 1977 111110 421130 421140 511120 Neutron Intercomparisons on Nuclear Reactor in the

USSR. Vasilyev, R.D.; Grigoryev, E.I.; Jarina, V.P. EUR-5667E/F.PT.I , PP.823-847;


T IONS OF THE EUROPEAN COMMUNIT IES , ( ) BOITE POSTAL 1003 - LUXEMBOURG

RUSSIA

8629 Date 1977 111110 122100 210000 810000 421140 Differential Neutron Data for Reactor Dosimetry. Paulsen, A.; Magurno, B.A. EUR-5667E/F.PT.I I , t- PP.93-111;

CONF-750935,PT.II, PP.93- 111 v, A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-

T IONS OF T H E EUROPEAN COMMUNIT IES , BOITE POSTAL 1003 - LUXEMBOURG

BELGIU

8631. Date 1977 111110 421140 810000 870098 Measurements of Integral Cross Sections in the Californi-.

um-252 Fission Neutron Spectrum. Alberts, W.G.; Gunther, E.; Matzke, M.; Rassl, G. EUR-5667E/F,PT.I I ; PP.131-141;



G E R M A N

179'

8632 Date 1977 111110 421140 713000 719A00 870092 Intercomparison of Reactor Dosimetry Cross Sections Mea-

sured in a Thermal Reactor, in a Fast Reactor and with an Enriched Uranium Fission Plate. "

Kimura, I.; Kobayashi, K. EUR-5667E/F.PT.I I , PP.142-151;


TIONS OF THF, EUROPEAN COMMUNIT IES, BOITE POSTAL 1003 - LUXEMBOURG

JAPAN

8635 Date 1977 020000 111110 421140 551120 795209 810000 The Tapiro Fast Source Reactor as a Benchmark to Test

Activation Detector Cross Sections. Martini, M.; Belli, M. ; Sirito, M.F. EUR-5667E/F,PT.I I , PP.259-276;

CONF-750935;PT.II, PP.259-276 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


•ITALY

8636 Date 1977 II1110 020000 32AOOO 421140 511120 713000 810000 Fast Neutron Spectrum and Dosimetry Studies in the Cou-

pled Fast Reactivity Measurements Facility. Rogers, J.W.; Harker, Y.D.; Millsap, D.A. tt EUR-5667E/F,PT.I I , PP.277-295;



AEROJE

8637 Date 1977 111110 122110 421140 795112 Neutron Selfshielding of Activation Detectors Used in Spec-

trum Unfolding. V, Zijp, W.L.; Nolthenius, H.J. EUR-5667E/F,PT.I I , " PP.297-321;



NETHER

8638 Date 1977 111110 421140 430000 795112 Neutron Spectra in the STEK Facility; Determined with the

S A N D - I I Activation Technique. Zijp, W.L.; Nolthenius, H.J.; Baard, J.H.

EUR-5667E/F,PT.I I , PP.322-348; CONF-750935,PT.II, PP.322-348

A V A I L A B I L I T Y - OFFICE FOR OFFICIAL PUBLICA-T IONS OF T H E EUROPEAN COMMUNIT IES, BOITE POSTAL 1003 - LUXEMBOURG

NETHER ^

8639 Date 1977 111110 421140 430000 511120 795112 Comparison of S A N D - I I and RFSP-JUL Spectrum

Unfolding Codes for Several Neutron Spectra in the STEK Facility.

Fischer, A.; Nolthenius, H.J.; Zijp, W.L. EUR-5667E/F,PT.I I , PP.349-380;



NETHER

8640 Date 1977 111110 122110 421140 795112 >, Remarks on the Comparison of Cross Section l ibraries for

Neutron Metrology. Zijp, W.L.; Nolthenius, H.J.; Appelman, K.H. EUR-5667E/F, PT.II, " " PP.381-395;



NETHER

8642 Date 1977 111110 421140 Neutron Flux Density Spectra of Interest to Reactor Neu-

tron Metrology. Zijp, W.L.; Nolthenius, H.J.; RiefTe, H.Ch. < EUR-5667E/F,PT.II , PP.468-683; ,


TIONS OF THE EUROPEAN COMMUNIT IES , BOITE POSTAL 1003 - LUXEMBOURG

NETHER

8658 Date February 1979 111110 122310 210000 421140 430000 521130 810000

870098 >) Testing of ENDF/B Cross-Section Data in the Californi-

um-252 Neutron Benchmark Field. Mannhart, \V. ORNL/RSIC-42 , PP.119-133 A V A I L A B I L I T Y - N T I S GERMAN

180'

8659 Date February 1979 111110 122310 210000 421140 719A00 861000 795112



Guthrie, G.L.; Schmittroth, F.;.Simons, R.L.; Lippincott, E.P.; Oster, C.

O R N L / R S I C - 4 2 , PP.135-143 A V A I L A B I L I T Y - N T I S HANFOR

8672 Date February 1979 111110 122310 795254 795204 421140 861000 The Linearity Assumption in Adjustment Procedures. Yeivin, Y. O R N L / R S I C - 4 2 , PP.343-350 A V A I L A B I L I T Y - N T I S ISRAEL

Henry, H.F. NUCL. SCL ENG., 72(1), 65-74 U - I N

9574 '< Date August 1979 122100 123000 421140 794000 810000

' Nuclear Data Guide for Reactor Neutron Metrology. Part 1: Activation Reactions. (1979 Edition)

Zijp, W.L.; Baard, J.H. ''' E C N - 7 0 A V A I L A B I L I T Y - N E T H E R L A N D S ENERGY

RESEARCH F O U N D A T I O N ECN, P.O. BOX 1, 1755 ZG PETTEN (NH)', T H E NETHERLANDS

NETHER

I n s t r u m e n t s - Energy Spec t ra - Neut ron -Other Means


8675 Date February 1979 111110 122310 421140 430000 795112 , / r Influence of Cross - Section Structure on Unfolded Neutron

Spectra. Ertek, C.; Vlasov, M.F.; Cross, B.; Smith, P.M. O R N L / R S I C - 4 2 , PP.375-383 A V A I L A B I L I T Y - N T I S AUSTRI

0 8695 . Date June 1978

111110 210000 421140 521230 713000 810000 The Zero-Power Basis of Fast Reactor Dosimetry. Sanders, J.E. A E E W - R - 1183 A V A I L A B I L I T Y - U K A E A , A T O M I C ENERGY

ESTABLISHMENT, W I N F R I T H , DORCHESTER, DORSET, GREAT BR ITA IN

E N G L A N

8911 "r. Date 1978 „ 112710 122200 421140 810000 ^ Gamma-Ray Spectra of Neutron-Irradiated Activation

Detectors. Hogel, J. ZJE-230 r j

A V A I L A B I L I T Y - S K O D A WORKS, NUCLEAR POWER CONSTRUCTION DEPART., INFORMA-T I O N CENTRE, P L Z E N - CZECHOSLOVAKIA

CZECHO

o 9253 Date October 1979

421140 Neutron Spectra Determination by Resonance Reactions.

6954 Date February 1978 111110 111220 421130 421150 430000 511120 870098 Neutron Spectrum Measurements for Radiation Protection

Purposes. Slaughter, D.R.; Rueppel, D.W.; Fuess, D.A. UCRL-52,415 A V A I L A B I L I T Y - C A L I F O R N I A UNIVERSITY,

LAWRENCE L IVERMORE LABORATORY , L A L L


Energy Distributions in Nuclear Reactor Experiments. Yegorov, Yu.A.; Pankrat'yev, Yu.V. E R D A - T R - 1 2 5 , PP. 176-190 A V A I L A B I L I T Y - N T I S RUSSIA

7120 Date July 1976 11 1110 421150 511120 861000 870013 870022 Application of Hydrogen Spectrometer for Spectral Analysis

of Neutrons in Reactor Shield Materials Badyayev, V.V.; Yegorov, Yu.A.; Kulagin, V.A.;

Pankrat'yev, Yu.V. < E R D A - T R - 1 2 5 , PP. 199-206 A V A I L A B I L I T Y - N T I S RUSSIA

7127 Date July 1976 111110 112500 421150 511120 521230'853100 853200

853300 853400 853500 853600 853700

181'

Analysis of the Shielding Properties of Various Concretes. Veselkin, A.P.; Voskresenskiy, Ye.V.; • Yegorov, Yu.A.;

Pankrat'yev, Yu.V.; Piskunov, V.I.; Staurin, N.V. E R D A - T R - 1 2 5 , PP. 273-290 A V A I L A B I L I T Y - N T I S RUSSIA

8608 Date 1977 111110 210000 421150 Methodes Speciales Ut i l ises en Dosimetrie des Neutrons. Mas, P. s'v, EUR-5667E/F.PT.I , PP.536-549(IN FRENCH); „ CONF-750935.PT.I, PP .536-549(IN FRENCH)

A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-TIONS OF T H E EUROPEAN COMMUNITIES, BOITE POSTAL, 1003 - LUXEMBOURG

FRANCE

8609 Date 1977 111110 421150 Les Collectrons.

/'Passe, J.; Petitcolas, H.; Verdant, R. " EUR-5667E/F,PT.I , PP.550-559(IN FRENCH);

CONF-750935,PT.I. PP.550-559(IN FRENCH) A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-

TIONS OF T H E EUROPEAN COMMUNITIES, ^ fBOITE POSTAL 1003 - LUXEMBOURG

' FRANCE } -O K

9293 Date 1978 • 111110 220000 421150 511120 Evaluation of Results of the European Neutron Dosimetry


Hef, J. V EUR-5848,PP.899-915; CONF-770597,PP.899-915 A V A I L A 3 I L I T Y - O F P I C E J O R OFFICIAL PUBLICA-

TIONS OF THE!; EUROPEAN COMMUNITIES, BOITE POSTALEl.1003 - LUXEMBOURG ISBN

° 9 2 - 8 2 5 - 0 2 5 6 - 2 , NETHER

w a i; 9575 Date August 1979

122100 123000 421150 810000 Nuclear Data Guide for Reactor Neutron Metrology. Part

2: Fission Reactions. ,(1979 Edition) Zijp, W.L.; Baard, J.H. ECN-71 A V A I L A B I L I T Y - N E T H E R L A N D S ENERGY

RESEARCH FOUNDATION ECN, P.O. BOX 1, 1755 ZG PETTEN (NH) , THE NETHERLANDS

NETHER

Ins t rumen t s - Energy Spec t ra - Neut ron -Time of Flight


,,6833 Date 1978 11 i'l 10 421160 410000 540000 Thermal Neutron Standard Fields with the KUR Heavy

Water Facility. Kanda, K..; KobayasliiJC; Shibata, T. —-< IAEA-208, V'OL.II\PP:107- life n

A V A I L A B I L I T Y - I N I S MICROFICHE 'CLEARING-HOUSE

JAPAN

8247 Date November 1978 020000 410000 421160 Neutron Flux Monitoring and Data Analysis for Neutron

Standard Reaction Cross Sections. •-»- ' Wasson, O.A.; Schrack, R.A.; Lamaze, G.P. <> ^ NUCL. SCI. ENG., 68(2), 170-182 NABS o

8375 If. Date February 1978 111210 421160 329000 511120 861000 870022 Pulsed Sphere Measurements^ for Weapons and <Fusion

Reactor-Design. UCRL-52000 r 78 -2 , PP.9-14 A V A I LABIL ITY-DEP. , NTIS L A L L

Ins t ruments - Energy Spec t ra - Gamma-Ray


6742 Date June 1977 112760 421200 424000 870094 ^ Determination of the Isotopic Composition of Rlutonium by

Gamma-Ray Spectrometry. Banham, M.F. AERE-R-8737 Q „ A V A I L A B I L I T Y - D E P . , NTIS (U.S. SALES O N L Y ) ENGLAN

O ff


Thermal and Californium-252 Neutrons. Debertin, K. ., ° IAEA-208, VOL.11, PP.261-263 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE ^ l / '

182'

G E R M A N t) r,

6900 Date December 1977 421200 ' New Developments in Field Gamma-Ray Spectrometry, o Gogolak, C.V.; Mil ler, K.M. E M L - 3 3 2 A V A I L A B I L I T Y - N T I S $4.50 „ DOE

O

6944 Date May 1978 111110 112120 210000 421200 719BOO 810000 Distribution of Fission Products in Peach Bottom HTGR

Fuel Element F03-01. Dyer, F.F.; Wichner, R.P.; Mart in, W.J.; Fairchild, L.L. O R N L / T M - 5 9 9 6 A V A I L A B I L I T Y - N T I S $10.75•> O A R N L -

7046. . . . V Date October 1977 112120 421200 430000 870092 U

Fission-Product Energy Release for Times Following Ther-mal-Neutron Fission of 23*}*-U Between 2 and 14000 Seconds.

Dickens, J.K.; Emery, J.F.; Love, T.A.; McConnell, J.W.; Northcutt, K.J.; Peellc, R.W.; Weaver, H .

O R N L / N U R E G - 1 4 f i

A V A I L A B I L I T Y - N T I S $8.00 " O A R N L

7113 Date July 1976 1)1110 112500 421200 Capture Gamma-Radiation Yield from 'a-Layer of Iron for "

Neutrons Striking at an Angle. Degtyarev, S.F.; Repin, N.N. ; Sakovich, V.A.; Sakharov,

V.M.; Suvorov, A.P.; Tarasov, V.V. E R D A - T R - 1 2 5 , PP. 140-144 A V A I L A B I L I T Y - N T I S RUSSIA

0 7115 Date July 1976 112B00 421200 522210 610000 820000 870013 8"6i000

870082 " « v

Differential Characteristics of the Energy Albedo of Gamma-Quanta for Organic Mediums.

Viktorov, A.A.; Mashkovich, V.P. E R D A - T R - 1 2 5 , PP. 152-156 A V A I L A B I L I T Y - N T I S • RUSSIA "

8413. . ; Date May 1978 010000 421200 4! 0000 424000 DOE-Grand Junction Logging Model Data Synopsis. Mathews, M.A. f Koizumi, C.J.; Evans, H.B. GJBX-76(78) A V A I L A B I L I T Y - D E P . , N T I S . . B E N D I X . ,,

J

7086 Date January 1977 111500 112B00 421130 421200 430000 Utilization of Plastic Scintillator in the Measurement of

Unchanged Radiations. 0

Sarkar, P.K.; Kirthi, K.N. NBS SPEC. PUB. 46 I f PP.'" 247-1251 <0 # A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,'

W A S H I N G T O N , D.C. 20402 >, ' 0

I N D I A

7111 Date July 1976 111110 421130 421200 521230 522230 710000 719A00

810000 1

Spectral Composition of the Radiation on the Premises of the Novo-Voronezhskaya AES's Second Unit.

Glushchenko, A.I . ; Orlov, Yu.V.; Satarin, V.Ye. E R D A - T R - 1 2 5 , PP. 119-126 A V A I L A B I L I T Y - N T I S RUSSIA

' 8414 Date May 1978 421200 410000 424000 <J

Borehole Gamma-Ray Spectrometer for Uranium Explo-ration. v ^ — - — { J

George, D.C.; Evans, H.B.; Allen, J.W.; Key, B.NTfWard, D.L.; Mathews, M.A. ^

GJBX-82(78) '' * " A V A I L A B I L I T Y - D E P . , NT IS BENDIX I,

o V) 9 8881 . . D a t e 1979

111110 2400 112500 421200 522230 795065 795223 861000 870098 . °

, Measurement andii-Calculation of the Gamma-Fields Q Induced in Iron "by 252-Cf Fission Neutrons. Jiang, S.H. 0 t , D 0 E - T R - 7 2 ; KFK-2444 ( I N G E R M A N ) A V A I L A B I L I T Y - U S D O E T E C H N I C A L ^ INFORMA-

/J T ION.CENTER, OAK RIDGE, T E N N . G E R M A N

9328 Date February 1979 111110 112110 420000421200 511120-512120 810000 Measurements of the Free Field Radiation^Environment at

' the APRD Reactor.

0 ff y 183 i>

Schanzler, L.; Buchholz, F. W.; Kazi, A.H.; Heimbach, C.R.; Harrison, R.C.

W W D NR.27 AVAILABIL1TY-WEHRWISSENSCHAFTLICHE ,

DIENSTSTELLE DER BUNDESWEHR FUR ABC-SCHUTZ, D 3042 MUNSTER, GERMANY

G E R M A N

Ins t ruments - Flux - Neutron - Activation Techniques


f'i 8250... Date November 1978

422110 On Several Good Methods for Computing the Distortion

Factor Relevant to a Foil' Placed in an Exponentially Varying Flux.

Benoist, P.; Boffi, V.C.; Grandjean, P.; Kavenoky, A.; Moli-nari, V.G.; Siewert, C.E.; Spiga, G.

NUCL. SCL ENG., 68(2), 217-219 FRANCE

C

8412 Date August 1977 421140 422110 430000 Nuclear Data Guide for Reactor Neutron Metrology. (Edi-

tion 1977) Zijp, W.L. ECN-77-104" , . A V A I L A B I L I T Y - S T I C H T I N G ENERGIEONDER-

ZOEK CENTRUM NEDERLAND s ^ C N ) , , = ; ' VOORTZETTING V A N DE STICHTING REAC-

TOR CENTRUM, .NEDERLAND (RCN), ,, WESTERDUl^WEG 3, PETTEN (NH) °

NETHER, .

8428 ..j. . Date October 1978 111210 329000 32AOOO 4221U0 511120 870003 881000 Tri t ium Production in a Sphere of 6 - L i D Irradiated by

14-MeV Neutrons)1

Hemmendinger, A.; Ragan, C.E.; Shunk, E.R.; Ellis, A.N.; Anaya, J.M.; Wallace, J.M. " q

LA-7310 « .. . A V A I L A B I L I T Y - NTIS LOASL

8553 i>. Date February 1979 <> 111110 122310 422110 870098 Measurement and Calculation of Average Activation Cross - Sections in the Spontaneous Fission Neutron Field of

252-Cf. (Tech. Note) ' £-„. Mannhart, W.; Alberts,'W.G. NUCL^SCI. ENG., 69(2), 333-338

GERMAN

" 8617 Date 1977 111110 210000 422110 Neutron Fluence Measurements Applied to Reactor Materi-

als Irradiation. Schneider, W. EUR-5667E/ F,PT. 1, PP.649-674;

CONF-750935,PT.I, PP.649-674 A V A I L A B I L I T Y -OFFICE FOR OFFICIAL PUBLICA-


GERMAN

8618 Date 1977 111110 210000 422110 423250 532000 713000 810000

H I > Dosimetry Work in Connection with Irradiations in the High

Flux Materials Testing Reactor BR2. Debrue, J.;De Leeuw-Gierts, G.; De Leeuw, S.; Raedt, Ch.

de; Fabry, A.; Leenders, L.; Maene, N.; Menil, R. EUR-5667E/F,PT.I, PP.700-737;

"CONF-750935,PT.I, PP.700-737 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-

T I O N S OF THE EUROPEAN COMMUNITIES, BOITE POSTAL 1003 - LUXEMBOURG

FRANCE Q

8620 Date 1977 I I I I 1 0 210000 422110 810000 870041 ° Application de la Reaction 93-Nb (n,n') 93m-Nb a la

Dosimetric,des Irradiations de Materiaux. Lloret, R. EUR-5667E/F,PT.I, PP.747-756(IN FRENCH);



FRANCE

8621 Date 1977., 111110 210000 422110 810000 870041 Utilization of the Reaction 93 -Nb (n,n') 93m-Nb for Fast

Neutron Fluence Measurement. Hegedus, F. EUR - 5667E/F,PT.I, f i PP.757-762;

CONF-750935,PT.I, PP.757-762 AVAILAB IL ITY -OFFICE FOR OFFICIAL PUBLICA-

TIONS OF . THE EUROPEAN COMMUNITIES, BOITE POSTAL 1003 - LUXEMBOURG

SWITZ

184'

8622 Date 1977 /( 111110 210000 422110 861000

Vessel's Material Surveillance Program Fast Neutron (E greater greater than 1 MeV)'Flux Measurement.

Galliani, M.; Benatti, P.I.N.; Puliandri, P.I.A. EUR-5667E/F.PT.I , PP.763-777;



I T A L Y


in the 10 M W Research Reactor HIFAR. Hilditch, R.J.; Lowenthal, G.C. EUR-5667E/F,PT.I , PP.791-S07;,

CONF-750935,PT.I, PP.791 -807 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


AUSTRA

8756 Date March 1979 111110 422110 422150 Neutron Fluence Measurements with Solid-State Nuclear

Track Detectors: Results of a Comparative Study with Gold and Indium Foils.

Aframian, A. NUCL. TECHNOLOGY, 42(3), &J3-349 I R A N

9400 Date November 1979 122310 422110 795112 Integral Tests of Neutron Activation .Cross Sections in a

9-Be(d,n) Fields at E/sub d/=40 MeV. Greenwood, L.R.; Heinrich, R.R.; Saltmarsh, M.J.; Hari-

har, P. NUCL. SCL ENG., 72(2), 175-190 A R G O N N

o

O O

185

a

r

Instruments:-^,Flux - Neutron - B(n,a) React ion


ft

6710 - Date February 1978 111110 422120 326000 511120 820000 870098 Spatial Distribution Measurements' of Fission Neutrons in ,

Water as an,Oxygen Data Test (AWBA Development Program).

Green, L.; Ullo, J.J. W A P D - T M - 1 3 6 5 A V A I L A B I L I T Y - N T I S BETTIS

ft

<s Ins t ruments - Flux - Neutron - Fission

Process


6837 Date 1978 111110422130 410000 511120 Intercomparison of the>Intermediate-Energy Standard

Neutron Fields at the NISUS and MOL-s igma sigma Facilities by Means of Absolute Fission Chambers.

Fabry, A.; Williams, J.G.; Hannan, A.H.M.A.; Azimi-Garakani; D.


HOUSE BELGIU

nfber 7033 Date September 1976 111210 32A000 521230 422130 717000 717100 870003

870006 870092 793000 795254 Fission-Rate Distributions in Lithium and Hybrid Fusion

Blanket Assemblies. Maekawa, H.; Seki, Y. . CONF-760935-P3, PP. 883-894 / / A V A l LABI L IT Y - NTIS « JAPAN

8478 Date January 1979 422130 87 Qf)93 The Imporf'/nce of Subthreshold Fission Phenomena in Cer.^ ., . tain Applications of Fission ^.Threshold Detectors: An

Example of Neptunium-237 foFNondestructive Assay. (Tech. Note) " 1

Difilippo, F.C.; Ragan, G.L. NUCL. SCI. ENG., 69(1), 104-107 OARNL

'!) -8604. . . : Date 1977

111110 210000 421140 422130 430000 870092 870094 Fission Rate Measurements for Materials Neutron Dosime-

try in Reactor Environments. Grundl, J.; Eisenhauer, C. -EUR-5667E/F,PT.I, PP.425-454;



NABS <s> ft

ir



Fabry, A.; Garlea, I. IAEA-208, V,OL.II, PP.291-308 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE BELGIU

8605 Date 1977 111110 421140 422130 430000 870092 870094 Techniques de.Fission. Bouchard, j'.; Menessier, P. EUR-5667E /F .PT . I , PP.476-497(IN F R E N C H ) ;

CONF-750935,PT .I, PP.476-497(IN F R E N C H ) A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L PUBLICA-„ T I O N S O F T H E E U R O P E A N C O M M U N I T I E S ,

BOITE POSTAL 1003 - L U X E M B O U R G F R A N C E ^

186 ' f \

8606 Date 1977 111110 210000 421140 422130 870092 870094 Specimen Fission Rate Estimation in the JMTR. Mizuho, M.; Oyamada, R.; Sezaki, K.. EUR-5667E/F,PT.I , PP.498-523;

CONF-750935,PT t I , PP.498-523 A V A I LABI L IT Y - OFFICE FOR OFFICIAL PUBLICA-

TIONS OF T H E EUROPEAN COMMUNITIES, BOITE POSTAL 1003 LUXEMBOURG

JAPAN

V, ^ Ins t ruments - Flux - Neutron -

Moderation


7045 Date October 20,-1976 111110 329000 421120 422140 430000 Monte Carlo Efficiency Predictions for a Portable 3 - H e

Neutron Detector. O'Dell, A.A. UCRL-52151 A V A I L A B I L I T Y - N T I S L A L L

7124 Date July 1976 111110 422140 430000 521130 841000 Calculator of the Sensitivity of a Spherical Neutron Detec-

tor. Utkin, V.A. E R D A - T R - 1 2 5 , PP. 240-250 A V A I L A B I L I T Y - N T I S RUSSIA

8392 Date September 1, 1978 329000 422140 430000 794000 Absolute Neutron Flux Measurements Using an NE-110

Scintillation Counter. ') Renner, C.; Hi l l , N.W.; Morgan, G.L.; Rush, K.; Harvey,

• J - A - Q NUCL. 1NSTRUM. METHODS, 154(3), 525-533 O A R N L "

9045. . Date December 1978 II1110 111220 422140 795254 O Multi-Technique Characterization of Neutron Fields from

Moderatedv252-Cf and 238-PuBe Sources. Griffith, R.V.; Slaughter, D.R.; Patterson, H.W.; Beach,

J.L.; Frank, E.G.; Rucppel, D.W.; Fisher, J.C. STI /PUB-471 (VOL.2),PP. 167 r 188; (s

' CONF-771209-P2,PP. 167- 188; A V A I L A B I L I T Y - I N T E R N A T I O N A L ATOMIC

ENERGY AGENCY, V I E N N A (AUSTRIA)

L A L L ,

Ins t ruments - Flux - Neutron - Nuclear Track Detector

ir. CATEGORY NUMBER 422150

8756 Date March 1979 111110 422110^.422150 Neutron Fluence Measurements with Solid-State Nuclear

Track Detectors: Results of a Comparative Study with Gold and Indium Foils.

Aframian, A. NUCL. TECHNOLOGY, 42(3), 343-349 I R A N

W /J Ins t ruments - FIr.x - Gamma-Ray


>t 8971 Date January 23, 1979

112720 422200 424000 719A00 810000 Neutron Shielding Requirements for the Loft Densitome-

ters. ' 0

Wheeler, F.J.; McCracken, R.T. LTR-141 -97 AVA ILAB IL ITY -DEP. , NTIS IDNEL

i Ins t ruments - Dose Rate - Neutron - Ion

Chamber

CATEGORY NUMrtER 423110

6706 Date October 10, 1977 111210 329000 423110 511120 521230 830000 861000 Dosimetry Measurements External to a 10 Kiloliter Liq-

u id -A i r Vessel Containing a D - T Neutron Source. Tripler, D.J.; Goldberg, E.; Farley, W.E. UCRL-52334 '" 0

AVAILAB IL ITY -DEP. , NTIS l i A L L

0 8112 Date 1978

010000 111110 111220 410000 423110 423120 423130 423135 423140 511120 ' °

An International Neutron Dosimetry Intercomparison. ICRU & ICRU-27 A V A I L A B I L I T Y - I C R U PUBLICATIONS, P.O. BOX

30165^WASHINGTON, D.C. 20014 ,

ICRU JAPAN

Ins t ruments - Dose Ra te - Neutron Proport ional Counter

Tt


8112. Date 1978 010000 111110 111220 410000 423110 423120 423130

423135 423140 5lV'l20 An International Neutron Dosimetry Intercomparison. ICRU ICRU-27 <- )) A V A I L A B I L I T Y - I C R U PUBLICATIONS, P.O. BOX


Ins t ruments - Dose Ra te - Neutron -Scintillation Counter


8112 Date 1978 010000 111110 111220 410000 423110 423120 423130

423135 423140 511120 An International Neutron Dosimetry Intercomparison. ICRU ICRU-27 A V A I L A B I L I T Y - I C R U PUBLICATIONS, P.O. BOX


8112 Date 1978 010000 111110 111220 410000 423110 423120 423130

423135 423140 511120 An International Neutron Dosimetry Intercomparison., ICRU ICRU-27 A V A I L A B I L I T Y - I C R U PUBLICATIONS, P.O. BOX)

301.65, WASHINGTON, D.C. 20014 ICRU "

8378 Date August 1978 ' 423135 430000 The Responses of Some T L Albedo Neutron Dosimeters. Douglas, J.A.; Marshall, M. <J.S HEALTH PHYS., 35(2), 315-324 ENGLAN

8613 Date 19/77 111110 423135 423250 531000 532000 Application of Thermoluminescence Dosimeters for Nuclear

Heating Measurements of Gamma Rays and Neutrons. Tanaka, S.; Takeuchi, K.; Furuta, Y. EUR-5667E/F,PT.I, PP.599-610; "

CONF-750935.PT.I, PP.599-610 AV A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


JAPAN "

Ins t ruments - Dose Ra te - Neutron -Thermoluminescence (TLD)


a 6856 Date 1978

111110 2200,00 423135 521210 Neutron Response of a New, Albedo-Neutron Dosimeter. Blackstock, A.W.; Cortez, J^R.; Littlejohn, G.J.; Storm, E. L A - U R - 7 8 - 4 0 ; CONF-780110-8 A V A I L A B I L I T Y - D E P . , NTIS LOASL

7079 Date January 1977 111500 423135 Neutron Dosimetry by Thermoluminescence Dosimeter. Furuta, Y.; Tanaka, S. ° NBS SPEC. PUB. 461, PP. 209-218 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS,- GPO, * WASHINGTON, D.C. 20402 0

8615 Date 1977 111110 423135 423250 421140 531000 532000 Reactor Dosimetry Using TLD and Rh-Activation Tech-

niques. ° Gomaa, M.A.; Sayed, A.M.; Ei'd, A.M.; El-Kolaly, A.M. EUR-5667E/F,PT.I, PP.623-632;


TIONS OF THE EUROPEAN COMMUNIT IES, { f BOITE POSTAL 1003 - LUXEMBOURG

EGYPT ^

8649 Date October 1978 220000 223000 423135 423250 <• Radiation Dose to^Construction Workers at Operating


Endres, G.W.R.; Shipler, D.B. NUREG/CR-0426; PNL-2773 A V A I L A B I L I T Y - D t P . , NTIS PANL iy " v

tt

df

188'

8832 Date March 15, 1979 329000 423135 Monte Carlo Calculated Absorption Probabilities for Cylin-

drical and Rectangular T L D Probes in Isotropic Thermal Neutron Fluences.

Horowitz, Y.S.; Freeman, S.; Dubi, A. NUCL. INSTRUM. METHODS, 160(2), 313-315 ISRAEL


„ Nuclear Power Plant Sites. Vol.2. Appendices A - F. Final Report, Sept. 1975-Sept. 1978.

Endres, G.W.R.; Shipler, D.B. " N U R E G / CR - 0426, VOL.2; PNL-2773, VOL.2 A V A I L A B I L I T Y - N T I S S9.00 P A N L 0 „

In s t rumen t s - Dose Ra te - Neu t ron -Other

.as CATEGORY NUMBER 423140 ft

8047 Date May 1978 111110 423140 719A00 721200 Neutron Streaming Measurements at an 850-MWe Pres-

surized Water Reactor and Subsequent Shielding Recommendations.

Ritchie, J.C. H E A L T H PHYS., 34(5), 479-483 N U R C

In s t rumen t s - Dose Ra te - Gamma-Ray -Ion C h a m b e r '

CATEGORY NUMBER 423210 ,

6698 Date Apri l 1978 113100 220000 329000 423210 423250 553120 845000 An Evaluation of the Distribution of Absorbed Dose'in Child

Phantoms Exposed to Diagnostic Medical X-Rays. Chen, W.; Poston, J.W.; Warner, G.G. O R N L / T M - 5 9 3 3 • A V A I L A B I L I T Y - N T I S O A R N L

8513 Date January 1978 112910 220000 410000 423210 The KFM, a Homemade yet Accurate and Dependable Fall-

out Meter. ^ Kearny, C.H.; Barnes, P.R.; Chester, C.V.; Conner, M.W. ORNL-5040 A V A I L A B I L I T Y - N T I S l> O A R N L

9035 A . . . Date December 1978 020000 423210 Practical, Accurate Methods for Measuring the m-Values

of Ionizing Gases. Moriuchi, Y.; Katoh, A.; Takata, N.; Tanaka, R.; T&mura,

STI /PUB-471( VOL.2),PP.45 - 63; CONF-771209-P2,PP.45 - 63;

A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C ENERGY AGENCY, V I E N N A (AUSTRIA)

JAPAN o

8112 > : Date 1978 010000 111110 111220 410000 423110 423120 423130

423135 423140 511120 An International Neutron Dosimetry Intercomparison. ICRU I C R U - 2 7 /J o A V A I L A B I L L T Y - I C R U PUBLICATIONS, P.O. BOX


^ 9036 Date December 1978 <020000 423210 Dependence of the W-Va lue on the Atomic Number of

Heavy Ions. „ Varma, K IN. ; Baum, J.W. STI/PUB-471(VOL.2),PP.65-71;


ENERGY AGENCY, V I E N N A (AUSTRIA) BROOKH


Reactors. o Barton, T.P.; Easterly, C.E. O R N L / T M - 6 7 5 6 A V A I L A B I L I T Y - N T I S O A R N L

O

9037. . Date December 1978 020000 220000 423210 High-Energy Radiation Dosimetry: C sub lambda, C sub

E and Solid - Cavity Theory. Gregene, A.O. STI /PUB-471 (VOL.2),PP.73-80;

C O N F - 771209 -P2,PP.73 - 80;

0

189

A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C ENERGY AGENCY, V I E N N A (AUSTRIA) °

N I G E R I - ,', '•A

9039 Date December 1978 020000 220000 423210 430000 Wal l Effects in Gamma-Ray Dosimetry. Jarrett, R.D.; Brynjolfsson, A.; Wang, C.P. ST I /PUB-471 (VOL.2),PP.91 -102;

-4CONF-771209-P2,PP.91 - 102; " A V A I L A B I L I T Y - I N T E R N A T I O N A L , A T O M I C

/ / E N E R G Y AGENCY, V I E N N A (AUSTRIA) ARMY, " „ " U

9041 Date December 1978 112720 423210 430000 0

Calculation of the Fluence of Secondary Photons, Compton and Fluorescence, Generated by Attenuation in Thin Walls. 0

Janssens, A.; Eggermont, G.; Jacobs, R. STI/PUB-471(VOL.2),PP.123-136; o


ENERGY AGENCY, V I E N N A (AUSTRIA) BELGIU .

9050 Date December 1978 I12B00 420000 423210 Absorbed-Dose Determination with Ionization Chambers

in Electron and Photon Beams Having Energies Between 1 and 50 MeV. "

Johansson, K . - A . ; Mattsson, L.O.; Lindborg. L.; Svensson,

S T I / P U B - 4 7 l(VOL.2),PP.243-270; CONF-771209-P2,PP.243-270; 0

A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C ENERGY AGENCY, V I E N N A (AUSTRIA)

SWEDEN -o

Instruments - Dose Rate - Gamma-Ray -Scintillation Counter, ^ ^ ^


a 8831 Date March 15, 1979

423230 A Linear Response Photon Counter. Biswas, M.; Roy, S.C.; Ghose, A.M. NUCL. INSTRUM. METHODS, 160(2), 283-286 I N D I A <>

I n s t r u m e n t s Dose R a t e - G a m m a - R a y Othe r Q


7077 Date January 1977 112B00 423240 Q 'i Track Theory Applied to Physical, Chemical and Biological

Systems. 0

Sharma, S?C.; Katz, R. NBS SPEC. PUB. 461, PP. 183-187 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

WASHINGTON, D.C. 20402 U - N B ' J ' 0

7078 Date January 1977 010000 121200 220000 423240 " o Actual Problems in Photon Dosimetry. Regulla, D.F.; Drexler, G. v <• NBS^SPEC. PUB. 461, PP. 197-208 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

WASHINGTON, D.C. 20402 J G E R M A N f

U 8612 Date 1977 (11110 423240 531000 532000 810000 0 Dosimetry Methods for Structural Materials: Nuclear Heat-

ing. Boyd, A.W. EUR-5667E/F,PT>.I, PP.591-598;'

CONF-750935,PT.I, PP.591-598 A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L PUBLICA-' T IONS OF T H E EUROPEAN C O M M U N I T I E S ,

BOITE POSTAL 10,013 - L U X E M B O U R G C A N A D A " ^ 0

7070 Date January 1977 112720 423230 522130 Back-Scattering (Sky Shine) of Gamma Rays from a 650

Curie 60-Co Source by Infinite Air. Swarup, J.; Ganguly, A.K. \ ) NBS SPEC. PUB. 461, PP. 124-128

^ A V A I L A B I L I T Y - S U P T . O F D O C U M E N T S , I-GPO, W A S H I N G T O N , D.C.. 20402"* V

I N D I A

\ o,

9040 Date December,1978 112720 423240 430000 <= Correction Factors in Gamma-Ray Dosimetry. Brynjolfsson, A.; Wang, C.P.; Massoud, E. STI /PUB - 471 (VOL. 2),PP. 103 -122;

C O N F - 771209 -P2,PP. 103 -122;° * A V A I L A B I L I T Y - I N T E R N A T I O N A L v A T O M I C

ENERGY AGENCY, V I E N N A (AUSTRIA ) A R M Y

190

Ins t rumen t s - Dose Ra te - Gamma-Ray -Thermoluminescence (TLD)


6566. . . .(( Date September 15, 1977 423250 853100

nerete Shieldi itoring Post to Reduce Background Interference.

Weng, P.i.HsuJJT NUCL. INSTRUM. METHODS, 145(3), 433-435 C H I N A

6698 Date Apri l 1978 '-J

113100 220000 329000 423210 423250 553120 845000 An Evaluation of the Distribution of Absorbed Dose in Child

Phantoms Exposed to Diagnostic Medical X-Rays. Chen, W.; Poston, J.W.; Warner, G.G. O R N L / T M - 5 9 3 3 A V A I L A B I L I T Y - N T I S O A R N L

6707 Date October 13, 1977 112720 112730 112750 423250 Gamma-Ray Dosimetry Errors with TLDs. Grahan, C.L.; Homann, S.G. UCRL-80133; CONF-771209-3 A V A I L A B I L I T Y - D E P . , NTJ.S L A L L ^

7080 Date January 1977 112B00 423250 Effect of Heat Treatments on Thermoluminescencc of Pure

A1203. Basu, A.S.; Ganguly, A.K. NBS SPEC. PUB. 461, PP. 219-221 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


7081 Date January 1977 112B00 423250 Thcrmoiuminescence Mechanisms in Lithium Fluoride. Kathuria, S.P.; Bapat, V.N.; Sunta, C.M.; Jain, V.K. NBS SPEC. PUB. 461, PP. 222-226 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


7082 Date January 1977 112B00 423250 Thermoluminescence Response of LiF to Gamma Rays.

6 Jain, V.K.; Kathuria, S.P. NBS SPEC. PUB. 461, PP. 227-230 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

WASHINGTON, D.C. 20402 IND IA

7083 Date January 1977 112B00 423250 " Change in T L Sensitivity of Quartz Due to Stress. David, M.; Ganguly, A.K. NBS SPEC. PUB. 461, PP. 231-233 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


7084 Date January 1977 112B00 423250 E S R - T L Correlation Studies in CaSO\SUB4 (RE) Phos-

phors. Nambi, K.S.V. NBS SPEC. PUB. 461, PP. 234-237 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


7114. Date July 1976 112500 423250 32AOOO 511110 512210 512220 853800

861000 Investigation of the Field of Capture Gamma-Radiation in

Solid Shielding. Bolyatko, V.V.; Gorbatov, V.S.; Reytblat, V.L.; Tkachenko,

V.V.; Khokhlov, V.F.; Tsypin, S.G. E R D A - T R - 125, PP. 145-151 A V A I L A B I L I T Y - N T I S RUSSIA

8613 Date 1977 111110 423135 423250 531000 532000 Application of Thermoluminescence Dosimeters for Nuclear

Heating Measurements of Gamma Rays and Neutrons. Tanaka, S.; Takeuchi, K.; Furuta, Y. EUR-5667E/F,PT.I, " PP.599-610;



JAPAN

8615 Date 1977 111110 423135 423250 421140 531000 532000 Reactor Dosimetry Using TLD and R h - Activation Tech-

niques. 15 ,, Gomaa, M.A.; Sayed, A.M.; Eid, A.M.; El-Kolaly, A.M.

191

EUR-5667E/F.PT.I, PP.623-632; t/'CC)NF-750935,PT.I, PP.623-632

A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-TIONS OF T H E EUROPEAN COMMUNITIES, BOITE POSTAL 1003 - LUXEMBOURG

EGYPT

Limitations of the Paired LiF TLD-600 , 700 Technique for the Estimation of Gamma Ray Doser i n " Mixed n-gamma Radiation Fields: The Effect of Thermal Neutrons.

Horowitz, Y.S.; Freeman, S.; Dubi, A. NUCL. INSTRUM. METHODS, 160(2), 317-320 ISRAEL

8616 Date 1977 111110 423250 532000 713000 TLD Gamma-Ray Energy Deposition Measurements in

the Zero Energy Fast Reactor Zebra. Knipe, A.D. EUR-5667E/F.PT.I, PP.633-647;

CONF-750935,PT.I, PP.633-647 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA- ,


ENGLAN

)!

9055 Date December 1978 112720 112730 112750 423250 Gamma-Ray Dosimetry Errors with Thermoluminescent

Dose Meters. Graham, C.L.; Hormann, S.G. STI/PUB -471 (VOL.2),PP.335 -348;

CONF-771209 -P2,PP.335 - 348; AVA ILAB IL ITY - I N T E R N A T I O N A L ATOMIC

ENERGY AGENCY, V I E N N A (AUSTRIA) L A L L

8618 Date 1977 111110 210000 422110 423250 532000 713000 810000' Dosimetry Work in Connection with Irradiations in the High


de; Fabry, A.; Leenders,"L.; Maene, N.; Menil, R. EUR-5667E/F.PT.I, PP.700-737;



FRANCE

9292 Date 1978 111110 112110 423250 713000 Further Studies on the Mixed Field of Neutrons and Gam-

mas in a Fast Reactor, Using Solid State Dosimeters. Scarpa, G.; Aceto, A.; Moscati, M.; Furetta, C. EUR-5848,PP.737 - 746; C O N F - 770597,PP.737 -746 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


ITALY

8649 Date October 1978 220000 223000 423135 423250 Radiation Dose to Construction Workers at Operating


Endres, G.W.R.; Shipler, D.B. NUREG/CR-0426; PNL-2773 A V A I L A B I L I T Y - D E P . , NTIS PANL

8828 Date February 1979 122200 423250 220000 845000 Dosimetry of Very Low Energy Photons. Reddy, A.R.; Mehta, S.C. HEALTH PHYSICS, 36(2), 175-182 INDIA

8833 Date March 15, 1979 423250


Nuclear Power Plant Sites. Vol.2. Appendices A - F. Final Report, Sept. 1975-Sept. 1978.

Endres, G.W.R.; Shipler, D.B. NUREG/CR-0426, VOL.2; PNL-2773, VOL.2 A V A I L A B I L I T Y - N T I S S9.00 PANL


112940 423250 Measurement of the Gamma Dose Rate Distribution in a

Spent Fuel Assemby with.a Thermoluminescent Detec-tor.

Ohno, A.; Matsuura, S. NUCL. TECHNOLOGY, 47(3), 485-493 JAPAN

192'

In s t rumen t s - Dose Ra te - X-Ray


9048.11 Date December 1978 113100 430000 423300 General Cavity Theory in the Dosimetry of X - Rays: Exper-

imental Study with a High-Pressure Chamber. Janssens, A.; Eggermont, G.; Jacobs, R. STI /PUB - 471 (VOL. 2),PP.207 - 228;

CONF - 771209 - P2.PP.207 - 228; A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C

ENERGY AGENCY, V I E N N A ( A U S T R I A ) BELGIU

7088 Date January 1977 112760 424000 Role of High Resolution Ge(Li) Detector in Trace Element

Study in Water Activated with Thermal Neutrons. Chatterjee (DAS), J.M.; Peeters, E.; Castiaux, M.A. NBS SPEC. PUB. 461, PP. 255-256 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

W A S H I N G T O N , D.C. 20402 BELGIU

8140 Date September 1, 1978 010000 111120 420000 424000 A Review of the Delayed Fission Neutron Technique. Binney, S.E.; Scherpelz, R.I. N U C L . I N S T R U M . METHODS, 154(3), 413-431 U - O R

9049 Date December 1978 113100 420000 423300 A New Type of Standard Free-A i r Chamber for High

, Quantum Energies. Uotila, I.K. STI /PUB - 4 71 (VOL.2),PP.229 - 241;

CONF-771209-P2.PP.229-241; A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C

ENERGY AGENCY, V I E N N A (AUSTRIA) F I N D L A

9053.. Date December 1978 113100 423300 430000 Effet du-.Rayonnement Diffuse sur le Rapport des Doses

Absorbees Derivees de Mesures d'lonisation et Obtenues par Dosimetre de Fricke.

Garsou, J.L. STI /PUB-47KVOL.2) ,PP.301-316;

C O N F - 771209 - P2,PP.301 - 316; A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C

ENERGY AGENCY, V I E N N A (AUSTRIA) B E L G I U M

Density, Wate r Content, Non-Destruct ive Tes t ing - Radiat ion Methods


. 8413 Date May 1978 010000 421200 410000 424000 DOE-Grand Junction Logging Model Data Synopsis. (

Mathews, M.A.; Koizumi, C.J.; Evans, H.B. ' > GJBX-76(78) A V A I L A B I L I T Y - D E P . , NTIS B E N D I X

8414 Date May 1978 421200 410000 424000 Borehole Gamma-Ray Spectrometer for Uranium Explo-

ration. i George, D.C.; Evans, H.B.; Allen, J.W.; Key, B.N.; Ward,

D.L.; Mathews, M.A. GJBX-82(78) A V A I L A B I L I T Y - D E P . , NTIS B E N D I X

8523 Date December 1978 113100 410000 424000 870006 X - R a y Transmission/Scattering Technique for Thick-

ness-Independent Density Measurement. Giacomelli, E.J. Y -2166 A V A I L A B I L I T Y - N T I S U N C A R

6742 Date June 1977 112760 421200 424000 870094 Determination of the Isotopic Composition of Plutonium by

Gamma-Ray Spectrometry. Banham, M.F. A E R E - R - 8 7 3 7 A V A I L A B I L I T Y - D E P . , NT IS (U.S. SALES O N L Y ) E N G L A N

8726 Date May 1978 424000 410000 A Beta-Ray Thickness Gauge with 14-C Beta-Rays. Nonaka, I.; Sugai, I. I N S - J - 1 5 9 A V A I L A B I L I T Y - I N S T I T U T E FOR N U C L E A R

STUDY, U N I V E R S I T Y OF TOKYO, T A N A S H I (JAPAN)

J A P A N

193'

8856 Date September 1978 010000 111110 329000 424000 430000 810000 Nuclear Data in the Design of Neutron Probes for Borehole

Logging. Sanders, L.G. CONF-780921, PP.642-647 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,


9531 Date February 1979 424000 711100 719B00 Design and Evaluation of a Nondestructive Fissile Assay

Device for HTGR Fuel Samples. McNeany, S.R.; Knoll, R.W.; Jenkins, J.D. O R N L / T M - 6 6 1 0 A V A I L A B I L I T Y - N T I S $4.50 O A R N L ! '

8971 Date January 23, 1979 112720 422200 424000 719A00 810000 Neutron Shielding Requirements for the Loft Densitome-

ters. $ Wheeler, F.J.; McCracken, R.T. L T R - 1 4 1 - 9 7 A V A I L A B I L I T Y - D E P . , N T I S I D N E L

& 9145,. . -Date September 1979

424000 " " ' , F

Neutron Gauge for Measurement of High Void Fraction in Water-Steam Mixtures.

Frazzoli, F.V.; Magrini, A. NUCL . TECHNOLOGY, 45(2), 177-182 I T A L Y

9260 ': Date July 1979 112760 421200 424000 711100 870094 870095 , A Nondestructive Assay System for Use in Decommission-

ing a Plutonium-Handling Facility. Roche, C.T.; Vronich, J.J.; Bellinger, F.O.; Perry, R.B. A N L - 7 9 - 6 0 A V A I L A B I L I T Y - A R G O N N E N A T I O N A L ' L A B O R A -

TORY, ILL. A R G O N N

9271 Date May 1979 424000 870094 Nuclear Data for Nuclear Material Safeguards. Lemley, J.R. BNL-50991,PP.297-303; CONF-781174,PP.297-303 A V A I L A B I L I T Y - N T I S

' BROOKH

9371 Date September 1979 111220 424000 719A00 Use of Sealed Tube Neutron Generators for Verification of

L W R Fuel Assemblies. Lee, D.M. L A - 7 9 9 6 - M S ' A V A I L A B I L I T Y - N T I S LOASL

10000 Date August 1980 111110 329000 424000 719A00 795154 An Analysis of Ex-Core Detector Response to

Core-Water Level Using Monte Carlo Techniques. Cacciapouti, R.J.; Lucier, R.D.; Harris, D.R.; Napolitano,

D. O R N L / R S I C - 4 4 , PP.197-201 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 YAAEC

10073 Date July 1980 112760 424000 870092 87,0088' Estimates of Uranium Content and Radon Flux for Uranium I , s

Mine Dumps Based OJI Borehole Radioactivity Logs. Riedel, D.W. ' " ~ NUREG/CR -1549 A V A I L A B I L I T Y - N T I S NUUS

Analysis - Energy Spec t r a Unfolding and Detector Response


6341 Date December 15, 1977 430000 Gamma-Ray Pulse-Height Response of an Ne-213 ' '

Scintillation Detector. " Ingersoll, D.T.; Wehring, B.W. NUCL. INSTRUM. METHODS, 147(3), 551-562 U - I L

6463 Date Dec. 1977 122310 870041 870098 430000 794000 Integral Tests of Niobium Cross Sections Through Simulta-




194'

6517 Date Apr i l 16, 1975 111220 421130 430000:521230 522230 853100 861000 Time-Dependent Measurements of Fast-Neutron "and


Young, J.C.; Harris, L.,Jr.; Bryan,<D.E.; Lurie, N.A.; Stein-man, D.K.; Friescnhahn, S.J.; Gober, W.E.; Schanzler, L.

I R T - 8 0 2 5 - 7 2 3 A V A I L A B I L I T Y - I N S T R U M E N T A T I O N

RESEARCH T E C H N O L O G Y , 7650 C O N V O Y COURT, P.O. BOX 80817, SAN DIEGO, CAL IFOR-N I A 92138

I R T

6535 Date February 1978 010000 421140 430000 Contributions (to Few-Channel Spectrum Unfolding.; Perey, F.G. O R N L / T M - 6 2 6 7 ; E N D F - 2 5 9 A V A I L A B I L I T Y - N T I S S6.00 O A R N L /1

6658 Date March 1977 010000 421140 430000 511120 810000 ( J Activation Detectors for Neutron Flux and Spectrum Deter-

mination. Boot, S.J. A E R E - R - 8 6 5 4 A V A I L A B I L I T Y - H M . S . O . PRICE POUND1.50; NT IS


6667 Date 1977 111110 421140 430000 810000 Foil Activation Dosimetry at Energies Below 1 MeV. Stallmann, F.W.; Kam, F.B.K. C O N F - 7 7 1 0 3 6 - 5 A V A I L A B I L I T Y - D E P . , N T I S U - T N

6748 Date March 1978 010000 430000 Generalized Least-Squares for Data Analysis. Schmittroth, F. H E D L - T M E - 7 7 - 5 1 A V A I L A B I L I T Y - N T I S H A N F O R it-

6808 Date 1978 010000 111110 122200 210000 421140 430000 511120

810000 Neutron Cross Sections for Reactor Dosimetry - Review

Papers. Summary Report. Vlasov, M.F. (Ed.) I A E A - 2 0 8 , VOL.1, PP.1 - 4 ? A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

H O U S E I A E A

6809 Date 1978 010000 111110 410000 122200 511120 421140 770000

430000 Benchmark Neutron Fields for Reactor Dosimetry. Grundl, J.; Eisenhauer, C. ,, I A E A - 2 0 8 , VOL.1, PP.53-104 A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE

6812 Date 1978 010000 430000 122310 795112 Spectral Characterization by Combining Neutron Spectros-

copy, Analytical Calculations, and Integral Measurements.

McElroy, W.N.; Gold, R.; Lippincott, E.P.; Fabry, A.; Rob-erts, J.H.

I A E A - 2 0 8 , VOL.1, PP.147-181 A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE H A N F O R

6696 Date Apr i l 1978 111110 112120 221000 532000 422200 430000 794000


mal -Neut ron Fission of 239-Pu Between 2 and 14000 Seconds.



6824 Date 1978 010000 111110 421140 430000 810000 Foil Activation Detectors - Some Remarks on the Choice


McCracken, A.K.; Packwood, A. I A E A - 2 0 8 , VOL.1, PP.431-442 A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE E N G L A N

195'

6846. ; Date 1978 111110 421140 430000 511110 795112 Comparison of Integral Cross Section Values of Several

Cross Section Libraries in the S A N D - I I Format. Zijp, W.L.; Nolthenius, H.J. IAEA-208 , VOL.11, PP.327-348 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE NETHER

6850 Date 1978 111110 421130 421140 430000 On the Possibility of Unfolding Simultaneously Data from

ft Multiple Foil, Proton Recoil and Other Neutron Spec-trometers by the S A N D - I I Type Unfolding Codes.

Najzer, M. ' IAEA-208 , VOL.11, PP.411-422 A V A I L A B I L I T Y - I N I S MICROFICHE ,CLEARING-

HOUSE YUGOSL \:>

6853 Date February 1977 111110 421130 430000 870098 Unfolding Code System for the NE213 Liquid Scintillator. Sasamoto, N.; Tanaka, S. J A E R I - M - 6 9 5 2 //

.—V

A V A l LABILITY-DE7 : .1 , NTIS (U.S. SALES-ONLY) T JAPAN

- / 6954. Date February 1978 / /

111110 111220 421130 421150 430000 511120 8700p(8 Neutron Spectrum Measurements for Radiation Protection

Purposes. Slaughter, D.R.; Rueppel, D.W.; Fuess, D.A. UCRL-52,415 A V A I L A B I L I T Y - C A L I F O R N I A , UNIVERSITY,

LAWRENCE L IVERMORE LABORATORY „ L A L L

7045 Date October 20, 197$ 111110 329000 421120 422140 430000 Monte Carlo Efficiency Predictions for a Portable 3 - H e

Neutron Detector. ' O'Dell, A.A. -UCRL-52151 A V A I L A B I L I T Y - N T I S " " " L A L L

7046 '.' Date October 1977 112120 421200 430000 870092 Fission-Product Energy Release for Times Following Ther-

mal-Neutron Fission of 235 -U Between 2 and 14000 Seconds.

Dickens, J.K.; Emery, J.F.; Love, T.A.; McConnell, J.W.; Northcutt, K.J.; Peelle! R.W.; Weaver, H.


6893 Date 1977 020000 220000 430000 Radiation Protection Instrumentation Test and Calibration. Selby, J.M.; Larson, H.V.; Bartlett, W T . ; Mulhern, O.R.;

Fleming, D.M. CONF-771209-12; I A E A - S M - 2 2 2 / 0 6 A V A I L A B I L I T Y - D E P . , NTIS BANW

7086 Date January 1977 111500 112B00 421130 421200 430000 ° Utilization of Plastic Scintillator in the Measurement of

Uncharged Radiations. Sarkar, P.K.; Kirthi, K.N. NBS SPEC. PUB. 461, PP. 247-251 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

WASHINGTON, D.C. 20402 I N D I A '

6899 Date October 1977 111110 122110 421140 430000 521230 719AOO 795112

795233 810000 Neutron Metrology in the L.F.R. Neutron Flux Density

Spectrum in the Inner Graphite Reflector of the L.F.R. Zsolnay, E.M. . /J E C N - 7 7 - 1 3 4 (RESTRICTED DISTRIBUTION) A V A l L A B I L I T Y - S T I C H T I N G ENERGIEONDER-

ZOEK C E N T R U M N E D E R L A N D (ECN), VOORTZETTING V A N DE ST ICHTING REAC-TOR C E N T R U M (RCN), WESTERDUINWEG 3, PETTEN (NH) , THE N E T H E R L A N D S

NETHER

7119 Date July 1976 111110 111220 421130 430000 ' ' Measurement of Different Forms of Neutron Energy Distri-

butions with Single-Crystal Scintillation Spectrometer. Trykov, L.A. E R D A - T R - 1 2 5 , PP. (191-198 A V A I L A B I L I T Y - N T I S RUSSIA , <•

7122 Date July 1976 111110 329000 421120 430000 511120 810000 Matrix Method of Analyzing Spectra of Neutrons Measured

with He* *3-Spectrometer in Shield Materials.

I 196

Yegorov, Yu.A.; Zharkov, V.P.; Orlov, Yu.V. E R D A - T R - 1 2 5 , PP. 225-230 A V A I L A B I L I T Y - N T I S RUSSIA

7123 Date July 1976 111110 329000 421120 430000 511120 810000 Calculation of Instrument Line Form for He**3-Neutron

Spectrometer by Monte Carlo Method. Yegorov, Yu.A.; Zharkov, V.P.; Orlov, Yu.V. E R D A - T R - 1 2 5 , PP. 231-239 A V A I L A B I L I T Y - N T I S RUSSIA. ''

Fuess, D.A.; Slaughter, D.R.; Strout, R.E.; Rueppel, D.W. UCRL-52513 A V A I L A B I L I T Y - N T I S L A L L

8254 Date November 1978 122310 430000 794000 Development and Testing of Neutron Dosimetry Techniques

for Accelerator-Based Irradiation Facilities, o Greenwood, L.R.; Heinrich, R.R.; Kennerley, R.J.; Medrzy-

chowski, R. NUCL. TECHNOLOGY, 41(1), 109-128 ARGONN

7124v-v Date July 1976 111110 42214<Jf430000 521130 841000 Calculator of the Sensitivity of a Spherical ,Neutron Detec-

" tor. Utkin, V.A. ERDA-TR-125 , PP. 240-250 A V A l L AB1 L IT Y - NTIS RUSSIA

7133 *. Date October 1977 111220 421140 430000 794000 Least-Squares Dosimetry Unfolding: The Program Stay'sl. Perey, F.G. " , „ " r

O R N L / T M - 6062; ENDF-254 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8086. Date January 15, 1978 430000 794000 , Effect of the Light Output Efficiency of Charged Particles

on an Unfolded Neutron Spectrum by an NE213 Organic Scintillator.

Sasamoto, N.; Tanaka, S. NUCL. INSTRUM. METHODS, 148(2), 395-397 JAPAN

8096.. Date September 1978 421140 430000 882000 Neutron Attenuation Due to Boron-10 Shields. (Tech.

Note) Harvey, J.T.; Meason, J.L.; Wright, H.L. NUCL. SCL ENG., 67(3), 343-344 U - A R #

8225 Date August 2, 1978 410000 430000 Determination of Continuous Gamma-Ray Spectra over

the Energy Range 6.1 to 8 MeV.

8378 . . Date August 1978 423135 430000 The Responses of Some T L Albedo Neutron Dosimeters. v

Douglas, J.A.; Marshall, M. HEALTH PHYS., 35(2), 315-324 ENGLAN

839 1 Date September 1, 1978 329000 430000 Monte Carlo Calculation of Efficiencies of Right-Circular

Cylindrical Na l Detectors for Arbitrarily Located Point Sources. ' '

Beam, G.B.;Wielopolski, L.; Gardner, R.P.; Verghese, K. NUCL. INSTRUM. METHODS, 154(3), 501-508 U - N C

839 2 Date September I, 1978 329000 422140 430000 794000 Absolute Neutron Flux Measurements Using an NE-110

Scintillation Counter. Renner, C.; Hil l , N.W.; Morgan, G.L.; Rush, K.; Harvey,

J.A. NUCL. INSTRUM. METHODS, 154(3), 525-533 OARNL

8397 Date December 1978 430000 A Direct Technique for Unfolding Neutron Spectra from

Activation Data. (Tech. Notes) Sekimoto,>H. NUCL. SCL ENG., 68(3), 351-356 JAPAN

8412 Date August 1977 421140 422110 430000 Nuclear Data Guide for Reactor Neutron Metrology. (Edi-

tion 1977) Zijp, W.L.

197'

E C N - 7 7 - 1 0 4 A V A I L A B I L I T Y - S T I C H T I N G .. ENERGIEONDER-

ZOEK C E N T R U M N E D E R L A N D (ECN), VOORTZETTING V A N DE STICHTING REAC-TOR CENTRUM, N E D E R L A N D (RCN), WESTERDUINWEG 3, PETTEN ( N H )

NETHER

'J ' ij 8522 Date October',12, 1978

010000 329000 430000 On Some Statistical Problems Inherent in Radioac-

tive-Source Detection. Barnett, C.S. UCRL-52588 A V A I L A B I L I T Y - N T I S L A L L

8543 Date December 1974 430000 Semi-Empirical Efficiency Equations for Ge(Li) Detectors. Hajnal, F.; Klusek, C., NUCL. INSTRUM. METHODS, 122(3), 559-565 DOE

8545 Date Apri l 15, 1978 112770 512120 430000 795219 Formation of a Response Matr ix to Provide Benchmark

Data for 6 MeV Gamma Photon Penetrations Using,"? Na l Spectrometer.

Bishop, G.B.; Marafie, A.M. NUCL . INSTRUM. METHODS, 150(3), 505-508 E N G L A N

8585 Date 1977 010000 111110 210000 421140 430000 713000 717000

719AOO 719B00 795112 810000 Neutron Environmental Characterization Requirements for


McElroy, W.N.; Bennett, R.A.; Johnson, D.L. EUR-5667E/F,PT.I , PP.1-26; CONF-750935,PT.I,

PP.1-26 A V A I L A B I L I T Y - O F F I C E FOR OFFIC IAL PUBLICA-

TIONS OF T H E EUROPEAN COMMUNITIES," BOITE POSTAL 1003 - LUXEMBOURG

WEE

/ 8591 |< Date 1977

111210 210000 421140 430000f/717000 521130 795254 6 793000 795112 810000 " Investigation of Neutron Flux Spectral Measurement for


i< Odette, G.R. ' ^ V-EUR-5667E/F,PT.I, PP.84-97; CONF-750935,PT.I,

PP.84-97 " AVAILABILITY - OFFICE FOR OFFICIAL PUBLICA-


U-CA

6 8594 ^ Date 1977 111110 421110 430000 L i th ium-6 Neutron Spectrometry In-Core. De Leeuw-Gierts, G.;De Leeuw, S. r i JR-5667E/F,PT. I , PP. 176-208;

CONF-750935,PT.I, PP. 176-208 A V A I L A B I L I T Y - OFFICE FOR O F F I C I A L PUBLICA-

' TIONS OF T H E EUROPEAN C O M M U N I T I E S , BOITE POSTAL 1003 - L U X E M B O U R G

BELGIU

8595 Date 1977 1U110 410000 421130 421120 430000 Neutron Spectrometry Techniques for the Energy Region

0.1 to 10 MeV. Werle, H.; Bluhm,:,H.; Fieg, G. EUR-5667E/F.PT.I , PP.209-220;

CONF-750935,PT.I, PP.209-220 A V A I L A B I L I T Y - O F F I C E FOR OFF IC IAL PUBLICA-


G E R M A N

8596 Date 1977 010000 111110 430000 795112 795233 Review of Unfolding Methods for Neutron Flux Dosimetry. Stallmann, F.W.; Kam, F.B.K. EUR-5667E/F,PT.I , c, " PP.221-232;

CONF-75093S,PT.I, PP.221-232 A V A I L A B I L I T Y - O F F I C E FOR OFF IC IAL PUBLICA-


U - T N

8597 Date 1977 010000 111110 421140 430000 795108 795112 795233 Review of Activation Methods for the Determination of (

Neutron Flux Density Spectra. Zijp, W.L. feUR-5667E/F,PT.I , PP.233-300;


TIONS OF THE EUROPEAN C O M M U N I T I E S , BOITE POSTAL 1003 - L U X E M B O U R G

NETHER

198'

8599 Date 1977 111110 111220 421140 430000 A New Method for the Unfolding of Pulse Height Distribu-

tions from Continuous Encrgy'Spectra. Na^'T-.M.; Pauko, M. £' .-V7E/F.PT.I, PP.310-321;

£ .^-750935,PT.I, PP.310-321 W ^ . . JAB IL ITY-OFF ICE FOR OFFICIAL PUBLICA-

T I O N S OF THE EUROPEAN COMMUNITIES, Z BOITE POSTAL 1003 - LUXEMBOURG

YUGOSL

8600 Date 1977 010000 111110 421140 430000 795108 795112 795233 Unfolding Codes for Neutron Spectra Evaluation Possibili-

ties and Limitations. Dierckx, R.; Sangiust, V. EUR-5667E/F,PT.1,„ PP.322-350;



I T A L Y

8601 Date 1977 111110 421140 430000 794000 The Experimental Data Processing Program RADAK. McCracken, A.K.; Grimstone, M.J. EUR-5667E/F,PT.I, PP.358-374;



ENGLAN

8604 Date 1977 -111110 210000 421140 422130 430000 870092 870094 Fission Rate Measurements for Materials Neutron Dosime-

try in Reactor Environments. Grundl, J.; Eisenhauer, C. EUR-5667E/F,PT.I, PP.425-454;



NABS

8605 Date 1977 111110 421140 422130 430000 870092 870094 Techniques de Fission. Bouchard, J.; Menessier, P. EUR-5667E/F,PT.I, PP.476-497(IN FRENCH);

CONF-750935,PT.I, PP.476-497(IN FRENCH)

A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-T IONS OF T H E EUROPEAN COMMUNITIES,

/ .BOITE POSTAL 1003 - LUXEMBOURG FRANCE


0.1 and 1.0 MeV with Silver. Kondo, I. EUR-5667E/F,PT.I , PP.5,7^-590;

CONF-750935,PT.I, PP.579-590 0

A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-TIONS OF T H E EUROPEAN COMMUNIT IES, BOITE POSTAL 1003 - LUXEMBOURG

JAPAN

8638 Date 1977 111110 421140 430000 795112 Neutron Spectra in the STEK Facility; Determined with theo

4 , ' S A N D - I I Activation Technique'.' Zijp, W.L.; Nolthenius, H.J.; Baard, J.H.

PP.322-348; EUR-5667E/F,PT.I I , CONF-750935,PT.II, PP:322-348

A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-TIONS OF T H E EUROPEAN COMMUNIT IES, BOITE POSTAL 1003 - LUXEMBOURG

NETHE&



Fischer, A.; Nolthenius, H.J.; Zijp, W.L. EUR-5667E/F, PT.II, PP.349-380;



NETHER A



199'

865 8 Date February 1979 111110 122310 210000 421140 430000 521130 810000

870098 .. Testing of ENDF/B Cross-Section Data in the Californi-

um-252 Neutron Benchmark Field. Mannhart, W'.' ORNL/RSIC-42 , PP.119-133 A V A I L AB I L IT Y - NTIS G E R M A N

865 9 Date February 1979 111110 122310 210000 421140 719A00 861000,795112

430000 < , Use of HEDL''Codes in the Sensitivity and Uncertainty



ORNL/RSIC-42 , PP.135-143 ' A V A I L A B I L I T Y - N T I S o

HANFOR

J) " / /


with Complete Covariance Capability. Schmittroth, F. ORNL/RSIC-42 , PP.145-159 A V A I L A B I L I T Y - N T I S HANFOR

8670 Date February 1979 111110 329000 312000 430000 713000 795203 Fuel-Motion Unfolding Based on Point Detector

Responses. McDaniel, P.J.; Wright, S.A. ORNL/RSIC-42 , PP.319-327 A V A I L A B I L I T Y - N T I S SANDIA

8675 Date February 1979 111110 122310 421140 430000 795112 Influence of Cross-Section Structure on Unfolded Neutron

Spectra. Ertek, C.; Vlasov, M.F.; Cross, B.; Smith, g.M. ORNL/RSIC-42 , PP.375-383 A V A I L A B I L I T Y - N T I S AUSTRI

8737 ' Date December 1978 430000,-794000 WINDOWS: A Program for the Analysis of Spectral Data

1 Foil Activation Measurements. <>

Stallmann, F.W.; Eastham, J.F.; Kam, F.B.K. ORNL /TM-6656 AVAILABIL ITY-DEP. , NTIS O A R N L

8744 Date January 1979 111210 421130 430000 Calculations of the Transverse Spatial Distribution of

NE102 Scintillation Light Made by Recoil Protons from Collimated 14-MeV Neutrons.

Goosman, D.R. „ UCRL-52,651 A V A I L A B I L I T Y - L A W R E N C E L IVERMORE LAB.,

UNIVERSITY OF CALIFORNIA , LIVERMORE, CALIFORNIA

L A L L


Logging. Sanders, L.G., CONF - 780921, PP.642 - 647 ° A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL?



Hydrogen-Filled Proportional Counters. Holman, M. ZJE-220 A V A I L A B I L I T Y - S K O D A WORKS, NUCLEAR

POWER CONSTRUCTION DEPART., INFORMA-T ION CENTRE, PLZEN - CZECHOSLOVAKIA

CZECHO


try. Seltzer, S.M.; Hubbell, J.H.; Berger, M.J. STI /PUB-471 (VOL.2),PP.3-43;

CONF-771209-P2,PP,3-43; A V A I L A B I L I T Y - I N T E R N A T I O N A L ATOMIC


i

c 9039. . .„ Date December 1978

020000 220000 423210 430000 Wall Effects in Gamma-Ray Dosimetry. Jarrett, R.D.; Brynjolfsson, A.; Wang, C.P.

if " " •

Effet du Rayonnement Diffuse sur le Rapport des Doses Absorbees Derivees de Mesures d'lonisation et Obtenues par Dosimetre de Fricke. y

Garsou, J.L. ^ 1' STI /PUB-471 (VOL. 2),PP.301 - 316;

CONF - 771209 -P2,PP.301 - 316; A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M IC

ENERGY AGENCY, V I E N N A (AUSTRIA) BELGIUM "

9122 Date May 1979 111110 421110 430000 713000

" Neutron Spectrum Measurements in CFRMF 6Li Spec-trometry.

De Leeuw-Gierts, G.; De Leeuw, S.; Rogers, J.W.; John-son, L.O.

, TREE-1358; BLG-525 A V A I L A B I L I T Y - N T I S $4.50 I D N E L

STI /PUB-471 (VOL.2),PP.91 -102; C O N F - 771209 - P2,PP.91 -102;

A V A I L A B I L I T Y - I N T E R N A T I O N A L ATOMIC ENERGY AGENCY, V I E N N A (AUSTRIA)

ARIvlY

904 0 Date December 1978 112720 423240 430000 Correction Factors in Gamma-Ray Dosimetry. Brynjolfsson, A.; Wang, C.P.; Massoud, E . ^ ,, STI/PUB-471(VOL.2),PP.103-122;

CONF -771209 - P2,PP. 103 -122; A V A I L A B I L I T Y - I N T E R N A T I O N A L ATOMIC

ENERGY AGENCY, V I E N N A (AUSTRIA) A R M Y

6

904 1 Date December 1978 112720 423210 430000 f -Calculation of the Fluence of Secondary Photons, Compton

and Fluorescence, Generated by Attenuation in Thin Walls. ^

Janssens, A.; Eggermont, G.; Jacobs, R. STI/PUB-471(VOL.2),PP.123-136;"

CONF-771209-P2,PP.123- 136; A V A I L A B I L I T Y - I N T E R N A T I O N A L ATOMIC^.

ENERGY AGENCY, V IENNA (AUSTRIA) BELGIU

9046 Date December 1978 020000 220000 430000 Quelques Ameliorations en Spectrometrie Gamma a Basse

Activite. Baltar, J.; Caboret, J. STI /PUB -471 (VOL.2),PP. 189-198;


ENERGY AGENCY, V I E N N A (AUSTRIA) " C A N A D A -l

9048 Date December 1978 113100 430000 423300 General Cavity Theory in the Dosimetry of X-Rays: Exper-

imental Study with a High-Pressure Chamber. Janssens, A.; Eggermont, G.; Jacobs, R. STI /PUB-471 (VOL.2),PP.207-228;

CONF - 771209 - P2,PP.207 - 228; A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M IC

ENERGY AGENCY, V I E N N A (AUSTRIA) BELGIU

a -9053 Date December 1978

113100 423300 430000

9193 Date Apri l 27, 1978 111110 111210 421130 430000 312000 32A000 522130


lated Neutron and Gamma-Ray Fluences in Liquid Air . <'

Scott,oW.H.,Jr.; Gritzner, M.L.; Albert, T.E.; Hagan, W.K.; Schanzler, L.

SA1-78 -648 -LJ A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, INC.,


SCA

9196 Date December 1978 020000 220000 430000 Dissemination en France des Unites des Grandeurs Utilisees

en Metrologie des Rayonnements Ionisants. Guiho, J.-P.; Simoen, J . -P. STI /PUB-471 (VOL. 1), PP.3-19; CONF-771209-P1,

PP.3-19; A V A I L A B I L I T Y - I A E A FRANCE

9197 Date December 1978 020000 220000 430000 Etudes Dosimetriques Menees au L M R I dans le Domaine '?}

des References Primaires et des Procedures de Transfert. Simoen, J.-P. STI /PUB-471 (VOL.1), PP.21-32;

CONF-771209-PI , PP.21-32; A V A I L A B I L I T Y - I A E A FRANCE

201'

9198 / I . Date December 1978 020000 220000 430000 Current Work in thi,Field/of Standardization in Dosimetry

of Photons and Elections in the Federal Republic of Ger-many.

Reich, H. -STI /PUB-471( VOL.1), PP.33-52;

CONF-771209-P1, PP.33-52; A V A I L A B I L I T Y - I A E A G E R M A N

9199 Date December 1978 020000 220000 430000 A Primary Standard for Determination of Absorbed Do™ in

Water for X-Rays Generated at Potentials of 7.5 to 30 U \ k V .

Bojim, J.; Hohlfeld, K.; Reich, H. STlVpUB-471 (VOL. 1),

CONF-7712D9-P1, PP.53-63; A V A I L A B I L I T Y - I A E A G E R M A N

PP.53-63;

0

920 0 Date December.,1978 020000 220000 430000 Traceability in Ionizing Radiation Measurements Systems. Cavallo, L.; Ehrlich, M.; Hutchingson, J.M.R. STI /PUB-471 (VOL. 1), PP.65-87;


a 920 1 Date December 1978

020000 220000 430000 Dosimetry Standards for Industrial Radiation Processing. McLaughlin, W.L. STI /PUB-471 (VOL. 1), PP.89-106;

,CONF-771209-PI , PP.89-106; A V A I L A B I L I T Y - I A E A NABS

9202 Date December 1978 020000 220000 430000 Primary and Secondary Standards of Dosimetry: Calibra-

tion Methods in Hungary." Zsdanszky, K. STI /PUB -471 (VOL. 1), R.P.107-117;

CONF-771209-P1, PP.107-A V A I L A B I L I T Y -1AEA H U N G A R

7;

9203 fe . Date December 1978 020000 220000 430000 " " Standardization in Radiation, Dosimetry in the United King-

d0m- ' O %>jf' ;

Jennings, W.A. STI /PUB-471 (VOL. 1), PP.119-131;

CONF-771209-P1, PP. 119—131; A V A I L A B I L I T Y - I A E A ENGLAN


cal Field. Rossiter, M.J. ^ STI /PUB-47KVOL.1) , PP.133-138;

CONF - 771209 - P1, PP. 133-138; A V A I L A B I L I T Y - I A E A ENGLAN

9205 Date December 1978 020000 220000 430000 Current Work on Dosimetry Standards in Japan. Moriuchi, Y. STI /PUB-471 (VOL. 1), PP.139-158;

CONF-771209-PL PP.139-158; A V A I L A B I L I T Y - I A E A JAPAN

9206 .cDate December 1978 020000 22000,0' 430000 Medical Dosimetry Standards Programme of the National

Bureau of Standards. Loevinger, R.

ft STI /PUB-471 (VOL.1), PP.159-174; V CONF-771209-P1,. PP.159-174;

A V A I L A B I L I T Y - I A E A NABS

9207 Date December 1978 020000 220000 430000 The Secondary Standard Dosimetry Laboratory - - A

Necessary Link in the Dissemination Chain. » Julius, H.W.; van der Lugt, G. =fc

STI/PIJB-471 (VOL.: ) , PP. 189 - i 92; C0NF-7712'_9-P1, PP.189-192; o ° V .

A V A I L A B I L I T Y - I A E A u

NETHER 0 » " '.I:

9208 Date December'1978-u 020000 220000 430000 „ ' «" <• •<"

Evaluation of the Need for Radiotherapy Calibrations in ,the United States of America. ' " „

Lanzl, L.H.fRozenfeld, M. « u, " " " V fiw •£>

STI /PUB-471 (VOL.1), -PP.193-T97;. CONF-771209-P1, PP.193-197; $ | ' ' '"a

A V A I L A B I L I T Y - I A E A " ^ —

ooH)0P (f' 202'

If

T J - I L

tt, 920 9 Date December 1978 ,.

020000 220000 430000 The Austrian Dosimetry Laboratory: A National Standard

and Routine Calibration Centre. ' Duftschmid, K.E. ST I /PUB-471 (VOL. 1), " PP.199-212;

CONF-771209-R1, PP.199-212; A V A I L A B I L I T Y - I A E A < AUSTRI

O 921 0 Date December 1978

020000 220000 430000 Exposure Intercomparison with Ionization Chambers -

Based on Three Intercompared Check Sources. Nette, P.; Reis, D.; Eckerl, H.; Drexler, G.; Pychlau, P. STI /PUB - 471 (VOL. 1), PP.2'i 3-218;

CONF-771209-P1, PP.213-218; A V A I L A B I L I T Y - I A E A BRAZ IL

,,9211 <-:,. Date December 1978 020000 220000 430000 The Regional Calibration Laboratory at the M.D. Anderson

Hospital. Humphries, L.J.; Shalek, R.J. ST I /PUB-471 (VOL.1), PP.219-227;

CONF-771209-P1, PP.219-227; A V A I L A B I L I T Y - I A E A U - T X

<> 9212/ Date December 1978 020000 220000 430000 Primary Dosimetric C) Standards at" the' Memorial

Sloan - Kettering Cancer Center. Holt, J.G.; McDonald, J.C.; Buffa, A.; Perry,"D.; Ma, I.;

Laughlin, J.S. ST I /PUB-471 (VOL. 1)," PP.229 - 240;

CONF-771209-P I , PP.229-240; A V A I L A B I L I T Y - I A E A ' S L O A N

9214 Date December 1978 020000 220000 430000 The Role of the Secondary Standards Dosimetry Laboratory

in a Nuclear Power Uti l i ty. Clarke, R.W.; Thompson, I.M.G. STI /PUB-471 (VOL.1), PP.251-263;

CONF-771209-P1, PP.251-263; A V A I L A B I L I T Y - I A E A E N G L A N

9215. Date December 1978 , 020000 220000 430000 Organization of a Secondary Standard Dosimetry Labora-J

tory for the Indian Region. . Subrahmanian, G.; Sundararao, I.S. STI /PUB - 471 (VOL. 1),

" ,CONF-771209-P' i , P.P.265-A V A I L A B I L I T Y - I A E A ^ '

L I N D I A

PP.265-272; 272;

„ 9216 Date December 1978 020000 11-2720 220000 430000-Eval'uation „of Dosimetric Accuracy and Uniformity for

o 60-Co"Radiation Therapy. ou ity . Sundararao// I.S.; Naik, S.B.; Pushpandpangadan, K.D.;

Vafliwala, R.; Subrahmanian, G. STI/PJJB - 42)1 (VOL. 1), ' PP.273-280;

CONF-7J1209-P1, PP.273-280; A V A I £ A B I L I T Y - I A E A ' INDIA

it: 2 9218. Date December 1978 020000 220000 430000 Implications of Dosimetry Intercomparisons for Standard-

ization in Neutron Dosimetry for Biological and Medical Applications.

Broerse, J.J.;rBurger, G.; Coppola, M. STI /PUB-47J (VOL.1), Pg.291-304;

CONF-771209-P1, PP.291-304; A V A I L A B I L I T Y - I A E A u NETHER

9213 Date December 1978 020000 220000 410000 430000 The Organization and Operation of the Regional Calibration

Laboratory at Victoreen, Cleveland.0 :> Simon, W.E. ST I /PUB-47 l (VOL . l ) , PP.241-249;

CONF-771209-P1, PP.241-249; A V A I L A B I L I T Y - I A E A VICTOR

9219 Date December 1978 020000 113100 220000 430000 The Need for Repeated Intercomparisons and Standardiza-

tion of X - R a y Dosimetry for the Co-Ordination of Late-Effects Research in Europe.

Zoetelief, J.; Broerse, J.J.; Puite, K.J. »STI /PUB-471 (VOL.1), PP.305-317;

CONF-771209-P1, PP.305-317: A V A I L A B I L I T Y - I A E A NETHER

203'

N"< r „ .(>' 9220 Date December 1978

020000 220000 430000 Y Evaluation of the 1977 I A E A Pilot Study of Postal Dose

Intercomparison (TLD) for Orthovoltage X - R a y Ther-aPy- i\

Bjarngard,' B.E.; Ruden, B . - I . ; Eisenlohr, H.H.; Girzi-kowsky, R.; Haider, J.

STI /PUB-47KVOL.1) , ' t O N F - 7 7 1 2 0 9 - P l , PP.319-333;

A V A I L A B I L I T Y - I A E A U - M A

i-i

PP.319-333;

S")

9221 'iJate December 1978 020000 220000 430000

9225. Date December 1978,

Dosimetric Primary and Secondary Standardization, within the European Communities.

Oberhofer, M. STI /PUB-471( VOL.1), PP.335-340;

CONF-771209-P1, PP.335-340;' A V A I L A B I L I T Y - I A E A ITALY, ;



Thompson, I.M.G. STI /PUB-471(VOL. l ) , PP.343-365;

CONF-77 I209-P1 , PP.343-365; A V A I L A B I L I T Y - I A E A E N G L A N

G O

020000,;l lii.l 10 220000 430000 Personnel Dosimetry Intercomparison Studies at the O R N L

Health Physics Research Reactor. Dickson, H.W.; Gilley, L.W. STI /PUB ^471 (VOL. 1), ^ PP.491-509;

CONF-771209-PI , PP^491-509; A V A I L A B I L I T Y - I A E A O A R N L

9227 Date December 1978 020000 220000 430000 Accuracy and Precision in Calibration of Low-Level Radi-

ation Monitors. ^ Ackers, J.G. STI /PUB-471 (VOL.1), - PP.527-532;


" o

9382 ^ Date September 1979 111110 111210 111220 220000 420000 430000 European Workshop on Neutron Dosimetry for Radiation

Protection. Alberts, W.G.; Cosack, M.; Kluge, H.;,Lesiccki, H.; Wag-

ner, S.; Zi l l , H.W. P T B - N D - 1 7 A V A I L A B I L I T Y - I N S T I T U T BERLIN DER PHYSI-

K A L I S C H - T E C H N I S C H E N BUNDESANSTALT, ABBESTRABE 2-12, 1000 BERLIN 10 (CHAR-LOTTENBURG). ISSN 0572-7170

GERMAN O

0 9223 Date December 1978 020000 111110 430000 870098 NBS Standard Reference Neutron Fields for Personnel

Dosimetry Calibration. Schwartz, R.B.; Grundl, J.A. STI /PUB - 471 (VOL. 1), PP.367-376;

CONF-771209-P1, PP.367-376;,, A V A I L A B I L I T Y - I A E A NABS

9224 : . Date December 1978 020000 220000 430000 Use of a Phantom in Personnel Dosimetry Photon Calibra-

tions. Bartlett, W.T.; Holland, J.P.; Hooker, C.D.; Mulhern, O.R.;

Fleming, D.M. STI /PUB - 471( VOL. 1), , PP.465-474;

CONF-771209-PI , PP.465-474; A V A I L A B I L I T Y - I A E A B A N W

9399. . Date October 1, 1979 )j 3 2 9 0 0 0 . 4 3 0 6 0 C p 4 2 1 1 3 0

The Response Function of Organic Scintillators to Fast Neu-trons. 0

Anghinolfi, M.; Ricco, G.; Corvisiero, P.; Masulli, F. NUCL. INSTRUM. METHODS, 165(,2), 217-224 Q

I T A L Y

9466 Date November 15, 1979 220000 430000 The Response of a Spherical Neutron Survey Meter. Harrison, K.G. NUCL. INSTRUM. METHODS, 166(2), 197-201 ENGLAN 0

9729 Date January 1980 430000 794000 ° Optimized Smoothing in Neutron Spectrum Unfolding by

the FERDOR Method. (Tech. Note) " Johnson, R.H.; Wehring, B.W.; Doming, J.J.

m O s*

. 9 204

N U C L . SCI. ENG., 73(1), 93-97 U - I L

Time Dependent Resul ts


8502 Date January 1979 112120 510000 512220 870092 870094 Fission Product Gamma Spectra. Jurney, E.T.; Bendt, P.J.; England, T.R. L A - 7 6 2 0 - M S A V A I L A B I L I T Y - N T I S L O A S L

9028 Date August 1979 112710 329000 32A000 510000 750000 717000 793000

795178 795203 795276 M A G I K — A Monte Carlo System for Computing

Induced Residual Activation Dose Rates. Barish, J.; Gabriel, T.A.; Alsmiller, R.G.,Jr. O R N L - 5 5 6 1 A V A I L A B I L I T Y - N T I S $6.00 O A R N L

9065 Date August 1979 122110 510000 795180 „ Discrete Transfer Cross-Section Expansion for

Time-Dependent Neutron Transport. Beranek, F.; Conn, R.W. N U C L . SCL ENG., 71(2), 100-110 U - W I

9099 Date Apr i l 1978 112B00 329000 510000 512110 795166 830000 Time-Dependent Dose Rate and Compton Electron Gener-o" ation from Mono-Energetic* Gamma Sources in

Homogeneous Air. Engstrom, G. FOA RAPPORT C 20236-A2 A V A I L A B I L I T Y - F O R S V A R E T S FORSKNINGSAN-

STALT, N A T I O N A L DEFENSE RESEARCH INST ITUTE, S -104 50 S T O C K H O L M 80, SWE-D E N

S W E D E N



dent Neutron Transport.

Beranek, F.; et al. U W F D M - 3 0 4 A V A I L A B I L I T Y - N U C L E A R E N G I N E E R I N G

DEPARTMENT, U N I V E R S I T Y OF WISCONSIN, M A D I S O N , W I

U - W I

9325 Date May 1979 111210 32A000 510000 521130 717000 795180 Neutron Moderation in ICF Pellets and Ejffects on Damage

and Radioactive Inventory. !| Beranek, F.; Conn, R.W. i U W F D M - 3 1 0 A V A I L A B I L I T Y - F U S I O N E N G I N E E R I N G PRO-

G R A M , N U C L E A R E N G I N E E R I N G DEPT., U N I V E R S I T Y OF WISCONSIN , ' M A D I S O N W I 53706

U - W I

9749 1 . Date 1979 111110 310000 510000 511110 | ° " Time-Dependent Continuous-Energy Benchmark Solu-

tions in Neutron Transport Theory. Ganapol, B.D.; Roybal, J.A.; Peddicord,iiK.L.; Henninger,

R.J. it CONF-790402,VOL.11, PP .4 -79 - - 4 - 9 4 A V A I L A B I L I T Y - H C - - A N S V I R G I N I A SECTION,

P.O. BOX 1260, L Y N C H B U R G , VA. 24505; M F - - N T I S t ,

9856 Date May 1980 111210 329000 424000 510000 795203 793000 810000 Calculation of Neutron D ie -Away Times in a

Large-Vehicle Portal Monitor. Lillie, R.A.; Santoro, R.T.; Alsmiller, R.G.,Jr.

" O R N L / T M - 7 2 9 9 A V A I L A B I L I T Y - N T I S , PC A 0 3 / M F A01 O A R N L

One Dimension - Neutron - P r imary -^ Calculation




Milosevicj, M.; Kocicj, A.; Altiparmarkov, D. I N I S - M F - 3 2 8 5 ( I N SERBIAN) A V A I L A B I L I T Y - I N S T I T U T Z A N U K L E A R N E

N A U K E BORIS K IDRIC , BELGRADE (YUGOSLA-V I A )

205'

YUGOSL 6803 Date 1975

6468 Date Dec. 1977 111210 329000 511110 820000 853100 861000 Radiation Doses as a Function of Thickness and Shielding

Material Surrounding a 14 MeV Neutron Source. Hansen, L.F.; Komoto, T.; Wong, C. CONF-770401, PP.881-888 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 L A L L

6543 Date October 1977 111110 325000 511110 719A00 870092 Analysis of Homogeneous U233 and U235 Critical Assem-

blies with E N D F / B - I V Data (AWBA Development Program).

Ullo, J.J.; Hardy, J.,Jr. W A P D - T M - 1 2 9 9 A V A I L A B I L I T Y - W E S T I N G H O U S E ELECTRIC

CORPORATION, BETTIS ATOMIC POWER DIVI-SION

BETTIS

6701 Date April 1978 111500 310000 324000 511110 Analytical Calculations of Neutron Slowing Down the

Transport and Transport in the Cons-tant-Cross-Section Problem.

Cacuci, D.G. O R N L / T M - 6 3 7 8 A V A I L A B I L I T Y - N T I S $10.75 O A R N L

6746 Date September 1977 111110 112110 112400 112500 32AOOO 511110 551110

512210 552210 719A00 793000 795254 795276 PWR and BWR Radiation Environments for Radiation

Damage Studies. Gritzner, M.L.; Simmons, G.L.; Albert, T.E.; Straker, E.A. EPRI -NP-152 , F I N A L REPORT A V A I L A B I L I T Y - S C I E N C E APPLICATIONS INC.,

LA JOLLA, CALIF. EPRI

6758 Date March 1978 111110 122110 325000 511110 794000 810000 Differences Between L A S L - and ANL-Processed Cross

Sections. Kidman, R.B.; MacFarlane, R.E.; Becker, M. L A - 7 L 9 L - M S A V A I L A B I L I T Y - N T I S $8.00 LOASL

111110 324000 32A000 511110 861000 870092 Multigroup Formalism for Evaluation of Continuous Slow-

ing Down Theory Parameters. Parvez, A.; Becker, M. COO-2458-18 A V A I L A B I L I T Y - D E P . , NTIS U - N Y

6846 Date 1978 111110 421140 430000 511110 7951 fc Comparison of Integral Cross Section Values of Several

Cross Section Libraries in the S A N D - I I Format. Zijp, W.L.; Nolthenius, H.J. IAEA-208, VOL.11, PP.327-348 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE NETHER

7031 Date September 1976 111210 122310 312000 32A000 511110 870003 717000 Neutronic Data Consistency Analysis for Lithium Blanket

Shield Design. Reupke, W.A.; Muir, D.W. CONF-760935-P3, PP. 861 -871; L A - U R - 7 6 - 2 0 9 2 A V A I L A B I L I T Y - N T I S U - G A

c

7066 Date January L977 111110 310000 511110 713000 870092 870094 Stochastic Method of Calculations for Fast Systems. Godwal, B.K.; Navalkar, M.P. NBS SPEC. PUB. 461, PP. 97-99 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


7069 Date January 1977 111110 32AOOO 423140 511110 511120 793000 795254

842000 870098 861000 870082 Transmission of 252-CF Fission Neutrons Through Vari-

ous Shields. Song, Y.T. NBS SPEC. PUB. 461, PP. 119-123 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

WASHINGTON, D.C. 20402 NAVY

(/ 7085 Date January 1977

111110 329000 511110 521110 795171 795017 810000 Neutron Dose Evaluation Using Calculated Neutron Spec-

o tra. Makra, S.

206'

NBS SPEC. PUB. 461, PP. 238-246 AVAILABILITY -SUPT. OF DOCUMENTS, GPO,

WASHINGTON, D.C. 20402 H U N G A R



Cramer, S.N.; Oblow, E.M. O R N L / T M - 5 5 3 5 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

7100 Date July 1976 111110 122110 32A000 511110 810000 Using the Method of Subgroups to Allow for the Resonance

Structure of Cross-Sections in Computations of the Passage of Neutrons Through Plane Layers of Shielding.

Germogenova, T.A.; Isayev, N.V.; Nikolayev, M.N.; Khokhlov, V.F.



tron fluxes in Heterogeneous Shielding. Germogenova, T.A.; Konovalov, N.V.; Suvorov, A.P. E R D A - T R - 125, PP. 25-34 A V A I L A B I L I T Y - N T I S RUSSIA



A.N. • E R D A - T R - 1 2 5 , PP. 35-45 J A V A I L A B I L I T Y - N T I S

RUSSIA

7114 Date July 1976 112500 423250 32A000 511110 512210 512220 853800



V.V.; Khokhlov, V.F.; Tsypin, S.G. E R D A - T R - 1 2 5 , PP. 145-151


7129 Date March 1977 111130 111400 122110 122210 32A000 511110 512210

830000 853100 810000 " Production and Testing of the D N A Few-Group Coupled

Neutron-Gamma Cross-Section Library. Bartine, D.E.; Knight, J.R.; Pace, J .V „ I l l ; Roussin, R. O R N L / T M - 4 8 4 0 A V A I L A B I L I T Y - D E P , NTIS $5.50 O A R N L

8023 Date June 1978 111110 122110 511110 551110 713000 793000 794000

122310 E N D F / B - I V , L I B - I V , and the CSEWG Benchmarks. Kidman, R.B. LA -7355 - M S -A V A I L A B I L I T Y - L O S ALAMOS SCIENTIFIC L A B ,


8032 Date September 1978 111210 122100 312000 32A000 511110 512210 717000


Reactor Shielding Experiments. Seki, Y.; Santoro, R.T.; Oblow, E.M.; Lucius, J.L. ORNL-5467 A V A I L A B I L I T Y - N T I S $4.50 O A R N L v

8035. . Date August 1978 111220 122110 32A000 511110 853900 853700 861000

512210 793000 Neutron-Photon Multigroup Cross Sections for Neutron

Energies to 60 MeV. Alsmiller, R.G.,Jr. O R N L / T M - 6 4 8 6 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8199 Date August 1977 112500 111500 112BOO 32A000 311000 511110 512110

795254 853100 Neutron- and Gamma-Ray Transport Calculations of

Dose Transmission Factors in Concrete. Engslrom, G.; Lefvert, T. FOA RAPPORT C 20195-A2 A V A I L A B I L I T Y - F O R S V A R E T S FORSKNINGSAN-

STALT, H U V U D A V D E L N I N G 2, 104 50 STOCKHOLM

207'

S W E D E N

8500 Date June 1977 111110 122110 324000 326000 327000 820000 861000


ing-Down Kernel: The Computer Code "MAGGIE" . Gado, J.; Keresziuri, A. KFKI -1977-44 A V A I L A B I L I T Y - K O Z P O N T I F I Z I K A I KUTATO


HUNGAR

8565 Date 1977 111210 32A000 329000 511110 512210 830000 853100

793000 770000 795203 795254 Skyshine Analysis for the Intense 14 MeV Neutron Source

Facility. Peng, W.H.; Celnik, J. CONF-771029,VOL.11, PP.1704-1706 A V A I L A B I L I T Y - I E E E SERVICE CENTER, SINGLE


BURNS



Peng, W.H. COO-2509-6 AVA ILAB IL ITY -DEP. , NTIS U - N Y

8662 Date February 1979 111110 32A000 312000 421130 511110 870041 794000


Cross Sections. Ingersoll, D.T.; Wehring, B.W. ORNL/RSIC-42 , PP.179-189 A V A I L A B I L I T Y - NTIS O A R N L

8926 Date May 1979 111210 32A000 511110 717000 Feasibility Study to Produce First Wall Fusion Reactor

Spectra Around a 14-MeV Neutron Point Source. Battat, M.E.; Dierckx, L.A.; Emigh, C.R. NUCL. TECHNOLOGY, 43(3), 338-348 LOASL

8993 Date February 1, 1979 111110 220000 511110 632110 820000 842000 853100 Depth-Dose Distribution for Fission Neutron Spectra''

Degraded Through Low Z Shields. Singh, D.; Bisht, J.S.; Madhvanath, U. NUCL. INSTRUM. METHODS, 159(1), 229-234 INDIA

9071 Date 1977 111110 112110 122110 328000 329000 511110 512110.




MAAG

9192 Date May 10, 1977 111110 111210 112110 32A000 511110 512110 512210

793000 795254 830000 870007 870098 Calculation of Neutron and Gamma Ray Energy Spectra in

the Californium Tank Experiment for Comparison with 2" x 2" NE-213 Detector Measurements.

Straker, E.A.; Gritzner, M.L.; Harris, L.,Jr.; Schanzler, L. S A I - 7 7 - 6 5 7 - L J AVA ILAB IL ITY -SCIENCE APPLICATIONS, INC.,


SCA >

9229 Date August 13, 1979 111110 111220 329000 511110 521130 793000 810000 Data Testing Results for the L L L Evaluated Nuclear Data

Library (ENDL-78) . Howerton, R.J. UCRL-50400, VOL.15, PT.E A V A I L A B I L I T Y - N T I S L A L L

9288 0 Date 1978 111110 111210 329000 795017 870082 511110 Calculated Leakage Spectrum from 238-U Spheres Con-

taining Sources of 14-MeV or Fission Neutrons for Radiobiological Applications.

Ing, H.; Cross, W.G. EUR-5848,PP.357-368; CONF-770597,PP.357-368 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


CANADA

208'

9749 Date 1979 111110 310000 510000 511110 Time-Dependent Continuous-Energy Benchmark Solu-

tions in Neutron Transport Theory. Ganapol, B.D.; Roybal, J.A.; Peddicord, K.L.; Henninger,

R.J. CONF-790402,VOL.11, PP.4-79- - 4 - 9 4 A V A I L A B I L I T Y - H C — A N S V I R G I N I A SECTION,


U - A Z

9750 Date 1979 o 111110 311000 326000 511110 Refinements for Spatial Channel Theory Computations. Abu-Shumays, I.K.; Selva, R.J.; Shure, K. CONF-790402,VOL.11, P P . 4 - 9 5 - - 4 - 1 1 5 A V A I L A B I L I T Y - H C - - A N S V IRGIN IA SECTION,


BETTIS

9797 Date January 1980 111500 329000 511110 861000 Computational Benchmark Problem for Deep Penetration in

Iron. Hendricks, J.S.; Carter, L.L. L A - 8 1 9 3 - M S A V A I L A B I L I T Y - D E P . , NTIS, PC A 0 6 / M F A01 LOASL

10015 Date June 1980 111110 311000 32AOOO 329000 511110 842000 870094

v 870094 795254 795203 Calculation of the Response of Cylindrical Targets to Colli-> ) mated Beams of Particles Using One-Dimensional

Adjoint Transport Techniques. Dupree, S.A. S A N D - 8 0 - 0 4 3 2 0

A V A I L A B I L I T Y - S A N D I A N A T I O N A L LABORATO-RIES, ALBUQUERQUE, N M , THEORETICAL DIV.

S A N D I A

One Dimension - Neutron - P r i m a r y -Exper iment


6458 Date Dec. 1977 111110 421120 511120 713000 421140 870011 Results of Neutron Propagation in Steel-Sodium Mixtures

with Various Source Spectra on H A R M O N I E and TAPIRO.

Calamand, D.; Desprets, A.; Rancurel, H.; Vienot, R.; Esti-ot, J.C.; Trapp, J.P.; Bargellini, M.L.; Bozzi, L.; Martini, M.; Moioli, P.; Antonini, D.; De Carli, A.; Rado, V.


DR., PRINCETON, NJ 08540 !•" FRANCE

6513 Date October 1976 020000 511120 Review of Microscopic Integral Cross Section Data in Fun-



HEDL-SA-1148 (DRAFT) ; CONF-761127-5 A V A I L A B I L I T Y - N T I S S4.00 U HANFOR

6578 Date March 1978 111110 329000 421130 795203 511120 820000 A First-Order Approximation to Fast-Neutron Penetra-

tion Spectra for Non-Normal ly Incident Neutrons on Water Slabs. (Tech. Note)

Miller, W.H.; Hollabaugh, D.; Meyer, W. NUCL. SCI. ENG., 65(3), 554-557 U - M O ,


mination. Boot, S.J. A E R E - R - 8 6 5 4 A V A I L A B I L I T Y - H . M . S . O . PRICE POUND1.50; NTIS


6706. Date October 10, 1977 111210 329000 423110 511120 521230 830000 861000 Dosimetry Measurements External to a 10 Kiloliter Liq-

u id -A i r Vessel Containing a D - T Neutron Source. Tripler, D.J.; Goldberg, E.; Farley, W.E. UCRL-52334 A V A I L A B I L I T Y - D E P . , NTIS L A L L

6710 Date February 1978 111110 422120 326000 511120 820000 870098 Spatial Distribution Measurements of Fission Neutrons in

Water as an Oxygen Data Test (AWBA Development Program).

Green, L.; Ullo, J.J.

£ 209'

W A P D - T M - 1 3 6 5 A V A I L A B I L I T Y - N T I S BETTIS

6799 Date June 1978 020000 421140 421130 32A000 861000 511120 Benchmark Shielding Experiments for Testing Iron and

Steel Data. McCombie, C.; Gmur, K.; Jermann, M.; Richmond, R.; Sch-

mocker, U.; Seth, S. CONF-780401, PP.53-62 A V A I L A B I L I T Y - N T I S SWITZ

6808 Date 1978 010000 1U110 122200 210000 421140 430000 511120


Papers. Summary Report. Vlasov, M.F. (Ed.) IAEA-208, VOL.I, PP.1-49 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE IAEA

6809 Date 1978 010000 111110 410000 122200 511120 421140 770000

430000 Benchmark Neutron Fields for Reactor Dosimetry. Grundl, J.; Eisenhauer, C. IAEA-208, VOL.I, PP.53-104 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE

6810 Date 1978 010000 210000 421130 421140 511120 719A00 861000 Power Reactor Pressure Vessel Benchmarks. (i Rahn, F.J. IAEA-208, VOL.I, PP.105-140 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE EPRI

HANFOR

o

6816 Date 1978 111110 122310 421140 511120 810000 870092 870098 , Ratios of Measured and Calculated Reaction Rates for

Some Known Spectra. Zijp, W.L.; Nolthenius, H.J.; Baard, J.H. IAEA-208, VOL.1, PP.265-300 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE NETHER

6829 , Date 1978 111110 421140 511120 795112 795233 Comparison of Neutron Spectrum Unfolding Codes.' Zijp, W.L.; Baard, J.H.; Nolthenius, H.J. IAEA-208, VOL.11, PP.37-62 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE NETHER


HOUSE ENGLAN

6831 Date 1978 111110 410000 ,421130 421140 511120 Spectrum Characterization and Threshold Reaction Rate


HOUSE ENGLAN

6815 Date 1978 010000 111110 122310 511120 810000 870092 870098 Review of Microscopic Integral Cross Section Data in Fun-


Fabry, A.; McElroy, W.N.; Kellogg, L.S.; Lippincott, E.P.; Grundl, J.A.; Gilliam, D.M:; Hansen, G.E.

IAEA-208, VOL.I, PP.233-263 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE

6832 Date 1978 111110 421130 421140 410000 511120 Several Studies of Neutron Standard Field in the Fast

Source Reactor "YAYOI" . Sekiguchi, A.; Nakazawa, M.; Kosako, T.; Wakabayashi,


HOUSE JAPAN '

210

6834. Date 1978 6842. Date 1978 111110 020000 410000 421140 511120 The Coupled Fast Reactivity Measurements Facility

(CFRMF). Rogers, J.W.; Harker, Y.D.; Millsap, D.A. IAEA-208, VOL.11, PP.117-176 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE EDGERT

010000 020000 111110 421140 511120 Measurement and Evaluation of Threshold Reaction Cross

Sections in Standard Neutron Fields. Kimura, I.; Kobayashi, K.; Hayashi, Shu A.; Yamamoto, S.;

Gotoh, H.; Yagi, H. IAEA-208, VOL.11, PP.265-290 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE JAPAN

6837 Date 1978 111110 422130 410000 511120 Intercomparison of the Intermediate-Energy Standard

Neutron Fields at the NISUS and;MOL-sigma sigma Facilities by Means of Absolute Fission Chambers.

Fabry, A.; Williams, J.G.; Hannan, A.H.M.A.; Azimi-Garakani, D.

IAEA-208, VOL.11, PP.191 -208 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE BELGIU



Fabry, A.; Garlea, I. IAEA-208, VOL.11, PP.291-308 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE BELGIU

6838 Date 1978 111110 410000 421140 511120 810000 Activation Foil Data for NISUS, MOL-sigma sigma and

235-U Fission Spectrum. Hannan, A.H.M.A.; Williams, J.G. IAEA-208, VOL.11, PP.209-225 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE " ENGLAN


Low and High Energy Part of the Californium-252 Neutron Spectrum.

Mannhart, W. IAEA-208, VOL.11, PP.227-246 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE GERMAN

6848 Date 1978 111110 210000 511120 861000 870092 One Material Experiments in the Frame of Power Reactor

Pressure Vessel Benchmarks. De Leeuw-Gierts, G.; De Leeuw, S. IAEA-208, VOL.11, PP.375-383 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE BELGIU

6867 Date May 1978 111210 11 1220 4221 10 511120 795123 820000 Thermal Neutron Fluxes Produced in Water by Various Iso-

tope and Accelerator Neutron Sources. Holland, L.; Walker, J. NUCL. INSTRUM. METHODS, 151(1,2), 175-182 ENGLAN

I! 6840 J,j. . Date 1978

111110 421140 511120 810000 ( / Spectrum Averaged Cross-Section Measurements in the

Fast Neutron Field of a Uranium Fission Plate. Najzer, M.; Rant, J. IAEA-208, VOL.11, PP.247-260

^ A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-HOUSE

YUGOSL

6875 Date June 1978 111210 421160,511120 512210 830000 Transport of Neutron and Secondary Gamma Radiations

Through a Liquid Air Sphere Surrounding a 14-MeV Neutron Source. (Tech. Note)

Sidhu, G.S.; Farley, W.E.; Hansen, L.F.; Komoto, T.; Pohl, B.; Wong, C.

NUCL. SCI. ENG., 66(3), 428-433 L A L L

211'

6954 Date February 1978 111110 111220 421130 421150 430000 511120 870098 Neutron Spectrum Measurements for Radiation Protection

Purposes. Slaughter, D.R.; Rueppel, D.W.; Fuess, D.A. UCRL-52,415 A V A I L A B I L I T Y - C A L I F O R N I A UNIVERSITY,

LAWRENCE L IVERMORE LABORATORY L A L L

6976. .' Date August 1978 111110 122310 326000 511120 820000 870098 Spatial Distribution Measurements of Fission Neutrons in

Water as an Oxygen Data Test. Green, L.; Ullo, J.J. NUCL. SCL ENG., 67(2), 172-183 BETTIS

7069 Date January 1977 .. 111110 32A000 423140 511110 511120 793000 795254



WASHINGTON, D.C. 20402 N A V Y


Energy Distributions in Nuclear Reactor Expei:merits. Yegorov, Yu.A.; Pankrat'yev, Yu.V. E R D A - T R - 1 2 5 , PP. 176-190 A V A I L A B I L I T Y - N T I S RUSSIA

7120 Date July 1976 111110 421150 511120 861000 870013 870022 Application of Hydrogen Spectrometer for Spectral Analysis


Pankrat'yev, Yu.V. E R D A - T R - 1 2 5 , PP. 199-206 A V A I L A B I L I T Y - N T I S RUSSIA


with He**3-Spectrometer in Shield Materials. Yegorov, Yu.A.; Zharkov, V.P.; Orlov, Yu.V.

ERDA-TR-125 , PP. 225-230 A V A I LABI L IT Y - NTIS RUSSIA


Spectrometer by Monte Carlo Method. Yegorov, Yu.A.; Zharkov, V.P.; Orlov, Yu.V. ERDA-TR-125 , PP. 231-239 A V A I L A B I L I T Y - N T I S RUSSIA

7127 Date July 1976 111110 112500 421150 511120 521230 853100 853200

853300 853400 853500 853600 853700 Analysis of the Shielding Properties of Various Concretes. Veselkin, A.P.; Voskresenskiy, Ye.V.; Yegorov, Yu.A.;

Pankrat'yev, Yu.V.; Piskunov, V.I.; Staurin, N.V. • ERDA-TR-125 , PP. 273-290 A V A I L A B I L I T Y - N T I S RUSSIA

8112 Date 1978 010000 111110 111220 410000 423110 423120 423130

423135 423140 511120 O \> An International Neutron Dosimetry Intercomparison. ICRU / / ICRU-27 A V A I L A B I L I T Y - I C R U PUBLICATIONS, P.O. BOX

30165, WASHINGTON, D.C. 20014 , ICRU

8375 Date February 1978 111210 421160 329000 511120 861000 870022 Pulsed Sphere Measurements for Weapons and Fusion

Reactor Design. UCRL-52000-78-2 , PP.9-14 AVAILABIL ITY-DEP. , NTIS L A L L

8428 Date October 1978 111210 329000 32A000 422110 511120 870003 881000 Trit ium Production in a Sphere of 6 - L i D Irradiated by

14-MeV Neutrons. Hemmendinger, A.; Ragan, C.E.; Shunk, E.F/; Ellis, A.N.;

Anaya, J.M.; Wallace, J.M. ^ LA-7310 ,. A V A I L A B I L I T Y - N T I S LOASL

212'

8530 Date December 1978 111220 422140 511120 843000 842000 861000 Shielding for Neutron Radiotherapy Sources Created by the

Be(d,n) Reaction. Smathers, J.B.; Graves, R.G.; Wilson, W.B.; Almond, P.R.;

Grant, W.H.; Otte, V.A. H E A L T H PHYS., 35(6), 807-816 U - T X

8625 Date 1977 111110 421130 421140 511120 Neutron Intercomparisons on Nuclear Reactor in the

USSR. Vasilyev, R.D.; Grigoryev, E.I.; Jarina, V.P. EUR-5667E/F,PT.I , PP.823-847;



RUSSIA

8636 Date 1977 111110 020000 32A000 421140 511120 713000 810000 Fast Neutron Spectrum and Dosimetry Studies in the Cou-

pled Fast Reactivity Measurements Facility. Rogers, J.W.; Harker, Y.D.; Millsap, D.A. EUR-5667E/F.PT.I I , PP.277-295;



AEROJE



Fischer, A.; Nolthenius, H.J.; Zijp, W.L. EUR-5667E/F.PT.I1, PP.349-380;

CONF-750935.PT.II, PP.349-380 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


NETHER

8859 Date September 1978 122310 111210 329000 421130 421200 511120 512220


Fusion-Fission Hybrid Reactors. Hansen, L.F.; Wong, C.; Komoto, T.; Pohl, B.A. CONF-780921, PP.766-771 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL ,

75775 PARIS CEDEX 16, FRANCE

L A L L

8916 Date May 1979 421160 511120 861000 The Transmission of Neutrons Through I ron-56 at 24.37

keV. Liou, H.I.; Chrien, R.E.; Block, R.C.; Singh, U.N. NUCL. SCL ENG., 70(2), 150-154 BROOKH

,9060 Date June 1979 111220 329000 421160 511120 853500 Attenuation of Fast Neutrons in Ilmenite Concretes. Adams, R.J.; Lokan, K.H. H E A L T H PHYS., 36(6), 671-678 C A N A D A

9142 Date September 1979 111220 421130 421200 511120 512110 329000 870006 Penetration of Secondary Neutrons and Photons from a

Graphite Assembly Exposed to 52 -MeV Protons. Shin, K.; Uwamino, Y.; Yoshida, M.; Hyodo, T.; Nakamura,

T. NUCL. SCL ENG., 71(3), 294-300 JAPAN

9188 Date October 1979 111220 421130 423135 423120 511120 717000 D - D Neutron Measurements on a 40-kV, 6 0 - A Neutral

Beam Test Facility. Kim, J.; Mihalczo, J.T. O R N L / T M - 7 0 1 6 AV A l L A B I L I T Y - NTIS O A R N L

923 1 Date Apri l 24, 1979 010000 020000 410000 511120 551120 Nuclear Criticality Experiments from 1943 to 1978, an

Annotated Bibliography: Volume 1, Main Listing. Koponen, B.L.; Wilcox, T.P.; Hampel, V.E. UCRL-52769, VOL.I A V A I L A B I L I T Y - N T I S L A L L

923 2 Date Apri l 24," 1979 010000 020000 410000 511120 551120 Nuclear Criticality Experiments from 1943 to 1978, an


213'

9289 Date 1978 111220 220000 329000 421130 51U 20 820000 In-Phantom Neutron Spectrometry: A Comparison of

Experiment and Calculation. Harrison, K.G.; Taylor, A.J.; Holt, P.D.; Boot, S.J. EUR-5848,PP.411 -423; CONF-770597,PP.411 -423 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


E N G L A N

9293 Date 1978 111110 220000 421150 511120 Evaluation of Results of the European Neutron Dosimetry


lief, J. EUR-5848,PP.899-915; CONF-770597,PP.899-915 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


NETHER

9295 ( Date 1978 „ 111110 410000 42006'0 511120 European Neutron Dosimetry Intercomparison Project

(ENDIP). Results and Evaluation. Broerse, J.J.; Burger, G.; Coppola, M. (Eds.) EUR-6004 A V A I L A B I L I T Y - D E P . , NTIS (U.S. SALES ONLY) NETHER



Harrison, R.C. WWD NR.27 A V A I L A B I L I T Y - WEHRWISSENSCH AFTLICH E

DIENSTSTELLE DER BUNDESWEHR FUR ABC-SCHUTZ , D 3042 MUNSTER, G E R M A N Y

GERMAN



Piesch, E.; Burgkhardt, B.; Hofmann, I. KFK-2847 A V A I L A B I L I T Y - KERNFORSCHUNGSZENTRUM

KARLSRUHE (F.R. GERMANY)

GERMAN

9455 Date 1979 ,111110 21,0000 861000 422110 511120 The Determination of Fast Neutron Fluence in Radiation

Stability Tests of Steel Samples. Hogel, J.; Vespalec, R. ZJE-237 A V A I L A B I L I T Y - S K O D A WORKS, NUCLEAR

POWER CONSTRUCTION DEPT., INFORMA-T ION CENTRE, PLZEN - CZECHOSLOVAKIA

CZECHO

One Dimension - Gamma-Ray - Pr imary -Calculation


6869 Date May 1978 112200 329000 512110 512210 820000 861000 870013

870082 Shielding Study of Bremsstrahlung in Bulk Media with Elec-

trons. Part II: Spatial Bremsstrahlung Distribution in 0 Water, Aluminum, Iron and Lead Bombarded by 22

MeV Electrons. Nakamura, T.; Hirayama, H.; Shin, K. NUCL. INSTRUM. METHODS, 151(1,2), 277-284 JAPAN

7108 '.' Date July 1976 112B00 329000 512110 861000 Investigating the Field of Scattered Radiation at Great Dis-

tances From the Source. Zolotukhin, V.G.; Ksenofontov, A.I.; Panchenko, A.M.;

Sinev, V.N. ERDA-TR-125 , PP. 92-99 A V A I L A B I L I T Y - N T I S RUSSIA

8095 Date September 1978 112B00 512110 632110,853100 Berger Coefficients for the, Eisenhauer-Simmons

Gamma-Ray Buildup Factors in Ordinary.Concrete. (Tech. Note)

Metghalchi, M. NUCL. SG ' ^ 'NG. , 67(3), 341-342 IRAN ' / ' £


Deposition from Scattered Gamma Rays.

214'

Malik, J.S.; Cashwell, E.D.; Schrandt, R.G. L A - 7 3 8 6 - M S A V A I L A B I L I T Y - L O S ALAMOS SCIENTIFIC LAB.,


LOASL

8197 Date January 1976 111130 112120 112130 113100 512110 512210 632110

795179 830000 Version 4 of ATR (Air Transport of Radiation). Huszar, L.; Woolson, W.A.; Straker, E.A. DNA-3995F AV A l L A Bi L ITY - NTIS SCA

8199 Date August 1977 112500 111500 112B00 32AOOO 311000 511110 512110

795254 853100 Neutron- and Gamma-Ray Transport Calculations of

Dose Transmission Factors in Concrete. Engstrom, G.; Lefvert, T. FOA RAPPORT C 20195-A2 AV A ILAB I L ITY - FORSV ARETS FORSKNINGSAN-

STALT, HUVUDAVDELNING 2, 104 50 STOCKHOLM

SWEDEN

8689 Date March 1979 112B00 512110 632110 820000 861000 870082 Gamma-Ray Dose Rate Conversion and Buildup Factors^

(Tech. Note) Shure, K. NUCL. SCL ENG., 69(3), PP.432-436 BETTIS

8690 Date March 1979 112B00 512110 632110 853100 Tchebycheff-Fitted Berger Coefficients for Eisen-

hauer-Simmons Gamma-Ray Buildup Factors in Ordinary Concrete. (Tech. Note)

Chilton, A.B. yNUCL. SCL ENG., 69(3), PP.436-438

1 - I L

8920 Date May 1979 112B00 512110 632110 820000 861000 870013 On the Polynomial Form of Gamma-Ray Buildup Factor

Functions. Q; Metghalchi, Ml. a ^ NUCL. SCL ENG., 70(2), 207-209 IRAN o o

9071 Date 1977 111110 112110 122110 328000 329000 511110 512110


Transport. De Gangi, N.L. THESIS A V A I LABIL ITY - M A T H E M A T I C A L APPLICA-


M A A G H

^ 9099 Date April 1978 1I2B00 329000 510000 512110 795166 830000 Time-Dependent Dose Rate and Compton Electron Gener-

ation from Mono-Energetic Gamma Sources in Homogeneous Air.

Engstrom, G. FOA RAPPORT C 20236-A2 AVAILAB IL ITY-FORSVARETS FORSKNINGSAN-

STALT, N A T I O N A L DEFENSE RESEARCH INSTITUTE, S-104 50 STOCKHOLM 80, SWE-DEN "

SWEDEN

9142 Date September 1979 IJ1220 421130 421200 511120 512110 329000 870006 Penetration of Secondary Neutrons and Photons from a

Graphite Assembly Exposed to 52-MeV Protons. Shin, K.; Uwamino, Y.; Yoshida, M.; Hyodo, T.; Nakamura,

T. NUCL. SCL ENG., 71(3), 294-300 JAPAN

9185 Date August 1979 112720 512110 329000 820000 User's Manual for PHOEL-2 , a Monte Carlo Computer


Turner, J.E.; Hamm, R.N:; Wright, H.A.; Modolo, J.T.;0

Sordi, G.M.A.A. ORNL /TM-6954 A V A I L A B I L I T Y - N T I S $4.50 OARNL

9192 Date May 10, 1977 111110 111210 112110 32A000 511110 512110 512210



Straker, E.A.; Gritzner, M.L.; Harris, L.,Jr.; Schanzler, L. S A I - 7 7 - 6 5 7 - L J

215'

A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, INC. , P.O. BOX 2351, 1200 PROSPECT ST., L A JOLLA, C A L I F O R N I A 92037

SCA

9634 Date March 1980 512110 632110 853100 Concrete Buildup Factors Based on the American National

Standard for F lux - to -Dose-Rate Conversion. (Let-ter to the Editor)

Chilton, A.B.; Brown, R.W. N U C L . SCL ENG., 73(3), 301 U - I L

EPRI

6869 Date May 1978 112200 329000 512110 512210 820000 861000 870013


trons. Part I I : Spatial Bremsstrahlung Distribution in Water, Aluminum, Iron and Lead Bombarded by 22 MeV Electrons.

Nakamura, T.; Hirayama, H.; Shin, K. NUCL. I N S T R U M . METHODS, 151(1,2), 277-284 JAPAN

9730 Date January 1980 112B00 327000 512110 632110 820000 830000 861000 Photon Point Source Buildup Factors for Ai r , Water, and

Iron. (Tech. Note) Chilton, A.B.; Eisenhauer, C.M.; Simmons, G.L. N U C L . SCL ENG., 73(1), 97-107 U - I L

One Dimension - Gamma-Ray - P r imary -Experiment


9328 Date February 1979 o 111110 112110 420000 421200 511120 512120 810000 Measurements of the Free Field Radiation Environment at



DIENSTSTELLE DER " BUNDESWEHR FUR A B C - S C H U T Z , D 3042 MUNSTER, G E R M A N Y

G E R M A N

One Dimension - Gamma-Ray -Secondary - Calculation


/ /

6873 Date June 1978 111110 112400 421120 421130 795066 512210 512220

861000 870098 Measurement and Calculations of Californium - 262 Fission

Neutron-Induced Gamma Yields in Iron. Jiang, S.H.; Werle, H. NUCL. SCL ENG., 66(3), 354-362 G E R M A N

6875 Date June 1978 111210 421160 511120 512210 830000 Transport of Neutron and Secondary Gamma Radiations

Through a Liquid Ai r Sphere Surrounding a 1 4 - M e V Neutron Source. (Tech. Note)


NUCL. SCL ENG., 66(3), 428-433 L A L L

7114 Date July 1976 112500 423250 32A000 511110 512210 512220 853800



V.V.; Khokhlov, V.F.; Tsypin, S.G. E R D A - T R - 1 2 5 , PP. 145-151 A V A I L A B I L I T Y - N T I S RUSSIA

6746 Date September 1977 111110 112110 112400,112500 32A000 511110 551110


Damage Studies. Gritzner, M.L. ; Simmons, G.L.; Albert, T.E.; Straker, E.A. EPRI - NP -152, F I N A L REPORT A V A I L A B I L I T Y - S C I E N C E APPL ICATIONS INC.,

LA JOLLA, CALIF .

7129 Date March 1977 111130 111400 122110 122210 32AOOO 511110 512210

830000 853100 810000 Production and Testing of the D N A, Few-Group Coupled

Neutron-Gamma Cross-Section Library. Bartine, D.E.; Knight, J.R.; Pace, J.V.,II I ; Roussin, R. O R N L / T M - 4 8 4 0 A V A I L A B I L I T Y - D E P . , NT IS S5.50 O A R N L

216'



Reactor Shielding Experiments. Seki, Y. ; Santoro, R.T.; Oblow, E.M.; Lucius, J.L. O R N L - 5 4 6 7 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8035 Date August 1978 111220 122110 32AOOO 511110 853900 853700 861000


Energies to 60 MeV. Alsmiller, R,G.',Jr. 3> H O R N L / T M - 6 4 8 6 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

One Dimension - Gamma-Ray -Secondary - Exper iment


6472 Date Dec. 1977&Jtow» 112400 112500 512220 820000 861000 870082 * l i Secondary Gamma Radiation Study in Reactor Shielding. Abagjan, A.A. ; Gasnikov, N.K. ; Germogenova, T.A.;

Bubinin, A.A.; Zhuravlyov, V.I.; Kolcvatov, Yu.J.; Kurachenko, Yu.A.; Mashkovich, V.P.; Sakharov, V.K.

CONF-770401, PP.913-921 A V A l L A B I L I T Y - S C I E N C E PRESS, 8 BROCKSTONE

DR., P R I N C E T O N , NJ 08540 RUSSIA

8197 Date January 1976 111130 112120 112130 113100 512110 512210 632110

795179 830000 Version 4 of A T R (A i r Transport of Radiation). Huszar,CL.; Woolson, W.A.; Straker, E.A. D N A - 3 9 9 5 F A V A I L A B I L I T Y - N T I S SCA

8565 Date 1977 111210 32AOOO 329000 511110 512210 830000 853100


Facility. ° Peng, W.H.; Celnik, J. CONF-771029,VOL.11, PP.1704-1706 A V A I L A B I L I T Y - I E E E SERVICE CENTER, S INGLE

P U B L I C A T I O N SALES DEPT., 445 HOES LANE, P I S C A T A W A Y , N.J. 08853

BURNS

9192 Date May 10, 1977 111110 111210 112110 32AOOO 511110 512110 512210


the Californium Tank Experiment for Comparison with 2" x 2" N E - 2 1 3 Detector Measurements.

Straker, E.A.; Gritzner, M.L. ; Harris, L ,Jr . ; Schanzler, L. S A I - 7 7 - 6 5 7 - L J A V A I L A B I L I T Y - S C I E N C E APPL ICATIONS, INC.,

P.O. BOX 2351, 1200 PROSPECT ST., L A JOLLA, C A L I F O R N I A 92037 f.

SCA , o

6841. . .' j ^ . . Date 1978 112120 421200 512220 870092 870098 Fission Product Yield Ratios for Uranium-235 Fission by

Thermal and Cal i fornium-252 Neutrons. Debertin, K. ^ I A E A - 2 0 8 , VOL.11, PVP.261-263 A V A I L A B I L I T Y - i i ^ S M I C R O F I C H E C L E A R I N G -

HOUSE G E R M A N

* 6873 Date June 1978 111110 112400 421120 421130 795066 512210 512220

861000 870098 Measurement and Calculations of Cal i fornium-262 Fission

Neutron-Induced Gamma Yields in Iron. Jiang, S.H.; Werle, H. N U C L . SCI. E N G , 66(3), 354-362 G E R M A N

7114 Date July 1976 112500 423250 32A000 511110 512210 512220 853800

861000 Investigation of the Field of Capture Gamma-Radiat ion in


V.V.; Khokhlov, V.F.; Tsypin, S.G. E R D A - T R - 1 2 5 , PP. 145-151 A V A I L A B I L I T Y - N T I S RUSSIA

8502 Date January 1979 112120 510000 512220 870092 870094 Fission Product Gamma Spectra. Jurney, E.T.; Bendt, P.J.; England, T.R. L A - 7 6 2 0 - M S A V A I L A B I L I T Y - N T I S L O A S L (f

217 (i

8859 Date September 1978 , 122310 111210 329000 421130 421200 511120 512220


Fusion-Fission Hybrid Reactors. Hansen, L.F.; Wong, C.; Komoto, T.; Pohl, B.A. CONF-780921, PP.766-771 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL,


One Dimension - X-Ray - P r imary -o Experiment


8983 . Date March 1979 113100 513120 750000 853100 Attenuation of Primary and Leakage Radiation in Concrete

for X-Rays from a 10 MV Linear Acceler 'f*r. Tochilin, E.; LaRiviere, P.D. H E A L T H PHYS., 36(3), 387-392 V A R I A N ;

8984 1 Date May 1979 113100 423300 513120 760000 885000 ' o Use of Gypsum Wallboard for Diagnostic X - R a y Protec-

tive Barriers. Glaze, S.A.; Schneiders, N.J.; Bushong, S.C. H E A L T H PHYS., 36(5), 587-593 U - T X

r8985 Date May 1979 113100 423300 513120 760000 885000 Attenuation Characteristics of Gypsum Wallboard. Christensen, R.C.; Sayeg, J.A. H E A L T H PHYS., 36(5), 595-600 U - K Y

One Dimension - X-Ray - Secondary and Bremss t r ah lung


8919 Date May 1979 513200 ,. Electron Transport in One-Dimensional Finite Systems. Gupta, S.K.; Prasad, M.A. NUCL. SCI. ENG., 70(2), 192-200 IND IA

9001 Date July 1979 513200 795130 „ " , On the Validity of the Extended Transport Cross-Section

Correction for Low-Energy Electron Transport. (Tech. Note)

Morel, J.E. NUCL. SCI. ENG., 71(1), 64-71 SANDIA "

One Dimension - P l a sma - P r imary -Calculation


6242 Date 1977 121300 122115 32A100 514110 717000 Neutral Hydrogen Transport in a Two-Dimensional Toroi-

dal Plasma Using Multigroup, Discrete Ordinates Methodology. >

Wienke, B.R.; Miller'/W.R.,Jr.; Seed, T.J.; Rood, P.L. L A - U R - 7 7 - 8 3 9 ,, A V A I L A B I L I T Y - T H E O R E T I C A L DIV., UNIV . OF,

CALIF., LOS ALAMOS SCIENTIFIC LABORATO-RY, LOS ALAMOS, NEW M E X I C O 87545

LOASL

In te r face Effects - Albedo and Scat te r ing - Neutron - Calculation


6473. . I . . Date Dec. 1977' ^ 521210 521110 " Neutron Quasibledos from Plane Reflectors. Abagjan, A.A.; Germogenova, T.A.; Dubinin, A.A.; Zhurav-

lyov, V.I.; Klimanov, V.A.; Mashkovich, V.P.; Stroganov, A.A.

CONF-770401, PP.922-930 A V A I L A B I L I T Y - S C I E N C E PRESS, 8BROCK.STONE

DR., PRINCETON, NJ 08540 R U S S I A „

7085 Date January 1977c? 111110 329000 511110 521110 795171 795017 810000 Neutron Dose Evaluation Using Calculated Neutron Spec-


WASHINGTON, D.C. 20402 HUNGAR

218'

8792 Date February 1979 010000 I t 1110 223000 32AOOO 521110 522110 610000


LWRs. Rahn, F.; Ti l l , H. ORNL/RS1C-43.PP.1 -21; ANS/SD-79 /16 ,PP. l -21 A V A I L A B I L I T Y - N T I S EPRI

9724 Date January 1980 111500 329000 521110 853100 795203 793000 Neutron Spectra from Monoenergetic Source Neutrons

After Multiple Reflections Between Plane-Parallel Concrete Interfaces.

Hagan, W.K.; Simmons, G.L. NUCL. SCI. ENG., 73(1), 3 5 - 4 L SCA . ' f

In te r face Effects - Air Over Ground -Neutron - Calculation


8212 Date October 1978 010000 111130 112130 220000 521120 522120 Organ Dose Estimates for the Japanese Atomic- Bomb Sur-

vivors. Kerr, G.D. ORNL-5436 A V A I L A B I L I T Y - N T I S $5.25 * O A R N L

A V A I L A B I L I T Y - N T I S BANW

6247 Date December 1977 111210 32AOOO 210000 521130 522130 5 • U00 5jl?fl00



6522 Date January 1978 111210 122110 122310 32A000 521130 717000 795042


Ncutronics Data. (Thesis) Reupke, W,A. L A - 7 0 6 7 - T A V A I L A B I L I T Y - N T I S LOASL


Source, INS. Battat, M.; Dierckx, R.; Emigh, C.R. L A - U R - 7 7 - 1 0 5 4 : CONF-770523-2 A V A I L A B I L I T Y - D E P . , NTIS LOASL


Plant. Kukhtevich, V.I.; Goryachev, I.V.; Trykov, L.A. BOOK ( IN RUSSIAN) A V A I L A B I L I T Y - A T O M I Z D A T , MOSCOW RUSSIA

In te r face Effects - Laminar Laye r s -Neutron - Calculation


6205 Date October 1975 111700 112940 32AOOO 329000 521130 522130 712000

810000 795217 795254 795291 Shielding Analysis for the Sealed Storage Cask Concept. Zimmerman, M.G. BNWL-1953

6627 Date March 1978 122310 312000 521130 719A00 870092 870013 870001


for the T R X - 2 Thermal Lattice. Tomlinsoti, E.T.; Lucius, J.L.; Drischler, J.D. ORNL-5336; ENDF-253 AVAJ L A B I L I T Y - N T I S $8.00 O A R N L

6657 Date November 1977 I l ' u i O 521130 551110 329000 795203 870090 870092

870093 810000 Monte Carlo Calculations of Time-Dependent Ncptuni-

um-237 and Uranium-235 Fission Rates in a Pulsed Thorium Assembly.

McGregor, B.J. AAEC/E-432 A V A I L A B I L I T Y - A U S T R A L I A N ATOMIC ENERGY

COMMISSION, RESEARCH ESTABLISHMENT, LUCAS HEIGHTS

219'

AUSTRA




RESEARCH FOUNDATION (ECN), 3 WESTERDUINWEG, PETTEN (NH) , T H E NETH-ERLANDS

NETHER

6690 Date February 1978 111220 122110 32A000 421000 521130 551110 760000


Below 60 MeV. Wilson, W.B. L ' \ 7 1 5 9 - T / ! I L A B I L I T Y - N T I S L ,'SL

6691 Date March 1978 111210 122110 521130 522130 717000 793000 810000 Riggatron Nucleonics: One-Dimensional Analysis. Wienke, B.R.; Dudziak, D.J.; Bosler, G.E. L A - 7 1 8 3 - M S A V A I L A B I L I T Y - N T I S LOASL

6734 Date May 1978 111210 122310 312000 521130 795204 717000 870006

870092 861000 Cross-Section Sensitivity Analysis of 235-U and 238 -U

Fission Rates Measured in a Graphite-Reflected Lith-ium Assembly. (Tech. Note)

Seki, Y.; Maekawa, H. NUCL. SCI. ENG., 66(2), 243-251 JAPAN

7020 Date September 1976 111210 111110 329000 521130 522130 717000 810000 Neutronic Study of a Laser Fusion Hybrid Reactor Design. Hansen, L .F.; Maniscalco, J.A. CONF-760935-P2, PP. 677-688; UCRL-78069 A V A I L A B I L I T Y - N T I S L A L L

7022 Date September 1976 111110 111210 32A000 521130 717000 810000 870090

870092 The Quality of Fissile Fuel Bred in a Fusion Reactor Blan-

ket. . . / V Leonard, B.R.,Jr.; Jenquin, U.P. CONF-760935-P2, PP. 711-722 i!

A V A I L A B I L I T Y - N T I S BANW

7025 Date September 1976 111210 521130 717000 870006 First Wall Studies of a Laser-Fusion Hybrid Reactor

Design. Hovingh, J. CONF-760935-P2, PP. 765-773; UCRL-78090 A V A I L A B I L I T Y - N T I S L A L L

7027 Date September 1976 111 110 111210 32A000 521130 717100 810000 793000

795254 Fusion - Fission Neutronics Calculations for the Laser Sole-

noid. Woodruff, G.L.; Quimby, D.C. CONF-760935-P2, PP. 787-798 A V A I L A B I L I T Y - N T I S MA.SN

7028 Date September 1976 010000 111210 210000 32A000 329000 531000 532000



7035 Date September 1976 111110 111210 521130 522130 717100 32A000 810000

793000 795254 Natural-Uranium Light-<Water Breeding Hybrid Reac-

tors. Greenspan, E.; Schneider, A.; Filai, D.; Levine, P. CONF-760935-P3, PP. 1061-1073 A V A I L A B I L I T Y - N T I S ISRAEL

7042 Date September 1976 ^010000 111210 112760 223000 210000 521130 522130

531000 532000 717000 795254 810000 0

Radioactivity and Associated Problems in Thermonuclear Reactors.

220 o

Vogelsang, W.F. CONF-760935-P4, PP. 1303-1318; U W F D M - 1 7 8 A V A I L A B I L I T Y - N T I S U - W I



mental Power Reactor. Simmons, E.L.; Gerstl, S.A.W.; Dudziak, D.J. L A - 6 9 4 2 - M S A V A I L A B I L I T Y - N T I S $5.00 LOASL

7074 Date January 1977 010000 111110 32A000 325000 32F000 521130 713000

810000 Neutron Transport Studies in Fast Reactor Shields. Vaidyanathan, R.; Murthy, K.P.N.; Singh, R.S. NBS SPEC. PUB. 461, PP. 163-165 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


7098 Date July 1976 111110 112110 112400 112500 325000 521130 522130

632110 820000 An Integrated Method of Calculating Reactor Shielding. Veselkin, A.P.; Gur'yeva, N.A.; Netecha, M.Ye; Nikitin,

A.V. E R D A - T R - 1 2 5 , PP. 6 -10 A V A I L A B I L I T Y - N T I S RUSSIA


tions. Gogotova, L.G.; Nikitin, A.V. E R D A - T R - 1 2 5 , PP. 11-16 A V A I L A B I L I T Y - N T I S RUSSIA

7106 r Date July 1976 111110 32B000 521130 522130 620000 810000 Optimum Multilayer Shadow Shielding for a Reactor. Sakovich, V.A.; Sakharov, V.M. E R D A - T R - 1 2 5 , PP. 79-87 A V A I L A B I L I T Y - 1 9 7 6 RUSSIA

7124 Date July 1976 111110 422140 430000 521130 841000 Calculator of the Sensitivity of a Spherical Neutron Detec-

tor. Utkin, V.A. E R D A - T R - 1 2 5 , PP. 240-250 A V A I L A B I L I T Y - N T I S RUSSIA

7130 Date March 1977 111210 32AOOO 521130 522130 531000 532000 717000

795254 810000 Neutronics and Photonics Calculations for the Tokamak

Experimentation Power Reactor. Santoro, R.T.; Baker, V.C.; Barnes, J.M. O R N L / T M - 5 4 6 6 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8135 Date August 1978 111210 521130 522130 532000 717000 795323 Nucleonic Design for a Compact Tokamak Fusion Reactor

Blanket and Shield. Cheng, E.T.; Maynard, C.W.; Vogelsang, W.F.; Klein, A.C. U W F D M - 2 5 6 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,

NUCLEAR ENGINEERING DEPT., UNIVERSITY OF (.WISCONSIN, MADISON, WISCONSIN 53706

U - W I


Blanket. Perry, R.T.; McKinnon, M.A.; Teofilo, V.L.; Aase, D.T. B N W L - S A - 6 4 2 0 ; CONF-771029-221 A V A I L A B I L I T Y - D E P . , NTIS BANW

8192 Date 1978 111110 122310 312000 521130 713000 870090 870092 Nuclear Data Sensitivity Coefficients for a

(233-U — 232-Th) Fueled LMFBR. Turski, R.B.; McKnight, R.D. CONF-780401 -15 A V A I L A B I L I T Y - D E P . , NTIS ARGONN

8193 Date 1978 111110 122310 312000 32AOOO 521130 713000 794000 Uncertainties in the Breeding Ratio of a Large LMFBR. Marable, J.H.; Weisbin, C.R. CONF-780401 -16

221'

A V A I L A B I L I T Y - D E P . , NTIS O A R N L



Ragheb, M.M.H. ; Gohar, YiM.; Maynard, C.W. U W F D M - 1 9 2 A V A I L A B I L I T Y - F U S I O N TECHNOLOGY PRO-

GRAM, N U C L E A R ENGINEERING DEPT., UNIVERSITY OF WISCONSIN, MADISON, WIS-CONSIN 53706

U - W I


nal-Source-Driven Multiplying Systems. Ragheb, M.M.H.; Maynard, C.W. U W F D M - 2 6 5 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,


U - W I

8278 Date 1978 111210 32AOOO 329000 521130 522130 717000 810000 Scoping Nucleonic Studies for the Riggatron Fusion Reactor

Concept. Wienke, B.R.; Dudziak, D.J.; Bosler, G.E. L A - U R - 7 8 - 9 6 4 ; CONF-780508-5 A V A I L A B I L I T Y - D E P . , NTIS LOASL

8373 i Date January 1978 111110 111210 32AOOO 521130 717000 795254 810000 TCT Hybrid Preconceptual Blanket Design Studies. Aase, D.T.; Bampton, M.C.C.; Doherty, T.J.; Leonard, B.R.;

McCann, R.A.; Newman, D.F.; Perry, R.T.; Stewart, C.W.

PNL-2304 A V A I L A B I L I T Y - B A T T E L L E PACIFIC NORTH-

WEST LAB. c BANW

8421 Date August 1978 111110 122310 521130 810000 Integral Determination of RP Neutron Cross Sections. Bustraan, M. IAEA-213 , VOL.11, PP.627-675 A V A I L A B I L I T Y - I A E A (MF O N L Y )

NETHER


(Using the Baker Model). Voropaev, A. I.; Van'kov, A.A.; Tsybulya, A.M. INDC(CCP) - 1 2 5 / L V A V A I L A B I L I T Y - I A E A N U C L E A R DATA SECTION,

K A R N T N E R RING 11, A -1010 V I E N N A U - W I

8459 Date October 1978 111210 112760 112930 220000 223000 521130 531000

532000 795303 795254 717000 810000 32A000, Safety Aspects of Activation Products in a Compact Toka-



ium Fall Laser Fusion Target Chambers. Meier, W.R.; Thomason, W.B. UCRL-80782 A V A I L A B I L I T Y - L A W R E N C E L IVERMORE LABO-

RATORY L A L L

8500 Date June 1977 111 110 122110 324000 326000 327000 820000 861000


ing-Down Kernel: The Computer Code "MAGGIE" . Gado, J.; Keresziuri, A. KFKI -1977-44 A V A I L A B I L I T Y - K O Z P O N T I F I Z I K A I KUTATO


HUNGAR

8509 Date July 1978 111110 312000 32A000 521130 795042 810000 Sensitivity Studies of One-Dimensional Neutronics Calcu-

lations for Prompt Burst Excursion (PBE) Experiments in the Annular Core Pulse Reactor (ACPR).

Varela, D.W.; Williams, D.C. NUREG/CR-0262; SAND78-0 I43 A V A I L A B I L I T Y - N T I S SANDIA

222'

8515 Date January 1979 111110 122110 32A000 521130 522130 794000 122210 Sample Problems for the Novice User of the A M P X - 1 I

System. Ford, W.E.,111; Roussin, R.W.; Pe'trie, L.M.; Diggs, B.R.;

Comolander, H.E. O R N L / C S D / T M - 7 2 ( A M P X - 7 ) A V A I L A B I L I T Y - N T I S $9.25 1

O A R N L

8518 Date January 1979 111210 122310 32A000 521130 551110 717000 793000



Seki, Y.; Santoro, R.T.; Oblow, E.M.; Lucius, J.L. O R N L / T M - 6 6 6 7 A V A I L A B I L I T Y - N T I S $4.00 O A R N L

8563 Date 1977 111210 32A000 521130 717000 795254 810000 A Practical Blanket Design for a Toroidal Fusion Reactor. Bettis, E.S.; Barnes, J.M.; Huxford, T.J.; Liu, K.C.; Santoro,

R.T.; Watts, H.L. CONF-771029,VOL.11, PP.1453-1458 A V A I L A B I L I T Y - I E E E SERVICE CENTER, SINGLE

PUBLICATION SALES DEPT., 445 HOES LANE, P ISCATAWAY, N.J. 08853

O A R N L

8566 Date 1977 111210 32A000 521130 717000 810000 795254 Design of the Blanket and Shield for a High-Field Com-

pact Tokamak Reactor (HFCTR). Cook, D.L.; Lidsky, L.M.; Herring, S.; Stephany, W. CONF-771029,VOL.11, PP.1713- 1717 A V A I L A B I L I T Y - I E E E SERVICE CENTER, SINGLE

PUBL ICAT ION SALES DEPT., 445 HOES LANE, P ISCATAWAY, N.J. 08853

U - M A

8567 Date 1977 111210 223000 521130 522130 717000 795217 795254



U - T X

8588 Date 1977 111110 210000'521130 713000 719AOO 795254 861000

795276 Prediction of Radiation Damage in Structural Materials

Outside the Reactor Core. Hehn, G.; Stiller, P. EUR-5667E/F,PT.I , PP.52-62; CONF-750935,PT.I,


T IONS OF T H E EUROPEAN COMMUNIT IES , BOITE POSTAL 1003 - LUXEMBOURG

G E R M A N

8591 ' Date 1977 111210 210000 421140 430000 717000 521130 795254

793000 795112 810000 Investigation of Neutron Flux Spectral Measurement Tor


Odette, G.R. EUR-5667F./F,PT.I, PP.84-97; CONF-750935,PT.I,


T IONS OF T H E EUROPEAN C O M M U N I T I E S , BOITE POSTAL 1003 - LUXEMBOURG

U - C A

8651 Date February 1979 111110 122310 312000 325000 521130 810000 The Use of Cross-Section Sensitivities in the Analysis of

Fast Reactor Integral Parameters. Collins, P.J.; Lineberry, M.J. ORNL /RS IC -42 , PP.13-23 A V A I L A B I L I T Y - N T I S ARGONN

8652 Date February 1979 111110 122310 312000 713000 794000 521130 32A000 Advances in Fast Reactor Sensitivity and Uncertainty Anal-

ysis. r-Marable, J.H.; Weisbin, C.R. ORNL /RS IC-42 , PP.25-48 A V A I L A B I L I T Y - N T I S O A R N L

8653 Date February 1979 111110 122310 32A000 521130 713000 810000 312000 Controlled Cross-Section Adjustment by Integral Data. Salmi, U.; Wagschal, J.J.; Ya'ari, A.; Yeivin, Y. ORNL/RSIC-42 , PP.49-59 A V A I L A B I L I T Y - N T I S ISRAEL

223'

8658 Date February 1979 111110 122310 210000 421140 430000 521130 810000

870098 Testing of E N D F / B Cross-Section Data in the Californi-

um-252 Neutron Benchmark Field. Mannhart, W. O R N L / R S I C - 4 2 , PP.119-133 A V A I L A B I L I T Y - N T I S G E R M A N

8660 Date February 1979 111110 122310 210000 430000 521130 861000 810000 Varied Applications of a New Maximum-Likel ihood Code

with Complete Covariance Capability. Schmittroth, F. O R N L / R S I C - 4 2 , PP.145-159 A V A I L A B I L I T Y - N T I S H A N F O R

8661 Date February 1979 111110 122310 32A000 312000 210000 521130 810000


N B S - I S N F . Broadhead, B.L.; Marable, J.H. O R N L / R S I C - * 2 , PP.161-178 A V A I L A B I L I T Y - NT IS U - T N

8663 Date February 1979 111210 122310 32A000 312000 521130 551110 717000

vv 795204 795254 795276 810000 The Application of Uncertainty Analysis in Conceptual

Fusion Reactor Design. Wu, T.; Maynard, C.W. O R N L / R S I C - 4 2 , PP.191 -217 ; U W F D M - 2 9 0 A V A I L A B I L I T Y - N T I S U - W I t.

8665 Date February 1979 111110 122310 32A000 312000 521130 795248 High Order Effects in Cross-Section Sensitivity Analysis. Greenspan, E.; Kami, Y.; Gilai, D. O R N L / R S I C - 4 2 , PP.231-249 A V A I L A B I L I T Y - N T I S ISRAEL

8674 Date February 1979 U1110 122310 32AOOO 312000 521130 713000 719A00


Adjustment. Chestnutt, M.M. ; MCracken. A.K.

O R N L / R S I C - 4 2 , PP.363-373 A V A I L A B I L I T Y - N T I S E N G L A N

° \ \ 8736 Date Marchi 1979

111400 112130 .210000 32AOOO 52113U 522130, 551110 552110 552220 830000 851000 853900 795320

Radiation Transport in Earth for Neutron and Gamma Ray Point Sources Above an A i r - G r o u n d Interface,

Lillie, R.A.; Santoro, R.T. O R N L / T M - 6 6 5 5 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8770 Date January 1979 11U10 122110 521130 713000 810000 Comparison of Some Mult igroup Nuclear Data Sets on

Existing Fast Neutron Assemblies. Cuculeanu, V.; Mocioiu, D.; Constantinescu, D. I N D C ( R U M ) - 9 / G V A V A I L A B I L I T Y - I A E A N U C L E A R D A T A SECTION,

K A R N T N E R R I N G 11, A - 1 0 1 0 V I E N N A R O M A N I

8796 Date February 1979 111110 223000 32A000 521130 522130 551110 552210

721100 722100 719A00 795254 795203 795276 810000 Methodology for the Analysis and Design of a PWR Reactor '

Cavity Shield System. Celnik, J. ORNL/RSIC-43 ,PP.54-67 ;

ANS/SD-79/16 ,PP. 54-67 A V A I L A B I L I T Y - N T I S BURNS

8807. Date March 1979 111210 32A000 521130 522130 717100 793000 794000

795254 810000 Nuclear Performance of Molten Salt Fusion-Fission Sym-

biotic Systems for Catalyzed DD and DT Reactors. , Ragheb, M.M.H. ; Santoro, R.T.; Barnes, J.M.; Saltmarsh,

M.J. O R I V L / T M - 6 5 6 0 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8816 Date October 1978 111210 32A000 521130 717100 793000 794000 795254

810000 Neutronics Optimization Studies for a Proliferation Resis-

tant Fuel Assembly from the Fusion-Fission Fuel Factory, S O L A S E - H .

Youssef, M.Z.; Conn, R.W.; Moses, G.A.

224'

U W F D M - 2 6 3 o A V A I L A B I L I T Y - N U C L E A R E N G I N E E R I N G

D E P A R T M E N T , U N I V E R S I T Y OF WISCONSIN, M A D I S O N 53706

U - W I

8819 Date March 1979 111110 32AOOO 521130 793000 795254 870090 870092 . Analysis of a Water Moderated Critical Assembly with

A N I S N - V I T A M I N C. Green, L. WFPS:TME-79 -015 A V A I L A B I L I T Y - F U S I O N POWER SYSTEMS

DEPARTMENT, WESTINGHOUSE ELECTRIC CORPORATION, P.O. BOX 10864, PITTSBURGH, P E N N S Y L V A N I A

WEE

8867 Dale September 1978 111210 122310 32A000 521130 795254 717100 810000

870092 Reproduction of the Weale Experiment Results with Modi-

fied E N D F / B - I V U - 2 3 8 Data. Segev, M.; Krumbein, A. CONF-780921, PP.1028-1032 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,


U 8932 Date January 1979

010000 111210 121100 210000 521130 717000 795217 795254 810000

Transmutation and Activation of Fusion Reactor Wal l and Structural Materials.

Jarvis, O.N. A E R E - R - 9 2 9 8 A V A 1 L A B I L I T Y - H . M . S . O . E N G L A N

8946 Date May 1978 111210 32A000 521130 522130 717100 793000 795254

810000 Evaluation of Potential Blanket Concepts for a Demonstra-

tion Tokamak Hybrid Reactor. Chapin, D.L.; Chi, J.W.H.; Kelly, J.L. CONF-780508,VOL.1, PP.230-238 A V A I L A B I L I T Y - D E P . , NT IS WEE

8948 Date May 1978 111210 32AOOO 521130 717000 795042 810000 Nucleonic Aspects of the ' L INUS ' Imploding Blanket. Dudziak, D.J.

CONF-780508,VOL.1, PP.254-261 A V A I L A B I L I T Y - D E P . , NTIS LOASL

8950 Date May 1978 111210 122310 32A000 521130 522130 620000 717000 A Minimuin-Thickness Blanket/Shield with Optimum

Tr i t ium Breeding and Shielding Effectiveness. Gerstl, S.A.W. CONF-780508,VOL.1, PP.269-278 A V A I L A B I L I T Y - D E P . , NTIS LOASL

9017 Date March 1979 111110 326000 521130 795254 The DPN "Surface Flux" Integral Transport Method with

General P sub N Polynomial Approximation. Stepanek, J. E IR-365 A V A I L A B I L I T Y - E I D G E N O E S S I S C H E S INST.

FUER REAKTORFORSCHUNG, W U E R E L I N G E N ( S W I T Z E R L A N D )

G E R M A N

9030 Date October 1978 111210 210000 32A000 521130 717000 861000 862000

870023 870027 793000 The Effects of F e - N i - C o - V Structural Alloys on Fusion

Reactor Neutronic Performance. Barnes, J.M.; Bishop, B.L.; Santoro, R.T.; Gabriel, T.A. O R N L / T M - 6 5 4 3 A V A I L A B I L I T Y - N T I S $4.00 O A R N L

9057 Date July 1979 111210 329000 521130 717000 717100 793000 810000 Pellet and Pellet-Blanket Neutronics and Photonics for

Electron- Beam - Fusion Microexplosives. Ragheb, M.M.H. ; Moses, G.; Maynard, C.W. U W F D M - 2 9 5 A V A I L A B I L I T Y - F U S I O N E N G I N E E R I N G PRO-

G R A M , N U C L E A R E N G I N E E R I N G DEPT., U N I V E R S I T Y OF WISCONSIN, M A D I S O N W I 53706

U - W I

9069 Date Mid-December 1978 111210 210000 32AOOO 521130 810000 861000 717000

795323 Minimizing Radioactivity and Other features of Elemental

and Isotopic Tailoring of Materials for Fusion Reactors. Conn, R.W.; Okula, K.; Johnson, A.W. NUCL. T E C H N O L O G Y , 41(3), 389-400; ' U W F D M - 3 0 5

225'

U - W I

9072 Date April 1979 111110 325000 329000 521130 713000 Monte Carlo-Based Validation of the

ENDF/MC**2 - I1 /SDX Cell Homogenization Path. Wade, D.C. A N L - 7 9 - 5 A V A I L A B I L I T Y - N T I S $5.25 ARGONN

9306 Date July 1979 111210 329000 521130 717000 793000 794000 795254



Takahashi, A'.; et al. KFK-2832/1 AVAILABIL ITY - KERNFORSCHUNGSZENTRUM


GERMAN

9107 Date June 1979 111110 020000 32A000 325000 521130 795134 795266

713000 793000 794000 SPECTRA-IV, Benchmark Spectra Based on L I B - I V . Kidman, R.B. LA-7861 - M S A V A I L A B I L I T Y - N T I S LOASL

9310 •. . Date August 1979 111210 32AOOO 521130 522130 717000 810000 The Reversed-Field Pinch Reactor (RFPR) Concept. Hagenson, R.L.; Krakowski, R.A.; Cort, G.E.

JLA-7973-MS A V A I L A B I L I T Y - N T I S LOASL

9123.' Date July 1979 111210 32AOOO 329000 521130 522130 717000 795203

795255 795279 810000 Preliminary Studies for the PDX Tokamak Radiation Shield

Design. Grimesey, R.A.; Nigg, D.W.; Scott, A.J.; Wheeler, F.J. TREE-1369 AVAILABIL ITY-DEP. , NTIS $8.00 EDGERT

9325 Date May 1979 11 1210 32AOOO 510000 521130 717000 795180 Neutron Moderation in ICF Pellets and Effects on Damage

and Radioactive Inventory. Beranek, F.; Conn, R.W. UWFDM-310 A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-


U - W I



dent Neutron Transport. Beranek, F.; et al. UWFDM-304 A V A I L A B I L I T Y - N U C L E A R ENGINEERING

DEPARTMENT, UNIVERSITY OF WISCONSIN, MADISON, WI

U - W I

9326 Date 1978 111210 32AOOO 521130 522130 717000 793000 795254

810000 Demonstration Tokamak Hybrid Reactor (DTHR) Blanket

Design Study, December; 1978. Chi, J.W-H. (Ed.) WFPS-TME-106 AVAILAB IL ITY-FUSION POWER SYSTEMS

DEPT., WESTINGHOUSE ELECTRIC CORP., PENN.

WEE


Library (ENDL-78) . Howerton, R.J. UCRL-50400, VOL.15, PT.E A V A l LABI LITY - NTIS L A L L

ft

9342 Date September 1977 111210 32AOOO 521130 522130 793000 795254 717000 Fusion Blankets for Catalyzed D - D and D-,**3He Reac-

tors. p Fillo, J.A.; Powell, J.R. ];) EPRI-ER-536-SR, PP.57-67 ^ AVAILABIL ITY-BROOKHAVEN N A T I O N A L LAB-

ORATORY, UPTON, N Y BROOKH

226

9438 Date October 1979 111210 329000 521130 717000 793000 794000 795254

810000 Fast Rigorous Numerical Method Tor the Solution of the


Takahashi, A.; Rusch, D. KFK-2832 / I I A V A I L A B I L I T Y - K E R N F O R S C H U N G S Z E N T R U M

KARLSRUHE (GERMANY, F.R.) G E R M A N

9448 Date August 1979 111110 122310 32A000 521130 793000 794000 719A00



Jenquin, U.P.; Thompson, J.K.; Trapp, T.J.; Kottwitz, D.A. NUREG/CR-0965; PNL-3071 AVA ILAB IL ITY -DEP. , NTIS, PC A05 /MF A01 PANL

9542 Date September 1979 111210 32A000 717000 521130 522130 810000 First Wall and Cavity Design Studies for a Light Ion Beam

Driven Fusion Reactor. Moses, G.A.; Abdel-Khal ik, S.I.; Drake, D.; Engelstad,

R.L.; Kulcinski, G.L.; Lewis, R.; Lovell, E.; McCarville, T.; Peranich, L.; Peterson, R.R.; Ragheb, M.M.H.; Spencer, R.

U W F D M - 3 2 0 A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-

GRAM, DEPARTMENT OF NUCLEAR ENGINEERING, UNIV. OF WISCONSIN, 'MADI-SON, WI 53706

U - W I o '

9544 Date June 1979 111210 32A000 521130 717100 793000 795254 810000

870094 Parametric Calculations of 239-Pu Breeding in Hybrid

Blankets With and Without Trit ium Breeding. Henderson, D.L.; Moses, G.A. U W F D M - 3 3 4 , A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-

GRAM, DEPARTMENT OF NUCLEAR ENGINEERING, UNIV . OF WISCONSIN, MADI-SON, WI 53706

U - W I

9765 Date December 1978,., 111210 32A000 795254 793000 521130 5221-30 7Tl7000

Thermal-Hydraulic and Neutronic Considerations for Designing a Lithium-Cooled Tokamak Blanket.

Mikic, B.; Todreas, N. COO-2431 - 2 A V A I L A B I L I T Y - D E P . , NTIS, PC A 0 6 / M F A01 U - M A

9826 Date March 1980 111210 32A000 521130 522130 795254 717000 844000 Evaluation of Organic Moderator/Coolants for Fusion

Breeder Blankets. Romero, J.B. A N L / F P P / T M - 1 3 0 A V A I L A B I L I T Y - N T I S , PC A 0 3 / M F A01 ARGONN

9840 Date March 1980 111210 312000 32A000 521130 717000 795254 795204

810000 x

Sensitivity Analysis of Neutronics Calculations in the Pre-liminary Design of JAERI Experimental Fusion Reactor. (Revised)

Yamauchi, M.; Seki, Y.; Iida, H. J A E R I - M -8739 A V A I L A B I L I T Y - D I V I S I O N OF T E C H N I C A L

INFORMATION, JAPAN A T O M I C ENERGY RESEARCH INSTITUTE, T O K A I - M U R A , N A K A - G U N , I B A R A K I - K E N , JAPAN

JAPAN

(I

810000 870003

9869 Date September 1979 111210 32A000 521130 522130 717100 793000 795254 Blanket Design Study for a Commercial Tokamak Hybrid

Reactor (CTHR). Chapin, D.L.; Green, L.; Lee, A.Y.; Culbert, M.E.; Kelly,

J.L. W F P S - T M E - 7 9 - 0 2 1 A V A I L A B I L I T Y - F U S I O N POWER SYSTEMS

DEPT., WESTINGHOUSE ELECTRIC CORPORA-TION, PITTSBURGH, PA

WEE

9897 Date January 1980 111210 32AOOO 521130 717100 793000 795254 810000 Evaluation of DD and DT Fusion Fuel Cycles for Different

{VFusion- Fission Energy Systems. Gohar, Y. A N L / F P P / T M - 1 3 2 A V A I L A B I L I T Y - N T I S , PC A03 /MF A01 ARGONN

0

227 -v. <ly-

9978 Date May 1980 010000 329000 32A000 521130 810000 The Status of Monte Carlo at Los Alamos. Thompson, W.L.; Cashwell, E.D.; Godfrey, T.N.K.; Sch-

randt, R.G.; Deutsch, O.L.; Booth, T:E. LA -8353 -MS; ORNL/RSIC-44 , PP.231-246 A V A I L A B I L I T Y - N T I S $5.25 LOASL

9988 Date August 1980 010000 312000 329000 521130 810000 Monte Carlo Perturbation Theory in Neutron Transport

Calculations. Hall, M.C.G. ORNL/RSIC-44 , PP.47-62 A V A I L A B I L I T Y - N T I S , PC A16 /MF AOL ENGLAN • •

9989 Date August 1980 010000 122310 329^00 521130 795372 795254 Study of Perturbations Using Correlated Monte 'fcarlo

Method. Dejonghe, G.; Gonnord, J.; Nimal, J.C. ORNL/RSIC-44 , PP.63-93 A V A I L A B I L I T Y - N T I S , PC A16 /MF A01 FRANCE

i t

In te r face Eifects - Albedo and Scat ter ing - Neutron - Exper iment


6473 Date Dec. 1977 521210 521110 Neutron Quasibicdos from Plane Reflectors. Abagjan, A. A.; Germogenova, T. A.; Dubinin, A. A.; Zhurav-

lyov, V.I.; Klimanov, V.A.; Mashkovich, V.P.; Stroganov, A.A.

CONF-770401, PP.922-930 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROCKSTONE


6856 Date 1978 111110 220000 423135 521210 Neutron Response of a New Albedo-Neutron Dosimeter. Blackstock, A.W.; Cortez, J.R.; Littlejohn, G.J.; Storm, E. LA-UR-^78-40; CONF-780110-8 AVAILABIL ITY-DEP. , NTIS LOASL

9997 Date August 1980 020000 329000 521130 795187 810000 TRX and UO/sub 2/ Benchmark Criticality Calculations

with S A M - C E . Beer, M. ; Troubetzkoy, E.S.; Lichtenstein, H.; Rose, P.F. ORNL/RSIC-44 , PP.157-167 A V A I L A B I L I T Y - N T I S , PC A16 /MF A01 M A A G

10006 Date August 1980 111220 329000 521130 853100 861000 795372 Experience with TRIPOLI at ORNL. Cramer, S.N.; Roussin, R.W. ORNL/RSIC-44 , PP.295-304 A V A I L A B I L I T Y - N T I S , PC A16 /MF A01 O A R N L

10146 Date Augusl'1980 111210 122310 32A100 521130 717000 810000 SENSIT: A Cross-Section and Design Sensitivity and

Uncertainty Analysis Code. Gerstl, S.A.W. L A - 8 4 9 8 - M S A V A I L A B I L I T Y - N T I S LOASL

8995 Date Apri l 1, 1979 220000 521210 522210 Statistical Errors of Dose Estimation in Personnel Neutron

Monitoring with Albedo Dosimeters. Burgkhardt, B.; Heinselmann, M.; Piesch, E.; Viragh, E. NUCL. INSTRUM. METHODS, 160(3), 533-540 GERMAN

In ter face Effects - Air Over Ground -Neutron - Exper iment


8020 Date December 1977 422120 521220 750000 Measurement of Stray Neutron Doses Around KEK

PS - Facility (1). Miyajima, M.; Hirayama, H.; Hozumi, K.; Miura, S.;

Katoh, K. K E K - 7 7 - 17 A V A I L A B I L I T Y - N A T I O N A L LABORATORY FOR

HIGH ENERGY PHYSICS, O H O - M A C H I , T S U K U B A - G U N , I B A R A K I - K E N , ^ 3 0 0 - 3 2 , JAPAN

JAPAN

228'

In te r face Effects - Laminar Layers -Neutron - Experiment


6517 Date April 16, 1975 111220 421130 430000 521230 522230 853100 861000 Time-Dependent Measurements of Fast-Neutron and


Young, J.C.; Harris,Vl»,Jr.; Bryan, D.E.; Lurie, N.A.; Stein-man, D.K.; Friesenhahn, S.J.; Gober, W.E.; Schanzler, L.

IRT-8025-723 AVAILABIL ITY- INSTRUMENTATION

RESEARCH TECHNOLOGY, 7650 CONVOY COURT, P.O. BOX 80817, SAN DIEGO, CALIFOR-N IA 92138

IRT


u id-A i r Vessel Containing a D - T Neutron Source. Tripler, D.J.; Goldberg, E.; Farley, W.E. UCRL-52334 AVAILABIL ITY-DEP. , NTIS LALL

6899 Date October 1977 111110 122110 421140 430000 521230 719A00 795112

795233 810000 Neutron Metrology in the L.F.R. Neutron Flux Density

Spectrum in the Inner Graphite Reflector of the L.F.R. Zsolnay, E.M. ECN-77-134 (RESTRICTED DISTRIBUTION) AVAILABIL ITY-ST ICHTING ENERGIEONDER-

' 2 0 EK CENTRUM NEDERLAND (ECN), VOORTZETTING V A N DE STICHTING REAC-TOR CENTRUM (RCN), WESTERDUINWEG 3, PETTEN (NH), THE NETHERLANDS

NETHER

7110 Date July 1976 111110 421140 421130 521230 710000 719AOO Investigation of the Absolute Fluxes and Spectra of Fast


Barinov, A.L.; Vikin, V.A.; Glushchenko, A.I.; Yegorov, Yu.A.; Kovalenko, V.V.; Luk'yanov, M.A.; Orlov, Yu.V.; Razumovskiy, M.V.; Tsofin, V.I.

ERDA-TR-125, PP. 106-118 A V A I L A B I L I T Y - N T I S RUSSIA

7111 Date July 1976 111110 421130 421200 521230 522230 710000 719A00


the Novo-Voronezhskaya AES's Second Unit. Glushchenko, A.I.; Orlov, Yu.V.; Satarin, V.Ye. ERDA-TR-125, PP. 119-126 A V A l LABILITY - NTIS RUSSIA


Screens with Various Thicknesses. Yegorov, Yu.A.; Zharkov, V.P.; Orlov, Yu.V. ERDA-TR-125, PP. 157-168 A V A I L A B I L I T Y - N T I S RUSSIA

7127 Date July 1976 111110 112500 421150 511120 521230 853100 853200

853300 853400 853500 853600 853700 Analysis of the Shielding Properties of Various Concretes. Veselkin, A.P.; Voskresenskiy, Ye.V.; fYegorov, Yu.A.;

Pankrat'yev, Yu.V.; Piskunov, V.L; Staurin, N.V. ERDA-TR-125, PP. 273-290 AVAILABIL ITY - NTIS RUSSIA

7033 Date September 1976 111210 32A000 521230 422130 717000 717100 870003


Blanket Assemblies. Maekawa, H.; Seki, Y. CONF-760935-P3, PP. 883-894 A V A I L A B I L I T Y - N T I S JAPAN

8695 Date June 1978 111110 210000 421140 521230 713000 810000 The Zero-Power Basis of Fast Reactor Dosimetry. Sanders, J.E. AEEW-R-1183 A V A I L A B I L I T Y - U K A E A , ATOMIC ENERGY

ESTABLISHMENT, WINFRITH, DORCHESTER, DORSET, GREAT BRITAIN

ENGLAN

229'

8861 Date September 1978 010000 122310 521230 717100 810000 Neutron Data for the Hybrid Reactor Calculation. Markovskii, D.V.; Shatalov, G.E. CONF-780921, PP.783-791 A V A I L A B I L I T Y - O E C D , ANDRE-PASCAL ,

75775 PARIS CEDEXtI6, FRANCE RUSSIA °

8953 Date May 1978 111210 32A000 329000 421130 521230 795203 795254

870003 870006 Measurements and Calculations of Fast Neutron Spectra in

a Graphite-Reflected Lithium Assembly. Itoh, S.; Seki, Y.; Maekawa, H. CONF-780508,VOL. 1, PP.385-393 AVA ILAB IL ITY -DEP. , NTIS JAPAN

(I 8962 v. . . Date Apri l 1979

111110 111600 210000 521230 719A00 795254 861000 793000

Measurement and Analysis of Gamma Ray Induced Con-tamination of Neutron Dosimetry Procedures Used for Reactor Pressure Vessel Applications.

Simmons, G.L. E P R I - N P - 1056 A V A I L A B I L I T Y - S C I E N C E APPLICATIONS,


SCA


Be(d,n) Sources, E /sub d/ = 1 4 - - 4 0 MeV. Greenwood, L.R.; Heinrich, R.R. CONF-790125, PT.A, PP.473-477; J. NUCLEAR


ING COMPANY - AMSTERDAM ARGONN

In te r face Effects - Albedo and Scat ter ing - Gamma-Ray - Calculation


7068 Date January 1977 010000 112B00 310000 522110 522210 610000 810000 Backscattering of Gamma Rays. Hyodo, T. -NBS SPEC. PUBf46f , PP. 110-118

A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO, WASHINGTON, D.C. 20402

JAPAN

7071 Date January 1977 112B00 329000 421200 522110 522210 810000 Backscattering of Gamma Rays by Barriers from Various

Media. Pozdneyev, D.B. u

NBS SPEC. PUB. 461, PP. 129-131 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

WASHINGTON, D.C. 20402 RUSSIA ' M

8389 " Date 1978 112730 329000 522110 522210 870004 870006 853100

861000 870050 870082 Surface Spectral-Angular Distribution of 137-Cs

Gamma Quanta Back Scattered from Different Types of Barriers.

Pozdneev, D.B.; Savyuk, S.N.; Fadeev, M.A. KERNENERGIE, 21(5), 148-149 ( I N RUSSIAN) RUSSIA

8792 Date February 1979 010000 111110 223000 32A000 521110 522110 610000


LWRs. Rahn, F.; Til l, H. ORNL/RSIC-43.PP.1 -21; ANS/SD-79/16.PP.1 - 2 1 A V A I L A B I L I T Y - N T I S EPRI

/ / 8829 Date 1978 112B00 329000 522110 861000 870006 870013 870050

870082 The Calculation of Gamma-Rays Albedo by the

Monte-Carlo Method. Seda, J.; Kluson, J.; Cechak, T. INT. J. APPL. RADIAT. ISOTOP., 29, 419-422 CZECHO

In te r face Effects - Air Over Ground -Gamma-Ray - Calculation


6445 : Date Dec. 1977 632110 522120 The Optimisation of Shielding for Direct-Cycle Steam

Turbine Plant.

- I •ZJ "

230'

Martin, A.; Firmin, G.H.; Eaton, J.R.P. CONF—770401, PP.694-702 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


In t e r f ace Effects - Laminar Laye r s -Gamma-Ray - Calculation


8212 Date October 1978 010000 111130 112130 220000 521120 522120 Organ Dose Estimates for the Japanese Atomic-Bomb Sur-

vivors. Kerr, G.D. ORNL-5436 A V A I L A B I L I T Y - N T I S S5.25 O A R N L


Plant. Kukhtevich, V.L; Goryachev, I.V.; Trykov, L.A. BOOK ( I N RUSSIAN) A V A I L A B I L I T Y - A T O M I Z D A T , MOSCOW RUSSIA

9539 Date October 24, 1979 ^12920 522120 731200

' Fallout Model for System Studies. Harvey, T.F.; Serduke/F.J.D. UCRL-52,858 A V A I L A B I L I T Y - N T I S L A L L

6205 Date October 1975 111700 112940 32A000 329000 521130 522130 712000

810000 795217 795254 795291 Shielding Analysis for the Sealed Storage Cask Concept. Zimmerman, M.G. BNWL-1953 A V A I L A B I L I T Y - N T I S BANW

6247 Date December 1977 111210 32A000 210000 521130 522130 531000 532000


Torus Reactor (EBTR) Reference Design. Santoro, R.T.; Barnes, J.M. O R N L / T M - 6 0 8 5 A V A I L A B I L I T Y - N T I S S4.50 OARNL

6691 Date March 1978 111210 122110 521130 522130 717.000 793000 810000 Riggatron Nucleonics: One-Dimensional Analysis. Wienke, B.R.; Dudziak, D.J.; Bosler, G.E. L A - 7 1 8 3 - M S A V A I L A B I L I T Y - N T I S ° LOASL

9557 Date January 1980 112720 32AOOO 522120 795209 830000 Analysis of 60-Co Gamma-Ray Transport Through Air

by Discrete-Ordinates Transport Codes. Sasamoto, N.; Takeuchi, K. NUCL. TECHNOLOGY, 47(1), ,189- 199 JAPAN (L

7020 Date September 1976 111210 111110 329000 521130 522130 717000 810000 Neutronic Study of a Laser Fusion ,Hybrid Reactor Design. Hansen, L.F.; Maniscalco, J.A. CONF-760935-P2, PP. 677-688; UCRL-78069 A V A I L A B I L I T Y - N T I S L A L L


ited on the Ground. Beck, H.L. E M L -378 A V A I L A B I L I T Y - D O E , NEW YORK, N.Y., ENVI-

R O N M E N T A L MEASUREMENTS LABORATORY

DOE c

7035 Date September 1976 11II10 111210 521130 522130 717100 32AOOO 810000

793000 795254 Natural-Uranium Light-Water Breeding Hybrid Reac-

tors. Greenspan, E.; Schneider, A.; Filai, D.; Levine, P. CONF - 7609 3 5 - PS', PP. 1061 - 1073 A V A I L A B I L I T Y - N T I S

231'

7042 Date September 1976 010000 111210 112760 223000 210000 521130 522130


Reactors. Vogelsang, W.F. CONF-760935-P4, PP. 1303-1318; UWFDM-178 -A V A I L A B I L I T Y - N T I S ° U - W I Vs

7050 Date September 1977 ,111210 122110 122210 32AOOO 312000 521130 522130 " 717000 810000 Cross-Section Sensitivity Analyses for a Tokamak Experi-

mental Power Reactor. Simmons, E.L.; Gerstl, S.A.W.; Dudziak, D.J. L A - 6 9 4 2 - M S A V A I L A B I L I T Y - N T I S $5.00 LOASL

7070 Date January 1977 o 112720 423230 522130 Back-Scattering (Sky Shine) of Gamma Rays from a 650

Curie 60-Co Source<by Infinite Air. Swarup, J.; Ganguly, A.K. NBS SPEC. PUB. 461, PP. 124-128* A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


7098 Date July 1976 111110 112110 112400 112500 325000 521130 522130


A.V. ERDA-TR-125 , PP. 6 -10 A V A I L A B I L I T Y - N T I S RUSSIA

" 7099 Date JSiy 1976 112BOO 111500 322000 330000 521130 522130 820000 Using Korobov's Method in Radiation Shielding Calcula-

tions. Gogotova, L.G.; Nikitin, A.V. ERDA-TR-125 , PP. 11-16 A V A I L A B I L I T Y - N T I S » RUSSIA °

7106 Date July 1976 111110 32B000 521130 522130 620000 810000 Optimum Multilayer Shadow Shielding for a Reactor. Sakovich, V.A.; Sakharov, V.M.

'-A

ERDA-TR-125 , PP. 79-AVAILABIL ITY-1976 RUSSIA

87

7,130 Date March 1977 111210 32AOOO 521130 522130 531000 532000 717000


Experimentation Power Reactor. Santoro, R.T.; Baker, V.C.; Barnes, J.M. o ^ O R N L / T M -5466 « " A V A I L A B I L I T Y - N T I S $4.50 OARNL o

8135 /C5* Date August 1978 111210 521130 522130 532000 717000 795323 Nucleonic Design for a Compact Tokamak Fusion Reactor

Blanket and Shield. t, Cheng, E.T.; Maynard, C.W.; Vogelsang, W.F.; Klein, A.C. UWFDM-256 0

A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM, NUCLEAR ENGINEERING DEPT., UNIVERSITY OF WISCONSIN,' MADISON, WISCONSIN 53706

U - ' W I

8278 Date 1978 111210 32AOOO 329000 521130 522130 717000 810000 Scoping Nucleonic Studies for the Riggatron Fusion Reactor

Concept. Wienke, B.R.; Dudziak, D.J.; Bosler, G.E.

n L A - U R - 7 8 - 9 6 4 ; CONF-780508-5 AVA ILAB IL ITY-DEP. , NTIS LOASL (s.

<3 8515 ; . . Date January 1979

111110 122110 32A000 521130 322130 794000 122210 Sample Problems for the Novice User of the A M P X - I I

System. o Ford, W.E.,III; Roussin, R.W.; Petrie, L.M.; Diggs, B.R.;

Comolander, H.E. O R N L / C S D / T M - 7 2 ( A M P X - 7 ) A V A I L A B I L I T Y - N T I S $9.25*' OARNL y

8567 Date 1977 111210 223000 521130 522130 717000 795217 795254

793000 810000 , Structure Activation in an Experimental Power Reactor. Smith, R.D.; Parish, T.A. C O N F - 771029, VOL. I I , (PP. 1718 - 1722 A V A I L A B I L I T Y - I E E E SERVICE CENTER, SINGLE


-232

U - T X

8736 Date March 1979 1114CI0 112130 210000 32A000 521130 522130 551110


Point Sources Above an Air-Ground Interface. Lillie, R.A.; Santoro, R.T. O R N L / T M - 6 6 5 5 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8796 Date February 1979 111110 223000 32A000 521130 522130 551110 552210


Cavity Shield System. Celnik, J. ORNL/RSIC-43,PP.54-67;

ANS/SD-79/16,PP.54-67 A V A I L A B I L I T Y - N T I S BURNS '

9123 Date July 1979 111210 32A000 329000 521130 522130 717000 795203


Design. Grimesey, R.A.; Nigg, D.W.; Scott, A.J.; Wheeler, F.J. TREE-1369 AVA ILAB IL ITY -DEP. , NTIS $8.00 EDGERT

9193 Date April 27, 1978 111110 111210 421130 430000 312000 32A000 522130



Scott, W.H.,Jr.; Gritzner, M.L.; Albert, T.E.; Hagan, W.K.; Schanzler, L.


P.O. BOX 2351, 1200 PROSPECT ST., LA JOLLA, CAL IFORNIA 92037

SCA

8807 Date March 1979 111210 32A000 521130 522130 717100 793000 794000


biotic Systems for Catalyzed DD and DT Reactors. Ragheb, M.M.H.; Santoro, R.T.; Barnes, J.M.; Saltmarsh,

M.J. O R N L / T M - 6 5 6 0 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8946 Date May 1978, 111210 32A000 521130 522130 717100 793000 795254


tion Tokamak Hybrid Reactor. Chapin, D.L.; Chi, J.W.H.; Kelly, J.L. CONF-780508,VOL.l , PP.230-238 A V A I L A B I L I T Y - D E P . , NTIS WEE

8950 Date May 1978 111210 122310 32AOOO 521130 522130 620000 717000 A Minimum-Thickness Blanket/Shield with Optimum

Tritium Breeding and Shielding Effectiveness. Gerstl, S.A.W. CONF-780508,VOL.l , PP.269-278 A V A I L A B I L I T Y - D E P . , NTIS LOASL

9310 Date August 1979 111210 32AOOO 521130 522130 717000 810000 The Reversed - Field Pinch Reactor (RFPR) Concept. Hagenson, P..L.; Krakowski, R.A.; Cort, G.E. L A - 7 9 7 3 - M S A V A I L A B I L I T Y - N T I S LOASL

9326 Date 1978 111210 32A000 521130 522L30 717000 793000 795254


Design Study, December 1978. Chi, J.W.H. (Ed.) WFPS-TME-106 A V A I L A B I L I T Y - F U S I O N POWER SYSTEMS

DEPT., WESTINGHOUSE ELECTRIC CORP., PENN.

WEE

O 9342 Date September 1977

111210 32A000 521130 522130 793000 795254 717000 Fusion Blankets for Catalyzed D - D and D - * * 3 H e Reac-

tors. Fillo, J.A.; Powell, J.R. EPRI -ER-536 -SR, PP.57-67 A V A I L A B I L I T Y - B R O O K H A V E N N A T I O N A L LAB-


233'

9542 Date September 1979 111210 32AOOO 717000 521130 522130 810000 First Wall and Cavity Design Studies for a Light Ion Beam

Driven Fusion Reactor. Moses, G.A.; Abdel-Khal ik, S.I.; Drake, D.; Engelstad,

R.L.; Kulcinski, G.L.; Lewis, R.; Lovell, E.; McCarvilie, T.; Peranich, L.; Peterson, R.R.; Ragheb, M.M.H.; Spencer, R.


GRAM, DEPARTMENT OF NUCLEAR ENGINEERING, UNIV. OF WISCONSIN, MADI -SON, WI 53706

U - W I

In te r face Effects - Albedo and Scat ter ing - Gamma-Ray - Exper iment


7068 Date January 1977 010000 112B00 310000 522110 522210 610000 810000. Backscattering of Gamma Rays. Hyodo, T. NBS SPEC. PUB. 461, PP. 110-118 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


r;

9765 Date December 1978 111210 32A000 795254 793000 521130 522130 717000

810000 870003 Thermal-Hydraulic and Ncutronic Considerations for

Designing a Lithium-Cooled Tokamak Blanket. Mikic, B.; Todreas, N. COO-2431 - 2 A V A I LAB I L IT Y - D EP., NTIS, PC A06 /MF A01 U - M A

9826 Date March 1980 111210 32A000 521130 522130 795254 717000 844000 Evaluation of Organic Moderator/Coolants for Fusion

Breeder Blankets. Romero, J.B. A N L / F P P / T M - 1 3 0 A V A I L A B I L I T Y - N T I S , PC A03 /MF A01 ARGONN

9869. . V Date September 1979 111210 32A000 521130 522130 717100 793000 795254 Blanket Design Study for a Commercial Tokamak Hybrid




WEE

7071 Date January 1977 112B00 329000 421200 522110 522210 810000 ^ Backscattering of Gamma Rays by Barriers from Various

Media. Pozdneycv, D.B. NBS SPEC. PUB. 461, PP. 129-131 AVA ILAB IL ITY -SUPT . OF DOCUMENTS, GPO,

WASHINGTON, D.C. 20402 RUSSIA

7115 Date July 1976 112B00 421200 522210 610000 820000 870013 861000

870082 Differential Characteristics of the Energy Albedo of

Gamma-Quanta for Organic Mediums. Viktorov, A.A.; Mashkovich, V.P. ERDA-TR-125 , PP. 152-156 A V A I L A B I L I T Y - N T I S RUSSIA

8389 Date 1978 112730 329000 522110 522210 870004 870006 853100

861000 870050 870082 Surface .^Spectral-Angular Distribution or 137-Cs



8992 Date February 1, 1979 112760 422200 522210 841000 853100 861000 870013'

870082 Measurement of Number Albedo of Backscattered Photons. Biswas, M.; Sinha, A.K.; Roy, S.C. NUCL. INSTRUM. METHODS, 159(1), 157-162 INDIA

234'

8995 Date April 1, 1979 220000 521210 522210 Statistical Errors of Dose Estimation in Personnel Neutron

Monitoring with Albedo Dosimeters. Burgkhardt, B.; Heinselmann, M.; Piesch, E.; Viragh, E. NUCL. INSTRUM. METHODS, 160(3), 533-540 GERMAN

In ter face Effects - Laminar Layers -Gamma-Ray - Experiment


6517 Date April 16, 1975 111220 421130 430000 521230 522230 853100 861000 Time-Dependent Measurements of Fast-Neutron and


Young, J.C.; Harris, L.,Jr.; Bryan, D.E.; Lurie, N.A.; Stein-man, D.K.; Friesenhahn, S.J.; Gober, W.E.; Schanzler, L.

IRT-8025-723 A V A I L A B I L I T Y - I N S T R U M E N T A T I O N

RESEARCH TECHNOLOGY, 7650 CONVOY COURT, P.O. BOX 80817, SAN DIEGO, CALIFOR-NIA 92138

IRT

7111 Date July 1976 111110 421130 421200 521230 522230 710000 719A00


the Novo-Voronezhskaya AES's Second Unit. Glushchenko, A.I.; Orlov, Yu.V.; Satarin, V.Ye. ERDA-TR-125 , PP. 119-126 A V A I L A B I L I T Y - N T I S RUSSIA

8881 Date 1979 111110 112400 112500 421200 522230 795065 795223

861000 870098 Measurement and Calculation of the Gamma-Fields

Induced in Iron by 252-Cf Fission Neutrons. Jiang, S.H. DOE-TR-72 ; KFK-2444 ( I N GERMAN) A V A I L A B I L I T Y - U S D O E TECHNICAL INFORMA-

T ION CENTER, OAK RIDGE, TENN. GERMAN

Heating - Neutron


6247 Date December 1977 111210 32A000 210000 521130 522130 531000 532000


Torus Rcactor'(EBTR) Reference Design. Santoro, R.T.; Barnes, J.M. ORNL/TM-6085 A V A I L A B I L I T Y - N T I S $4.50 O A R N L



Arcipiani, B.; Palmiotti, G.; Salvatores, M. NUCL. SCI. ENG., 65(3), 540-544 ITALY


531000 Effects of Isotopic Abundance on Kerma in Naturally

Occurring Targets: Chlorine. (Tech. Note) Spergel, M.S.; Lazareth, O.W. NUCL. SCL ENG., 65(3), 558-560 BROOKH

6592 Date 1977 111210 531000 532000 717000 870013 Aluminum Blanket/Shield Design for a High Field Ignition

Test Reactor. Fillo, J.A.; Powell, J.R.; Benenati, R.; Makowitz, H. BNL-23411; CONF-771029-132 AVAILABIL ITY-DEP. , NTIS BROOKH


in Fast Reactor Environments. Gold, R. HEDL-SA-1238; CONF-77 I036-7 AVAILABIL ITY-DEP. , NTIS WEE

235'

7028 Date September 1976 010000 111210 210000 32A000 329000 531000 532000


Reactors. Dudziak, D.J. CONF-760935-P3, PP. 819-832; L A - U R - 7 6 - 2 0 8 6 A V A I L A B I L I T Y - NTIS LOASL

7030 Date September 1976 010000 111210 329000 531000 532000 717000 810000 Multidimensional Neutronics Analysis of Major Penetra-

tions in Tokamaks. Abdou, M.A.; Milton, L.J.; Jung, J.C.; Gelbard, E.M. CONF-760935-P3, PP. 845-860 A V A I L A B I L I T Y - N T I S ARGONN

Santoro, R.T.; Baker, V.C.; Barnes, J.M. O R N L / T M - 5 4 6 6 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8130 Date October 1977 111110 111210 111220 121100 121200 531000 532000


nuclear Radiation. Part I I . Transient Energy Deposition, Temperatures, and Displacement Rate.

Hunter, T.O.; Kulcinski, G.L. UWFDM-217 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,


U - W I

7042 Date September 1976 010000 111210 112760 223000 210000 521130 522130-,



8214 Date October 1978 111210 32A000 329000 531000 532000 551110 552120

717000 810000 Two- and Three-Dimensional Neutronics Calculations

for the TFTR Neutral Beam Injectors. Santoro, R.T.; Lillie, R.A.; Alsmiller, R.G.,Jr.; Barnes, J.M. ORNL /TM-6354 ; CONF-780622-29 A V A I L A B I L I T Y - N T I S S5.25 O A R N L

7090 Date May 1977 111210 311000 329000 531000 532000 793000 717000

795203 810000 Monte Carlo Analysis of the Effects of a Blanket-Shield

Penetration on the erformance of a Tokamak Fusion Reactor.

Santoro, R.T.; Tang, J.S.; Alsmiller, R.G.,Jr.; Barnes, J.M. O R N L / T M - 5 8 7 4 A V A I L A B I L I T Y - N T I S $4.00 O A R N L

8401 Date July 1978 121100 121200 122110 122210 220000 531000 532000



Abdou, M.A.; Gohar, Y.; Wright, R.Q. A N L / F P P - 7 7 - 5 A V A I L A B I L I T Y - N T I S $6.00 ARGONN

7105 Date July 1976 111110 531000 532000 810000 Calculating the Temperature Field in Biological Shielding

by the Method of Electrothermal Analogy. Demeshev, R.S.; Rekshnya, N.F. E R D A - T R - 1 2 5 , PP. 73-78 A V A I L A B I L I T Y - N T I S RUSSIA

7130 Date March 1977 111210 32A000 521130 522130 531000 532000 717000


Experimentation Power Reactor.

8403 Date March 1978 122110 122210 220000 531000 532000 793000 794000



Gohar, Y.; Abdou, M.A. 4 . A N L / F P P / T M - 1 0 6 A V A I L A B I L I T Y - N T I S $9.25 ARGONN

8459 Date October 1978 111210 112760 112930 220000 223000 521130 531000

532000 795303 795254 717000 810000 32A000

236'

Safety Aspects of Activation Products in a Compact Toka-mak Fusion Power Plant.

Willenberg, H.J.; Bickford, W.E. PNL-2823 A V A I L A B I L I T Y - N T I S P A N L


Reactor. Iida, H.; Ide, T.; Seki, Y. CONF-771029,VOL.II , PP.1658-1662 A V A I L A B I L I T Y - I E E E SERVICE CENTER, SINGLE


JAPAN

8612 Date 1977 111110 423240 531000 532000 810000 Dosimetry Methods for Structural Materials: Nuclear Heal-

ing. Boyd, A.W. EUR-5667E/F,PT.I , PP.591-598;



C A N A D A

8613 Date 1977 111110 423135 423250 531000 532000 Application of Thermoluminescence Dosimeters for Nuclear

Heating Measurements of Gamma Rays and Neutrons. Tanaka, S.; Takeuchi, K.; Furuta, Y. EUR-5667E/F,PT.I , PP.599-610;



JAPAN

8615 Dale 1977 111110 423135 423250 421140 531000 532000 Reactor Dosimetry Using T L D and Rh-Activation Tech-

niques. Gomaa, M.A.; Sayed, A.M.; Eid, A.M.; El-Kolaly, A.M. EUR-5667E/F,PT.I , PP.623-632;



EGYPT

8955 Date May 1978 111210 123000 210000 531000 532000 793000 794000


M A C K - I V . Abdou, M.A.; Gohar, Y. CONF-780508,VOL.1, PP.402-410 A V A I L A B I L I T Y - D E P , NTIS A R G O N N


Below 20 MeV. Singh, M.S. UCRL-52,850 A V A I L A B I L I T Y - N T I S L A L L

Heat ing - G a m m a - R a y (includes fission products)





6343 Date Sept.-Oct. 1977 010000 112120 532000 A Review of Short-Term Fission-Product-Decay Power. Bjerke, M.A.; Holm, J.S.; Shay, M.R.; Spinrad, B.I. NUCL. SAFETY, 18(5), 596-616 O A R N L

6440 Date Dec. 1977 329000 32A000 532000 719A00 Evaluation of Uncertainties in the Gamma-Ray Heating

Analysis of a PWR. West, J .T , I I I CONF-770401, PP.652-659 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

D R , PRINCETON, NJ 08540 O A R N L

237'

6451 Date Dec. 1977 532000 719A00 A Three-Dimensional Synthesis Approach to Reactor

Internal Gamma-Ray Heating. <1 West, J.T.,111; Whitmarsh, C.L. CONF-770401, PP.739-745 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


Fission-Product Energy Release for Times Following Ther-mal-Neutron Fission of 239-Pu Between 2 and 14000 Seconds.



6469 Date Dec. 1977 112120 423250 532000 719A00 Spatial Distribution of Fission Product Energy. Johnson, W.R.; Bass, R.B.; Littig, G.A.; Robinson, F.L.;

Bracke, T.P. CONF-770401, PP.889-896 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 U - V A

\Y


Test Reactor. Fillo, J.A.; Powell, J.R.; Benenati, R.; Makowitz, H. BNL-23411; CONF-771029-132 A V A I L A B I L I T Y - D E P . , NTIS BROOKH

6608 Date February 1978 112120 532000 795137 795217 The Calculation of the Decay Heat of Fission Products from

Exact Relations. Final Report (Research Project 230). Volume 2.

(VGrossman, L.M.; Stein, M. EPRI -NP-616 , VOL.2 A V A I L A B I L I T Y - U N I V E R S I T Y OF CALIFORNIA,

BERKELEY, CAL IFORNIA EPRI


in Fast Reactor Environments. Gold, R. HEDL-SA-1238 ; CONF-771036-7 A V A I L A B I L I T Y - D E P . , NTIS WEE

6696 Date April 1978 111110 112120 221000 532000 422200 430000 794000

870094

6747 Date February 1978. 112120 532000 870092 A Calorimetric Measurement of Decay Heat from 2 3 5 - U

Fission Products from 10 to 10**5 Seconds. Schrock, V.E.; Grossman, L.M.; Prussin, S.G.; Sockalingam,

K.C.; Nuh, F.; 'Fan, C - K . ; Cho, N.Z.; Oh, S.J. EPRI -NP-616 , VOL. l A V A I L A B I L I T Y - U N I V E R S I T Y OF CAL IFORNIA ,

BERKELEY, CALIF. 94720 EPRI

\ 6858 Date June 1978

112120 112730 532000 719A00 870092 Fission Product Source Terms for the LWR

Loss-of-Coolant Accident: Summary Report. Lorenz, R.A.; Collins, J.L.; Malinauskas, A.P. NUREG/CR-0091; O R N L / N U R E G / T M - 2 0 6 A V A I L A B I L I T Y - N T I S O A R N L

6890 Date November 1977 010000 112120 532000 610000 713000 The Distribution of Fission Product Decay Heat. Turland, B.D.; Peckover, R.S. C L M - P - 5 1 0 A V A I L A B I L I T Y - U K A E A RESEARCH GROUP,


ENGLAN

6903 Date December 1976 112120 329000 532000 719A00 795187 Analysis of Post LOCA Gamma Ray Effects in,Representa-

tive Light Water Reactors. Volume 1. Final Report. Steinberg, H.; Lichtenstein, H.; Cohen, M.O. EPRI -NP-425( VOL. 1) A V A I L A B I L I T Y - N T I S M A A G

6904 Date Apri l 1978 112120 532000 719A00 Spatial Distribution of Fission Product Gamma-Ray


238'

Bass, R.B.; Johnson, W.R. EPRI -NP-672 , VOLUME I A V A I L A B I L I T Y - U N I V E R S I T Y OF V IRGINIA ,

SCHOOL OF ENGINEERING A N D APPLIED SCI-ENCE, CHARLOTTESVILLE, VA. 22901

U - V A

6910 Date May 1978 112120 532000 713000 Decay Heat for the Fast Test Reactor (FTR). Schmittroth, F. H E D L - T M E - 7 7 -13 A V A I L A B I L I T Y - N T I S $5.25 HANFOR s ,

7028 Date September 1976 010000 111210 210000 32A000 329000 531000 532000


Reactors. Dudziak, D.J. CONF-760935-P3, PP. 819-832; L A - U R - 7 6 - 2 0 8 6 A V A I L A B I L I T Y - N T I S LOASL °


tions in Tokamaks. Abdou, M.A.; Milton, L.J.; Jung, J.C.; Gelbard, E.M. CONF-760935-P3, PP. 845-860 A V A I L A B I L I T Y - N T I S ARGONN

7042 Date September 1976 010000 111210 112760 223000 210000 521130 522130



7090 Date May 1977 111210 311000 329000 531000 532000 793000 717000


Penetration on the Performance of a Tokamak Fusion Reactor.

Santoro, R.T.; Tang, J.S.; Alsmiller, R.G.,Jr.; Barnes, J.M. O R N L / T M - 5 8 7 4 A V A I L A B I L I T Y - N T I S $4.00 o

O A R N L

7105 Date July 1976 111110 531000 532000 810000 Calculating the Temperature Field in Biological Shielding

by/the Method of Electrothermal Analogy. Demeshev, R.S.; Rekshnya, N.F. ERDA-TR-125 , PP. 73-78 A V A I L A B I L I T Y - N T I S RUSSIA


Materials of Shielding Placed in Light Mediums. Avayev, V.N.; Yefimov, Ye.P. ERDA-TR-125 , PP. 169-175 A V A I L A B I L I T Y - N T I S RUSSIA

7130 Date March 1977 111210 32A000 521130 522130 531000 532000 717000


Experimentation Power Reactor. Santoro, R.T.; Baker, V.C.; Barnes, J.M. O R N L / T M -5466 A V A I L A B I L I T Y - N T I S $4.50 O A R N L


E N D F / B - I V and V. England, T.R.; Schenter, R.E.; Schmittroth, F. NUREG/CR-0305; L A - 7 4 2 2 - M S A V A I L A B I L I T Y - L O S ALAMOS SCIENTIFIC LAB.,


LOASL K'

I) 8130 Date October 1977

111110 111210 111220 121100 121200 531000 532000 717000 810000

Description of the Response of Materials to Pulsed Thermo-nuclear Radiation. Part II. Transient Energy Deposition, Temperatures, and Displacement Rate.

Hunter, T.O.; Kulcinski, G.L. UWFDM-217 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,


U - W I

239'

8135 Date August 1978 111210 521130 522130 532000 717000 795323 Nucleonic Design for a Compact Tokamak Fusion Reactor

Blanket and Shield. Cheng, E.T.; Maynard, C.W.; Vogelsang, W.F.; Klein, A.C. UWFDM-256 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,


U - W I

8403. Date March 1978 122110 122210 ''•220000 531000 532000 793000 794000


tions Generated with the M A C K - I V Computer Program from ENDF/B- IV .

Gohar, Y.; Abdou, M.A., ANL /FPP/TM-106 A V A I L A B I L I T Y - N T I S S9.25 ARGONN

8206 Date September 1978 112120 532000 795309 870090 870092 870094 The Application of a Library of Processed E N D F / B - I V

Fission-Product Aggregate Decay Data in the Calcula-tion of Decay-Energy Spectra.

LaBauve, R.J.; England, T.R.; George, D.C.; Stamatelatos, M.G. "

L A - 7 4 8 3 - M S A V A I L A B I L I T Y - N T I S LOASL

1 8214 Date October 1978 111210 32A000 329000 531000 532000 551110 552120

717000 810000 Two- and Three-Dimensional Neutronics Calculations

for the TFTR Neutral Beam Injectors. Santoro, R.T.; Lillie, R.A.; Alsmiller, R.G.,Jr.; Barnes, J.M. ORNl) /TM-6354; CONF-780622-29 A V A I L A B I L I T Y - N T I S $5.25 OARNL ^


Design and Operation. Devillers, C. IAEA-213, PP.61-89 A V A I L A B I L I T Y - I A E A , V IENNA (MF ONLY) FRANCE

8401 Date July 1978 121100 121200 122110 122210 220000 531000 532000


culate Nuclear Response Functions «from Data in ENDF/B Format.

Abdou, M.A.; Gohar, Y.; Wright, R.Q. ANL /FPP-77 -5 A V A I L A B I L I T Y - N T I S $6.00 ARGONN


Decay Power. Schenter, R.E.; England, T.R. IAEA-213, VOL.11, PP.677-741 A V A I L A B I L I T Y - I A E A (MF ONLY) HANFOR

8459 Date October 1978 111210 112760 112930 220000 223000 521130 531000


mak Fusion Power Plant. Willenberg, H.J.; Bickford, W.E., PNL-2823 AVAILABIL ITY - NTIS PANL

8510 Date September 1978 112120 423240 532000 870092 870094 Calometric Fission Product Decay Heat Measurements for

239-Pu, 233-U, and 235-U. Yarnell, J.L.; Bendt, P.J. NUREG/CR-0349; LA-7452 A V A I L A B I L I T Y - N T I S LOASL

8511 JDate July 1978 111110 112120 122310 532000 870092 887000 The Effects of the Depletion and Buildup of Fissile Nuclides

and of 238 - U Fast Fissions on Fission Product Decay Power.

Trapp, T.J.,Jr. NUREG/CR-0404; OSU-NE-7806; THESIS A V A I L A B I L I T Y - N T I S U - O R

8516 Date February 1.979 9

112120 122110 123000 532000 795217 Updated Decay and Photon Libraries for the ORIGEN

Code.

240'

Croff, A.G.; Haese, R.L.; Gove, N.B. O R N L / T M - 6 0 5 5 A V A I L A B I L I T Y - N T I S S6.50 O A R N L


Reactor. Iida, H.; Ide, T.; Seki, Y . CONF-771029,VOL.11, PP.1658-1662 A V A I L A B I L I T Y - I E E E SERVICE CENTER, S INGLE

P U B L I C A T I O N SALES DEPT., 445 HOES LANE, P I S C A T A W A Y , N.J. 08853

J A P A N

861 2 Date 1977 111110 423240 531000 532000 810000 Dosimetry Methods for Structural Materials: Nuclear Heat-

ing. Boyd, A .W. EUR-5667E/F ,PT. I , PP.591-598;

CONF-750935,PT.I , PP.591-598 A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L PUBLICA-

T I O N S OF T H E EUROPEAN C O M M U N I T I E S , BOITE POSTAL 1003 - L U X E M B O U R G

C A N A D A

o

861 3 Date 1977 111110 423135 423250 531000 532000 Application of Thermoluminescence Dosimeters for Nuclear

Heating Measurements of Gamma Rays and Neutrons. Tanaka, S.; Takeuchi, K.; Furuta, Y . EUR-5667E/F,PT. I , PP.599-610;

CONF-750935.PT.I , PP.599-610 A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L PUBLICA-


J A P A N

8615 Date 1977 111110 423135 423250 421140 531000 532000 Reactor Dosimetry Using T L D and Rh-Act ivat ion Tech-

niques. Gomaa, M.A. ; Sayed, A.M.; Eid, A.M.; E l -Ko la ly , A.M. EUR-5667E/F ,PT. I , PP.623-632;



EGYPT

8616 Date 1977 111110 423250 532000 713000 T L D Gamma-Ray Energy Deposition Measurements in

the Zero Energy Fast Reactor Zebra. Knipe, A.D. EUR-5667E/F,PT. I , PP.633-647;



E N G L A N

'-.8618 Date 1977 l l l l 10 210000 422110 423250 532000 713000 810000 Dosimetry Work in Connection with Irradiations in the High


de; Fabry, A.; Leenders, L.; Maene, N.; Menil, R. EUR-5667 E/F,PT.I , PP.700-737;

CONF-750935,P,T.I, PP.700-737 A V A I L A B I L I T Y i Q F F I C E FOR O F F I C I A L PUBLICA-


F R A N C E


istic Reactor Operating Histories. Trapp, T.J.; Spinrad, B.l. O R N L / R S I C - 4 2 , PP.105- 118 A V A I L A B I L I T Y - N T I S P A N L

8955 Date May 1978 111210 123000 210000 531000 532000 793000 794000


M A C K - I V . Abdou, M.A. ; Gohar, Y. CONF-780508,VOL. I , PP.402-410 A V A I L A B I L I T Y - D E P . , NT IS A R G O N N

9024 Date May 1979 112120 532000 870092 Nuclear Data Library of Fission Products for Decay Power

Calculation. Tasaka, K. N U R E G / C R - 0 7 0 5 ; TREE-1325 A V A I L A B I L I T Y - E G A N D G IDAHO, I N C , I D A H O EDGERT

V'

241



9845 Date March 1980 112120 532000 719A00 793000 T M I - 2 Decay Power: LASL Fission-Product and Acti-

nide Decay Power Calculations for the President's Commission on the Accident at Three Mile Island.

England, T.R.; Wilson, W.B. LA-8041 - M S , REVISED A V A I L A B I L I T Y - N T I S LOASL

10011 Date July 1980 112120 112760 532000 795217 810000 887000 A User's Manual for the ORIGEN2 Computer Code. Crofl", A.G. O R N L / T M - 7 1 7 5 A V A I L A B I L I T Y - N T I S , PC A09 /MF A01 O A R N L

10080 Date August 1980 112760 230000 532000 851000 Expected Environments in High-Level Nuclear Waste and

Spent Fuel Repositories in Salt. Claiborne, H.C.; Rickertsen, L.D.; Graham, R.F. O R N L / T M - 7 2 0 1 A V A I L A B I L I T Y - N T I S , PC A10/MF A01 O A R N L

Neutron Thermalizat ion and Low-Energy Spectra


6580 Date March 1978 325000 540000 870017 Expansion About a Local Maxwellian for Evaluating the

Spatially Dependent Neutron Spectrum. (Tech. Note) Moliriari, V.G.; Simonini, R. NUCL. SCI. ENG., 65(3), 560-565 ITALY

6826 Date 1978 010000 540000 Standards for Thermal Neutrons at the PTB.

Wagner, S.R. IAEA-208, VOL.11, PP.3-14 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE GERMAN

6833 Date 1978 111110 421160 410000 540000 Thermal Neutron Standard Fields with the KUR Heavy *

Water Facility. ^ Kanda, K.; Kobayashi, K.; Shibata^ T. IAEA-208, VOL.11, PP.107-116 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE JAPAN

a 6854 Date February 1977

111110 323000 540000 719A00 Neutron Spectrum Calculating Module of the Program

BETTY. Gado, J. K F K I - 7 7 - 1 4 AVAILABIL ITY-DEP. , NTIS (U.S. SALES ONLY) GERMAN

7073 Date January 1977 111110 540000 870001 870006 820000 Neutron Thermalization in Hydrogenous Moderators. Kothari, L.S. NBS SPEC. PUB. 461, PP. 149-162 AVAILABIL ITY-SUPT. OF DOCUMENTS, GPO,


8149 Date October 1978 5400$) 820000 Thermal-Neutron Steady-State Spectra in Pure and Poi-

soned Light Water Assemblies. (Tech. Note^ Swaminathan, K.; Tewari, S.P.; Bansal, R.M. NUCL. SCI. ENG., 68(1), 137-140 INDIA

8619 Date 1977 111110 421110 540000 Flux Depression and the Absolute Measurements of the

Thermal Neutron Flux Density. Bensch, F. EUR-5667E/F,PT.I, PP.738-746;



242'

8688 Date March 1979 325000 540000 820000 882000 Neutron Diffusion in Water Containing 1/v and N o n - l / v

Absorbers. Bansal, R.M.; Tewari, S.P.; Kothari, L.S. NUCL . SCI. ENG., 69(3), PP.367-374 I N D I A

9732 Date Apri l 1980 310000 540000 Application of the Multigroup Collision Probability Method'

to Selengut's Theory of Overlapping Neutron Spectra. Kamelander, G.; Putz, F. NUCL . SCL ENG., 74(1), 13-22 AUSTRI

Two Dimensions - Neutron - P r imary -Calculation



Theory Neutronics Results for Perturbation Analyses. Vondy, D.R.; Fowler, T.B. O R N L - 5 3 7 6 A V A I L A B I L I T Y - N T I S S6.00 O A R N L

t> 6657 Date November 1977

111110 521130 551110 329000 795203 870090 870092 870093 810000

Monte Carlo Calculations of 'Time-Dependent Neptuni-um-237 and Uranium-235 Fission Rates in a Pulsed Thorium Assembly.

McGregor, B.J. A A E C / E - 4 3 2 A V A I L A B I L I T Y - A U S T R A L I A N A T O M I C ENERGY


AUSTRA

6460 Date Dec. 1977 l , | ' f l 10 551110 795209 713000 Measurements and Calculations of Neutron Fluxes Through

a Simulation of the CRBR Upper Axial Shielding. Maerker, R.E.; Muckenthaler, F.J. CONF-770401, PP.812-818 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE " DR., PRINCETON, NJ 08540 O A R N L

6678 Date September 1977 111210 32A000 551110 717000 795222 Neutron Wall Loading Characteristics of a Doublet Reac-

tor. Woods, T.J. G A - A - 1 4 6 3 2 ; CONF-771029-53 A V A I L A B I L I T Y - D E P . , NT IS GEAC


Atmospheric Radiation Transport Problem. Shulstad, R.A. A F W L - T R - 7 6 - 2 2 1 A V A I L A B I L I T Y - N T I S A IR

6690 Date February 1978 111220 122110 32A000 421000 521130 551110 760000



6609 Date December 1977 111110 210000 311000 32A000 551110 795276 719A00


of an LWR. Final Report (Research Project 827-2). Livesay, R.B.; Wells, M.B. E P R I - N P - 6 1 7 A V A I L A B I L I T Y - R A D I A T I O N RESEARCH ASSOCI-

ATES, INC. RARA

6746 Date September 1977 111110 112110 112400 112500 32AOOO 511110 551110


Damage Studies. Gritzner, M.L.; Simmons, G.L.; Albert, T.E.; Straker, E.A. E P R I - N P - I 5 2 , F I N A L REPORT A V A I L A B I L I T Y - S C I E N C E APPLICATIONS INC.,

LA JOLLA, CAL IF . EPRI

243'



V. 6943 Date June 1978

111110 325000 551110 713000 810000 Test of the Diffusion Theory Difference Equations in Slab

Geometry (Computer Code VANCER). Vondy, D.R.; Fowler, T.B. ORNL-5381 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

6948 Date August 1978 111210 421000 32A000 551110 795276 861000 Design Calculations for a 14-MeV Neutron Collimator. Lillie, R.A.; Alsmiller, R.G.,Jr. O R N L / T M - 6 4 8 7 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

6975 Date August 1978 111110 325000 551110 The Application of the Symmetric SOR and the Symmetric

SIP Methods for the Numerical Solution of Neutron Diffusion Equation.

Wang, H.H. NUCL. SCL ENG., 67(2), 162-171 IBM 0

6979 Date August 1978 111110 325000 551110 713000 Benchmark Calculations for a Sodium-Cooled Breeder

Reactor by Two- and Three-Dimensional Diffusion Methods-II. (Tech. Note)

Buckel, G.; Kufner, K.; Stehle, B. NUCL. SCL ENG., 67(2), 257-259 GERMAN

7065 Date January 1977 111110 330000 551110 870092 870094 Criticality Calculations by Source-Collision Iteration

Technique for Cylindrical Systems. Sundaram, V.K.; Gopinath, D.V. NBS SPEC. PUB. 461, PP. 94-96 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


7102 Date July 1976 111500 321000 511110 551110 820000 861000 0

Spatial and Angular Distributions of Fast Neutrons in Coni-cal Shielding.

Bass, L.P.; Germogenova, T.A.; Dubinin, A.A.; Khmylev, A.N. - -


8010 Date June 1978 111110 328000 551110 Fast Computation of the Neutron Flux Distribution in X - Y

Geometry Using the QPO First Collision Probability Method.

Stepanek, J.; Hager, H. EIR-344 AVAILABIL ITY-EIDGENOISSISCHES INST. FUER

REAKTORFORSCHUNG, WUERENLINGEN, SWITZERLAND

GERMAN

8023 Date June 1978 111110 122110 511110 551110 713000 793000 794000

122310 E N D F / B - I V , L I B - I V , and the CSEWG Benchmarks. Kidman, R.B. L A - 7 3 5 5 - M S A V A I L A B I L I T Y - L O S ALAMOS SCIENTIFIC LAB.,


7029 Date September 1976 111210 32AOOO 551110 552110 721100 717000 810000 Neutronic and Photonic Analysis of U W M A K - I I I Blanket

and Shield in Noncircular Toroidal Geometry. Gohar, Y.; Maynard, C.W.; Cheng, E.T. CONF-760935-P3, PP. 833-844 A V A I L A B I L I T Y - N T I S U - W I

8033 Date August 1978 111110 230000 325000 551110 713000 887000 793000

794000 // Preliminary Neutronic Study of Actinide Transmutation >n

a Fast Reactor. ^ Williams, M.L.; McAdoo, J.W.; Flanagan, G.F. ORNL /TM-6309 A V A I L A B I L I T Y - N T I S $4.50 OARNL

244'

„ 8034 ^ Date August 1978 111110 220000 32A000 551110 552210 820000 861000


with Experimental Data. Santoro, R.T.; Alsmiller, R.G.,Jr.; Barnes, J.M. O R N L / T M - 6 4 0 1 / R 1 A V A I L A B I L I T Y - N T I S 54.00 O A R N L

8518 Date January 1979 111210 122310 32AOOO 521130 551110 717000 793000



Seki, Y.; Santoro, R.T.; Oblow, E.M.; Lucius, J.L. O R N L / T M - 6 6 6 7 A V A I L A B I L I T Y - N T I S S4.00 O A R N L

8214 Date October 1978 111210 32A000 329000 531000 532000 551110 552120

717000 810000 T w o - and Three-Dimensional Neutronics Calculations

for the TFTR Neutral Beam Injectors. Santoro, R.T.; Lillie, R.A.; Alsmiller, R.G,Jr.; Barnes, J.M. ORNL /TM-6354 ; CONF-780622-29 A V A I L A B I L I T Y - N T I S S5.25 O A R N L

8577 Date1 November 1978 111110 32A000 122310 312000 551110 551200 793000

794000 870011 861000 795276 795254 795203 Investigation of Steel-Sodium-Iron Shields. Oblow, E.M.; Maerker, R.E. CONF-781117-6 A V A I L A B I L I T Y - D E P . , NTIS O A R N L

8435 Date January 1979 111110 112930 122110 329000 32A000 325000 551110

713000 793000 794000 795222 795320 Neutronic Analysis of LMFBRs During Severe Core Dis-

ruptive Accidents. Tomlinson, E.T. ORNL /CSD-35 A V A I L A B I L I T Y - N T I S $5.25 O A R N L

8496 Date January 1978 111210 329000 32A000 551110 552110 793000 717000


Engineering, Trit ium and Neutronics. Project Staff - Argonne National Lab. . G A - A14614,VOL. V; ANL/FPP/77-6,V,OL.V A V A I L A B I L I T Y - N T I S $8.00 GEAC



Streaming Experiment with a Two-Dimensional3

Model. Seki, Y.; Santoro, R.T.; Oblow, E.M.; Barnes, J.M.; Lucius,

J.L. O R N L / T M - 6 5 8 8 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8589 1 Date 1977 111110 210000 421140 32AOOO 551110 810000 Neutron Energy Spectrum Determination for Irradiation

Damage Study of Reactor Structural Materials. Takeuchi, K.; Miura, T.; Yamaji, A. EUR-5667E/F,PT.I , PP.63-73; CONF-750935,PT.I,



JAPAN



8663 Date February 1979 111210 122310 32A000 312000 521130 551110 717000


Fusion Reactor Design. Wu, T.; Maynard, C.W. ORNL/RSIC-42 , PP.191-217; UWFDM-290 A V A I L A B I L I T Y - N T I S U - W I

245'

8710 Date 1978 010000 111110 32AOOO 329000 312000 551110 552210

713000 719B00 793000 794000 795254 795320 810000 Methods for U.S. Shielding Calculations: Applications to

FFTF and CRBR Designs. Engle, W.W.,Jr.; Mynatt, F.R.; Disney, R.K. CONF-781117-3 A V A I L A B I L I T Y - D E P . , NTIS O A R N L

8736 Date March 1979 111400 112130 210000 32A000 521130 522130 551110


Point Sources Above an Air -Ground Interface. Lillie, R.A.; Santoro, R.T. O R N L / T M - 6 6 5 5 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8796 Date February 1979 111110 223000 32A000 521130 522130 551110 552210


Cavity Shield System. Celnik, J. ORN L / R S I C - 43,PP.54 - 67;

ANS/SD-79/16,PP.54-67 A V A I L A B I L I T Y - N T I S BURNS

8802 , Date February 1979 111110 32A000.551110 719A00 710000 7211004)10000^ A Low Pressure Drop Reactor Cavity Shield System. Klotz, R.J.; Cavanaugh, G.P.; Kassawara, R.P.;

McLaughlin, D.J.; Pilver, A.B. ORNL/RSIC-43,PP.137-148;

A N S / S D - 79/16,PP. 137-148 A V A I L A B I L I T Y - N T I S COE

886,0 Date September 1978 111210 551110 717100 870092 810000 Neutronic Studies of a 233 -U Fusion Breeder. ,' Hansen, L.F.; Maniscalco, J.A. CONF-7,80921, PP.772-777 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL,

75775 PARIS-CEDEX 16, FRANCE L A L L

8885. Date March 1979 111500 32A000 329000 551110 552210 853100 861000

795203 793000

The SAI /EPRI Albedo Information Library. Simmons, G.L. EPRI -NP-1017 A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, INC.,

1200 PROSPECT ST., LA JOLLA, CAL IFORNIA 92038 M

SCA

8947 Date May 1978 111210 32A000 551110 552110 795276 717000 810000 A BWTR (Boiling Water Tokamak Reactor) Blanket Study. Sze, D.K.;. Maynard, C.W.; Sviatoslavsky, I.N.; Cheng,

E.T.; Wang, C.C.; Wrazel, J. ] CONF-780508,VOL.l , PP.239-248 AVA ILAB IL ITY-DEP. , NTIS U - W I

9006 Date June 1978 111110 325000 551110 719A00 810000 A Nodal Method for Solving Transient Fewgroup NeutronifV

Diffusion Equations. : i* Shober, R.A. A N L - 7 8 - 5 1 A V A I L A B I L I T Y - N T I S $6.00 A R G O N N

9011 Date 1979 11,1110 32DOOO 551110 Mathematical Behavior and Computation of Transmission

Probabilities for Annular Regions. Hwang, R.N.; Toppel, B.J. CONF-790402-21 AVAILABIL ITY-DEP. , NTIS ARGONN O

9095 Date September 1976 I I I I I O 325000 551110 810000 " ^ Exact and Approximate Interior Corner Problem in Neutron

Diffusion by Integral Transform Methods. Bareiss, E.H.; Chang, K.S.J.; Constatinescu, D.A. ^ COC?-2280-28 A V A I L A B I L ' T Y - N T I S U - I L ^ \L

9110 Date August 1979 111110 32A000 329000 551110 552210 719B00 795320

795203 810000 Analysis of the ORNL/TSF GCFR Grid-Plate Shield

Design Confirmation Experiment. Slater, C.O.; Cramer, S.N.; Ingersoll, D.T. ORNL-5551 A V A I L A B I L I T Y - N T I S $8.00 O A R N L

0

246

9284 Date 1978 111500 32A000 220000 551 110 552210 795203 845000 Recent Results in Neutron Depth Dose Calculations. Burger, G.; Morhart, A.; Schraube,, H. EUR -5848,PP. 125- 143; CONF-770597,PP.125-143 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


GERMAN

9532 Date February 1979 111500 1I2B00 220000 32AOOO 551110 552110 552210

793000 795276 845000 Development of a Mid-Head Radiation Dose Response

Function. Trubey, D.K.; Knight, J.R.; Bartine, D.E.; Pace, J.V.,III O R N L / T M - 6 6 3 4 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

9305 Date July 1979 111110 312000 325000 32A000 551110 TP2 - A Computer Program for the Calculation of Reactiv-


Kobayashi, K. KFK-2787 AVA ILAB IL ITY - KERNFORSCHUNGSZENTRUM

KARLSRUHE (GERMANY, F.R.), INST. FUER NEUTRONENPHYSIK U N D REAKTORTECH-N IK

GERMAN *

9563 v- Date July 1979 111400 112800 329000 32AOOO 551110 552110 552210

731100 793000 795262 810000 Radiation Transport Calculations for the M60A1 Medium

Tank and APRD Reactor Scenario. Rainis, A.E.; Kinch, J.W. A R B R L - M R - 0 2 9 3 4 A V A I L A B I L I T Y - D E F E N S E DOCUMENTATION

CENTER, CAMERON STATION, ALEXANDRIA , VA 22314

A R M Y

9314 Date August 1979 111110 325000 551110 713000 793000 794000 810000 Preliminary Neutronic Analysis of a Fast Mixed-Spectrum

Reactor (FMSR). Burns, T.J.; White, J.R. O R N L / T M - 6 8 5 4 A V A I L A B I L I T Y - N T I S OARNL

9380 Date October 1979 111110 32AOOO 551110 795320 The Stability of the Mesh-Cornered Synthetic Method of

Diffusion Acceleration of the D O T - I V Transport Code.

Aull, J. ORNL /TM-7097 A V A I L A B I L I T Y - N T I S O A R N L

» 9529 Date November 1977 111 110 312000 32AOOO 325000 551110 713000 795320 Transport-Diffusion Comparisons for Small Core LMFBR

Disruptive Accidents. Tomlinson, E.T. O R N L / C S D / T M -38 A V A I L A B I L I T Y - N T I S $5.25 O A R N L

9632 - Date March 1980 111110 112400 112500 421140 423250 551120 551110

795209 861000 Neutron and Gamma-Ray Penetrations in Thick Iron. Oka, Y.; An, S.; Kasai, S.; Miyasaka, S.; Koyama, K. NUCL. SCI. ENG.. 73(3), 259-273 JAPAN

9707 Date January 1980 111210 311000 329000 551110 870011 Application of Biasing Techniques to the Contributon Monte

Carlo Method. Dubi, A.; Gerstl, S.A.W. LA-8201 - M S AVA ILAB IL ITY -DEP. , NTIS, PC A03 /MF A0I LOASL

9744 Date 1979 111110 32AOOO 551110 795222 795320 A Timing Comparison of^ Two-Dimensional Dis-

crete-Ordinates Codes for Criticality Calculations. Miller, W.F.,Jr.; Alcouffe, R.E.; Bosler, G.E.; Brinkley,

F.W.,Jr.; O'Dell, R.D. CONF-790402,VOL.II, P P . 4 - 1 - - 4 - 1 8 A V A I L A B I L I T Y - H C - - A N S V IRGINIA SECTION?


LOASL

247'

9745 Date 1979 111110 32A000 551110 795222 795320 A Comparison of Codes for Deep Penetration Transport

Studies. Rhoades, W.A.; Tomlinson, E.T. CONF-790402,VOL.11, PP.4-19- - 4 - 3 3 A V A I L A B I L IT Y - HC - - ANS V IRGINIA SECTION,


OARNL



Kufner, K.; delMarmol, B.; Minsart, G. CONF-790402,VOL.II, P P . 4 - 3 5 - - 4 - 4 7 A V A I L A B I L I T Y - H C - - A N S VIRGINIA SECTION,


GERMAN

9747 Date 1979 111110 32A000 551110 795293 A Three-Dimensional Hexagonal-Z Difference Scheme

for Discrete-Ordinates Codes. Walters, W.F.; O'Dell, R.D. CONF-790402,VOL.11, P P . 4 - 4 9 - r 4 - 6 3 A V A I L A B I L I T Y - H C - - A N S VIRGINIA SECTION,


LOASL "

9748 Date 1979 1111 10 32A000 551110 Convergence of Two-Dimensional Discrete-Ordinates for

Regions with Imbedded Vacuums. Nelson, P. CONF-790402,VOL.11, P P . 4 - 6 5 - - 4 - 7 8 A V A I L A B I L I T Y - H C - - A N S VIRGINIA SECTION,


U - T X

9751 Date 1979 111110 310000 32AOOO 325000 551110 A Nodal Discrete-Ordinates Method for the Numerical

Solution of the Multidimensional Transport Equation. Wagner, M.R. CONF-790402,VOL.11, PP.4- 117- - 4 - 133 A V A I L A B I L I T Y - H C - - A N S V IRGINIA SECTION,


GERMAN

9762 Date 1979 111110 330000 551110 795276 Improvements of the Integral Transport Theory Method. Kavenoky, A.; Lam-Hime, M.; Stankovski, Z. CONF-790402,VOL.II, P P . 7 - 5 5 - - 7 - 6 9 A V A I L A B I L I T Y - H C - - A N S V I R G I N I A SECTION,


FRANCE

9855 Date May 1980 111110 312000 32AOOO 551110 552210 795204 795254

795320 719B00 810000 Analysis of the Initial Shielding Design for the Upflow

Gas-Cooled Fast Reactor (GCFR). Slater, C.O.; Tomlinson, E.T.; Williams, L.R. ORNL/TM-7246 A V A I L A B I L I T Y - N T I S , PC A05 /MF A01 OARNL

10136 Date August 1980 111 110 325000 551110 SEXI - A Fast Diffusion Program Based on Exponential

and Trigonometric Interpolation. Makai, M.; et al. EIR-401 A V A I L A B I L I T Y - E I D G . INSTITUT FUER REAK-

TORSCHUNG WURENLINGEN, SWITZERLAND

GERMAN

Two Dimensions - Neutron - P r imary -Experiment


6462 Date Dec. 1977 020000 111110 421140 551120 795254 795222 861000


Iron at YAYOI. Oka, Y.; An, S.; Kasai, S.; Sakata, S.; Miyasaka, S.; Koya-

ma, K.; Hyodo, T. CONF-770401, PP.833-840 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


248'

6464 Date Dec. 1977 111110 421140 551120 718000 731300 721200 795195 M o c k - U p Experiment of Radiation Streaming Through

Coolant Pipe Penetration. Tsubosaka, A.; Miyakoshi, J.; Furuta, K.; Kawakila, T.;

Natume, H.; Nishizaki, T.; Okumura, Y.; Miyasaka, S.; Asaoka, T.; Taji, Y.; Ise, T.; Koyama, K.; Tsutsui, T.; Takeuchi, M. ; Fuse, T.; Miura, T.; Yamaji, A.


D R , PRINCETON, NJ 08540 JAPAN

6611 Date February 1978 020000 111110 329000 551120 795209 795254 870092

870094 885000 Analysis of Some Uranium Oxide and Mixed-Oxide Lat-

tice Measurements. Sher, R.; Fiarman, S. EPRI -NP-691 A V A I L A B I L I T Y - D E P A R T M E N T OF MECHANI -

CAL ENGINEERING, STANFORD UNIVERSITY, STANFORD, CALIFORNIA 94305

EPRI

CONF-781117-2 AVA ILAB IL ITY -DEP. , NTIS O A R N L

8866 Date September 1978 111110 422110 551120 719B00 810000 Fast Neutron Dose in High-Temperature Gas-Cooled

Reactors - Comparison of Measured and Calculated Fast Fluxes.

Neef, R.D.; Druke, V.; Khamis, H.; Litzow, W. CONF-780921, PP.1022-1027 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL,



Annotated Bibliography: Volume I, Main Listing. Koponen, B.L.; Wilcox, T.P.; Hampel, V.E. UCRL-52769, VOL. I A V A I L A B I L I T Y - N T I S L A L L

t8628 Date 1977 111110 210000 422110 551120 810000 795254 795209

^Dosimetric Relative a des Irradiations d'Acier dans le Reac-teur Melusine.

Devillers, C.; Perdreau, R. EUR-5667E/F,PT.I I , PP.69-80(IN FRENCH);



FRANCE

8635 Date 1977 020000 111110 421140 551120 795209 810000 The Tapiro Fast Source Reactor as a Benchmark to Test

Activation Detector Cross Sections. Martini, M.; Belli, M.; Sirito, M.F. EUR-5667E/F,PT.I I , „ PP.259-276;

CONF-750935JPT.il, PP.259-276 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


I T A L Y

8709 Date 1978 020000 111110 32AOOO 329000 551120 552220 713000

795254 795320 795203 810000 U.S. Integral and Benchmark Experiments. Maienschein, F.C.



9632 Date March 1980 111110 112400 112500 421140 423250 551120 551110

795209 861000 Neutron and Gamma-Ray Penetrations in Thick Iron. Oka, Y.; An, S.; Kasai, S.; Miyasaka, S.; Koyama, K. NUCL. SCI. ENG., 73(3), 259-273 JAPAN

Two Dimensions - Neutron - Secondary


8577 Date November 1978 111110 32A000 122310 312000 551110 551200 793000

794000 870011 861000 795276 795254 795203 Investigation of Steel-Sodium-Iron Shields. Oblow, E.M.; Maerker, R.E. CONF-781117-6

249'

AVAILABILITY-DEP. , N T I S O A R N L

Two Dimensions - Gamma-Ray - P r i m a r y - Calculation



and Shield in Noncircular Toroidal Geometry. Gohar, Y.; Maynard, C.W.; Cheng, E.T. CONF-760935-P3, PP. 833-844 A V A I L A B I L I T Y - N T I S U - W I

),-7104 Date July 1976

112B00 312000 552110 810000 Using Perturbation Theory for Problems Concerning Scat-

tered Gamma-Radiation. Petrov, E.Ye.; Shemetenko, B.P. E R D A - T R - 1 2 5 , PP. 54-72 A V A I L A B I L I T Y - N T I S RUSSIA

8496 Date January 1978 111210 329000 32A000 551110 552110 793000 717000


Engineering, Tri t ium and Neutronics. Project Staff - Argonne National Lab. GA-A14614,VOL.V; ANL/FPP/77-6 .VOL.V A V A I L A B I L I T Y - N T I S £8.00 GEAC

8517 Date February 1979 020000 111210 122310 312000 32A000 551110 552110





8678 Date March 1979 112120 32AOOO 552110 795217 719A00 795320 861000 Calculated, Two-Dimensional Dose Rates from a PWR

Fuel Assembly.

Croff, A.G.; Hermann, O.W.; Alexander, C.W. ORNL/TM-675* -A V A I L A B I L I T Y - NTIS $4.50 OARNL

8736 Date March 1979 111400 112130 210000 32AOOO 521130 522130 551110


Point Sources Above an Ai r -Ground Interface. Lillie, R.A.; Santoro, R.T. O R N L / T M - 6 6 5 5 A V A I L A B I L I T Y - N T I S $4.50 OARNL

8947 Date May 1978 111210 32AOOO 551110^52110 795276 717000 810000 A BWTR (Boiling Water Tokamak Reactor) Blanket Study. Sze, D.K.; Maynard, c j w . ; Sviatoslavsky, I.N.; Cheng,

E.T.; Wang, C.C.; Wrazel, J. CONF-780508,VOL. l//pP.239-248 AVA ILAB IL ITY -DEP. , NTIS U - W I |

9532 Date February 1979 111500 112B00 220000 32A000 551110 552110 552210


Function. Trubey, D.K.; Knight, J.R.; Bartine, D.E.; Pace, J.V.,III ORNL /TM-6634 A V A I L A B I L I T Y - N T I S $4.50 OARNL

9563 Date July 19 79 111400 112800 329000 32AOOO 551110 552110 552210

" 731100 793000 795262 810000 Radiation Transport Calculations for the M60A1 Medium

Tank and APRD Reactor Scenario. Rainis, A.E.; Kinch, J.W. ARBRL-MR-02934 A V A I L A B I L I T Y - D E F E N S E D O C U M E N T A T I O N

CENTER, CAMERON STATION, A L E X A N D R I A , VA 22314

A R M Y

9919 Date July 1979 112120 552110 711100 719AOO 632120 Gamma Doses from Irradiated Assemblies Under Water. Rinard, P.M. L A - 7 9 1 4 - M S A V A I L A B I L I T Y - N T I S $4.50 LOASL

250'

Two Dimensions - Gamma-Ray - P r imary S a n t o r 0 i R . T . ; Alsmillcr, R.G.,Jr.; Barnes, J.M. - Exper iment O R N L / T M - 6 4 0 1 / R 1

CATEGORY NUMBER 552120 $ 4 °°

8214 Date October 1978 111210 32AOOO 329000 531000 532000 551110 552120


for the TFTR Neutral Beam Injectors. Santoro, R.T.; Lillie, R.A.; Alsmiller, R.G.,Jr.; Barnes, J.M. ORNL /TM-6354 ; CONF-780622-29 A V A I L A B I L I T Y - N T I S $5.25 O A R N L

Two Dimensions - Gamma-Ray -Secondary - Calculation




6746 Date September 1977 111110 112110 112400 112500 32A000 5)1110 551110


Damage Studies. Gritzner, M.L.; Simmons, G.L.; Albert, T.E.; Straker, E.A. EPRI -NP-152 , F I N A L REPORT A V A I L A B I L I T Y - S C I E N C E APPLICATIONS INC.,




8710 Date 1978 010000 111110 32A000 329000 312000 551110 552210

713000 719B00 793000 794000 795254 795320 810000 Methods for U.S. Shielding Calculations; Applications to


8796 Date February 1979 111U0 223000 32A000 521130 522130 551110 552210


Cavity Shield System. Celnik, J. ORNL/RSIC-43.PP.54-67;

ANS/SD-79/16.PP.54-67 A V A I L A B I L I T Y - N T I S BURNS

8885 Date March 1979 111500 32A000 329000 551110 552210 853100 861000

795203 793000 The SAI /EPRI Albedo Information Library. Simmons, G.L. EPRl -NP-1017 A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, INC.,

1200 PROSPECT ST., LA JOLLA, CAL IFORNIA 92038

SCA

9110 Date August 1979 111110 32A000 329000 551110 552210 719B00 795320

795203 810000 Analysis of the ORNL/TSF GCFR Grid-Plate Shield

Design Confirmation Experiment. Slater, C.O.; Cramer, S.N.; Ingersoll, D.T. ORNL-5551 A V A I L A B I L I T Y - N T I S $8.00 OARNL

8034 Date August 1978 111110 220000 32A000 551110 552210 820000 861000


with Experimental Data.

9284 Date 1978 111500 32A000 220000 551 110 552210 795203 845000 Recent Results in Neutron Depth Dose Calculations. Burger, G.; Morhart, A.; Schraube, H. EUR-5848,PP.125-143; CONF-77Q597,PP.125-143

251 <3

AVAILABILITY - OFFICE FOR OFFICIAL PUBLICA-TIONS OF THE EUROPEAN ^COMMUNIT IES, BOITE POSTALE 1003 - LUXEMBOURG ISBN 92-825-0256-2

GERMAN

9532 Date February 1979 111500 112B00 220000 32A000 551110 552110 552210


Function. l> Trubey, D.K.; Knight, J.R.; Bartine, D.E.; Pace, J.V..III


8736 Date March 1979 111400 112130 210000 32A000 521130 522130 551110


Point Sources Above an Ai r -Ground Interface. Lillie, R.A.; Santoro, R.T. ORNL /TM-6655 A V A I L A B I L I T Y - N T I S $4.50 OARNL

Two Dimensions - X-Ray - P r imary -Exper iment


9855 Date May 1980 111110 312000 32A000 551110 552210 795204 795254


Gas-Cooled Fast Reactor (GCFR). Slater, C.O.; Tomlinson, E.T.; Williams, L.R. O R N L / T M - 7 2 4 6 A V A I L A B I L I T Y - N T I S , PC A05/MF A01 O A R N L

Two Dimensions - Gamma-Ray -Secondary - Experiment


6698 Date April 1978 113100 220000 329000 423210 423250 553120 845000 An Evaluation of the Distribution of Absorbed Dose in Child

Phantoms Exposed to Diagnostic Medical X-Rays. Chen, W.; Poston, J.W.; Warner, G.G. ORNL/TM-5933 A V A I L A B I L I T Y - N T I S OARNL

Two Dimensions - P lasma - P r imary -Calculation


8709 Date 1978 020000 111110 32AOOO 329000 551120 552220 713000

795254 795320 795203 810000 U.S. Integral and Benchmark Experiments. Maienschein, F.C. CONF-781117-2 A V A I L A B I L I T Y - D E P . , NTIS O A R N L

9547 f,. . . Date February 1980 329000 554110 Monte Carlo Treatment for Neutral Particle Transport

Problems in a Toroidal Plasma. Inoue, S.; Taji, Y.; Nakahara, Y.; Suzuki, T. NUCL. SCI. ENG., 73(2), 119-124 JAPAN

D

252'

Formulas, Graphs, Tables, and Nomograms - n and 7 ray



Dancoff Factor of Spheres, Cylinders, and Slabs. Knight, J.R. O R N L / N U R E G / C S D / T M - 2 A V A I L A B I L I T Y - N T I S $6.00 O A R N L

6791 Date 1977 112710 610000 Quantum Radiations of Radioactive Nuclides. Gusev, N.G.; Dmitrev, P.P. BOOK A V A I L A B I L I T Y - A T O M I Z D A T , MOSCOW RUSSIA

6883 Date 1976 112710 610000 NEUTRON ACTIVATION TABLES. Erdtmann, G. BOOK „ A V A I L A B I L I T Y - N E W YORK, VERLAG CHEMIE GERMAN

6887 'V Date March 1977 020000 220000 610000 Neutron and Gamma-Ray Flux-to-Dose-Rate Fac-

tors. Battat, M.E. ANSI /ANS-6.1 .1-1977 A V A I L A B I L I T Y - A M E R I C A N NUCLEAR SOCIETY,

555 NORTH KENSINGTON, AVE., LAGRANGE PARK, I LL INOIS 60525 $12.00

A M N S

6940 ? Date May 1978 112930 610000 Definition of Loss-of-Coolant Accident Radiation

Source: Summary and Conclusions.

Bonzon, L.L.; Lurie, N.A.; Houston, D.H.; Naber, J.A. NUREG/CR-0183; SAND78-0091 A V A I L A B I L I T Y - N T I S $9.00 SANDIA

6996 Date. 1978 112400 610000 Atlas of Gamma - Ray Spectra from the Inelastic Scattering

of Reactor Fast Neutrons. Demidov, A.M. BOOK ( I N RUSSIAN A N D ENGLISH) A V A I L A B I L I T Y - M O S C O W , A T O M I Z D A T RUSSIA

7068 Date January 1977 010000 112B00 310000 522110 522210 610000 810000 Backscattering of Gamma Rays. Hyodo, T. NBS SPEC. PUB. 461, PP. 110-118 AVA ILAB IL ITY -SUPT . OF DOCUMENTS, GPO,


7115 Date July 1976 112B00 421200 522210 610000 820000 870013 861000

870082 Differential Characteristics of tthe Energy Albedo of

Gamma-Quanta for Organic Mediums. Viktorov, A.A.; Mashkovich, V.P. ERDA-TR-125 , PP. 152-156 A V A I L A B I L I T Y - N T I S RUSSIA

7116 Date July 1976 1U110 421130 521230 610000 810000 Investigation of the Field of Neutrons Reflected from

Screens with Various Thicknesses. Yegorov, Yu.A.; Zharkov, V.P.; Orlov, Yu.V. ERDA-TR-125 , PP. 157-168 A V A I L A B I L I T Y - N T I S RUSSIA u

II 0 253

8030 Date August 1978 112120 610000 Delayed Beta- and Gamma-Ray Production Due to Ther-

mal-Neutron Fission of 235 -U , Spectral Distributions for Times after Fission Between 2 and 14000 Sec: Tabular and Graphical Data.

Dickens, J.K.; Love, T.A.; McConnell, J:W.; Emery, J.F.; " Northcutt, K.J.; Peelle, R.W.; Weaver, H. N U R E G / C R - 0 1 6 2 ; O R N L / N U R E G - 3 9 A V A I L A B I L I T Y - N T I S O A R N L b).

8031 Date August 1978 112120 610000 870094 Fission-Product Energy Release for Times Following Ther-

mal-Neutron Fission of 241 - P u Between 2 and 14000 Seconds.

Dickens, J.K.; Emery, J.F.; Love, T.A.; McConnell, J.W.; ; Northcutt, K.J.; Peelle, R.W.; Weaver, H.


8044 Date January 1978 'ill 2710 610000 Internal Conversion Coefficients for E5 and M5 Nuclear

Transitions 30 Z 104. Band, I.M.; Trzhaskovskaya, M.B.; Listengarten, M.A. A T O M I C D A T A A N D N U C L . D A T A TABLES, 21(1),

1 -47 RUSSIA


Deposition from Scattered Gamma Rays. Mal ik, J.S.; Cashwell, E.D.; Schrandt, R.G. L A - 7 3 8 6 - M S A V A I L A B I L I T Y - L O S A L A M O S SCIENTIF IC LAB.,

P.O. BOX 1663, LOS A L A M O S , N E W M E X I C O 87545

LOASL

8239. Date February - March 1978 010000 112710 610000 Internal Conversion Coefficients for all Atomic Shells ICC

Values for Z = 30-67. Rosel, F.; Fries, H.M.; Alder, K.; Pauli, H.C. A T O M I C D A T A C A N D NUCL. D A T A TABLES,

21(2-3) , 91-289 S W I T Z E

8506 Date 1978 112710 420000 610000 A Handbook of Radioactivity Measurements Procedures. NCRP • N C R P - 5 8 A V A I L A B I L I T Y - N C R P PUBLICATIONS, P.O. BOX

30175, W A S H I N G T O N , D.C. 20014 NCRP

8792 Date February 1979 • 010000 l l l 1 1 0 223000 32AOOO 521110 522110 610000


LWRs. Rahn, F.; Ti l l , H. ORNL/RSIC-43 ,PP.1 -21; ANS/SD-79 /16 ,PP.1 -21 A V A I L A B I L I T Y - NTIS EPRI

8797 Date February 1979 " 111110 329000 721100 722100 793000 7I9AOO 610000


Harmonics Expansion of Albedo Data. Albert, T.E.; Simmons, G.L. ORNL/RSIC-43.PP.68-75 ;

ANS/SD - 79/16,PP.68 - 75 A V A I L A B I L I T Y - N T I S SCA

'' v

8835 Date 1978 112930 220000 222000 610000 Manual of Dose Evaluation from Atmospheric Releases. Shirvaikar, V.V.; Abrol, V. B.A.R.C. / I -503 A V A I L A B I L I T Y - B H A B H A A T O M I C RESEARCH

CENTRE, BOMBAY, I N D I A I N D I A

>•. 9100 Date February 1979 112710 610000 Gamma-Ray Catalog. Reis, U.; et al. 0

G S I - 7 9 - 2 A V A I L A B I L I T Y - G E S E L L S C H A F T FUER SCHWER-'1

IONENFORSCHUNG, D A R M S T A D T ( G E R M A N Y , F.R.)

G E R M A N

9257 •„ Date 1978 « 112710 610000 T A B L E OF ISOTOPES. Seventh Edition. Lederer, C.M.; Shirley, V.S.

254'

BOOK A V A I L A B I L I T Y - J O H N WILEY A N D SONS, INC. L A B L

9376 Date October 1979 112760 220000 610000 711100 845000 4 ,, Estimates of Internal Dose Equivalent to 22 Target Organs



NUREG/CR-0150,VOL.2; O R N L / N U R E G / T M - 1 9 0 / V 2

A V A I L A B I L I T Y - N T I S l. ' „ OARNL -

9441 Date September 1979 112710 122100 610000 717000 793000 810000 G A M M O N Activation Library. Battat, M.E.; LaBauve, R.J.; Muir, D.W. L A - 8 0 4 0 - M S AVAILABIL ITY-DEP. , NTIS, PC A03 /MF A0I LOASL

9538 Date November 1979 122100 122200 220000 610000 531000 532000 „ Kerma Factors for Neutrons and Photons with Energies


F o r m u l a s , G r a p h s , T a b l e s , and N o m o g r a m s - X - R a y


6775 Date October 1977 121200 613000 Semiempirical Auger-Electron Energies for Elements 10

Z 100. Larkins, F.P. q ATOMIC DATA AND NUCL. DATA TABLES, 20(4),

311-387 AUSTRA,,

" 8822 Date August 1978 122200 613000 K and L X - R a y Mass Attenuation Coefficients for L o w - Z

Materials. Montenegro, E.C.; Baptista, G.B.; Duarte, P.W.E.P.

A T O M I C DATA A N D NUCL. DATA TABLES, 22(2), 131-177

BRAZIL

8912 Date August 1978 613000 The Internal Conversion Coefficients of the 2 -0 , E2

Nuclear Transitions in Even-Even Nuclei. Mladjertovic, M.; Zupancic, M.; Vukanovic, R. ATOMIC DATA A N D NUCL. DATA TABLES, 22(2),

109-123 tl

YUGOSL

^ S h i e l d S h a p i n g , P l a c e m e n t , a n d O p t i m i z a t i o n


6450 Date Dec. 1977 620000 717000 883000 312000 Optimal-Iron-Water Shields for Fusion Reactors. Gilai, D.; Greenspan, E.; Levine, P.; Price, W.G.,Jr. CONF-770401, PP.731 -738 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


7106 Date July 1976 111110 32B000 521130 522130 620000 810000 Optimum Multilayer Shadow Shielding for a Reactor. Sakovich, V.A.; Sakharov, V.M. ERDA-TR-125 , PP. 79-87 AVAILABIL ITY-1976 RUSSIA

7107 Date July 1976 111500 112B00 620000 A N Optimality Criterion for the Shape of Reactor Shield-

ing. Goryavhev, I.V.; Kuznetsov, V.G.; Sakovich, V.A. ERDA-TR-125 , PP. 88-91 A V A I L A B I L I T Y - N T I S RUSSIA

8798 Date February 1979 111110 223000 329000 721100 721200 722100 620000

719A00 422110 Reactor Cavity Streaming--The Problem and Engineer-

ing Solutions, lotti, R.C.; Yang, T.L. ORNL/RSIC-43,PP.76-109; " ANS/SD-79/16.PP.76-109

255'

A V A I L A B I L I T Y - N T I S EBASCO

JAPAN

8950 Date May 1978 111210 122310 32AOOO 521130 522130 620000 717000 A Minimum-Thickness Blanket/Shield with Optimum

Tritium Breeding and Shielding Effectiveness. Gerstl, S.A.W. CONF-780508,VOL. 1, PP.269-278 A V A I L A B I L I T Y - D E P . , NTIS LOASL

6444 Date Dec. 1977 631000 722100 A Simple Albedo Method for Calculating Effects of Sin-

gle-Legged Ducts. Celnik, J. CONF-770401, PP.688-693 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 BURNS i!

9276 Date May 1978 620000 717000 Design of the Segment Structure and Coolant Ducts for a

Fusion Reactor Blanket and Shield. Brians, D.A.; Stan'oridge, J.R. C L M - R - 1 8 4 A V A I L A B I L I T Y - D E P . , NTIS (U.S. SALES O N L Y ) ENGLAN

8476 Date January 1979 112720 631000 223000 719A00 An Empirical Formula Predicting Shutdown Dose Rate of

the Recirculation Pipes in Boiling Water Reactors. (Tech. Note)


NUCL. SCL ENG., 69(1), 78-85 JAPAN

942 1 Date 1977 111210 620000 710000 717000 810000 o Neutral Beam System for an Ignition Tokamak. Fasolo, J.; Fuja, R.; Jung, J.; Moenich, J.; Norem, J.; Praeg,

W.; Stevens, H. CONF-771029-177 A V A I L A B I L I T Y - N T I S , PC A02 /MF A01 ARGONN

942 2 Date 1977 111210 620000 710000 717000 810000 Mechanical Design and Analysis for an EPR First

Wall/Blanket/Shield System. Stevens, H.C.; Misra, B.; Youngdahl, C.K. CONF-771029-194 A V A I L A B I L I T Y - N T I S , PC A02 /MF A01 ARGONN

Gross Models for Approximate Calculations


9738 Date M i d - A p r i l 1980 222000 631000 731200 Effects of Indoor Residence on Radiation Doses from Rou-

tine Releases of Radionuclides to the Atmosphere. Kocher, D.C. NUCL. TECHNOLOGY, 48(2), 171-179 OARNL

Special Models for Approximate Calculations - Calculated Attenuat ion

Kernels (includes buildup factors) CATEGORY NUMBER 632110

6442 Date Dec. 1977 632110 632300 Theory and Use of Maniscalco Two-Medium Buildup Fac-

| tors. Hungerford, H.E. CONF-770401, PP.668-679 x>o ° A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 r

U - I N

6443 Date Dec. 1977 631000 713000 721100 Development of a Computer Code for Neutron Streaming

Calculations in LMFBR. Nishimura, T.; Kinjo, H. CONF-770401, PP.680-687 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6445 Date Dec. 1977 632110 522120 The Optimisation of Shielding for Direct-Cycle Steam

Turbine Plant. Martin, A.; Firmin, G.H.; Eaton, J.R.P. CONF-770401, PP.694-702 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR. cPRINCETON, NJ 08540

256'

E N G L A N BETTIS

7098 Date July 1976 111110 112110 112400 112500 325000 521130 522130


A.V. E R D A - T R - 1 2 5 , PP. 6 -10 A V A I L A B I L I T Y - N T I S RUSSIA

8095 Date September 1978 112B00 512110 632110 853100 Berger Coefficients for the Eisenhauer-Simmons

Gamma-Ray Buildup Factors in Ordinary Concrete. (Tech. Note)

Metghalchi, M. NUCL. SCI. ENG, 67(3), 341-342 I R A N

8197 Date January 1976 111130 112120 112130 113100 512110 512210 632110

795179 830000 Version 4 of ATR (Air Transport of Radiation). Huszar, L.; Woolson, W.A.; Straker, E.A. DNA-3995F A V A I L A B I L I T Y - N T I S SCA

8249 Date November 1978 632110 Cylindrical Source Shielding Equations Utilizing Compact

Functions and Including Buildup. Kamphouse, J.L. NUCL. SCI. ENG, 68(2), 212-217 " GILBER

8690 Date March 1979 112B00 512110 632110 853100 Tchebycheff-Fitted Berger Coefficients for Eisen-


Chilton, A.B. NUCL. SCI. ENG, 69(3), PP.436-438 U - I L

8920 Date May 1979 112B00 512110 632110 820000 861000 870013 On the Polynomial Form of Gamma-Ray Buildup Factor

Functions. Metghalchi, M. NUCL. SCI. ENG, 70(2), 207-209 I R A N "

9018 Date Apri l 1978 112930 632110 731200

• Protective Action Evaluation. Part 1. Effectiveness of Shel-tering as a Protective Action Against Nuclear Accidents Involving Gaseous Releases.

Anno, G.H.; Dore, M.A. EPA-520/1 -78-001A A V A I L A B I L I T Y - N T I S EN PA

9634 Date March 1980 512110 632110 853100 Concrete Buildup Factors Based on the American National

Standard for F lux- to-Dose-Rate Conversion. (Let-ter to the Editor)

Chilton, A.B.; Brown, R.W. NUCL. SCI. ENG, 73(3), 301 U - I L

'8379 Date August 1978 220000 632110 Depth Dose, Dose Equivalent and Quality Factor for Reac-

tor Neutron Spectra. Singh,'»D.; Bisht, J.S.; Madhvanath, U. HEALTH PHYS, 35(2), 369-374 IND IA

9730 Date January 1980 112B00 327000 512110 632110 820000 830000 861000 Photon Point Source Buildup Factors for Air, Water, and

Iron. (Tech. Note) Chilton, A.B.; Eisenhauer, C.M.; Simmons, G.L. NUCL. SCI. ENG, 73(1), 97-107 U - I L

8689 Date March 1979 112B00 512110 632110 820000 861000 870082 Gamma-Ray Dose Rate Conversion and Buildup Factors.

(Tech. Note) Shure, K. NUCL. SCI. E N G , 69(3), PP.432-436

0 10137 Date July 1980

112710 522120 632110 810000 Exposure Rate Conversion Factors for Radionuclides Depos-

ited on the Ground. Beck, H.L. EML-378

a

257

A V A I L A B I L I T Y - D O E , NEW YORK, N.Y., ENVI-R O N M E N T A L MEASUREMENTS LABORATORY

DOE

Special Models for Approximate Calculations - Semi-empirical

Attenuation Kernels (includes buildup factors)

CATEGORY NUMBER 632120 7076 Date January 1977

112B00 632120 810000 Gamma Ray Buildup Factors for Finite Media. John, K.; Gopinath, D.V. NBS SPEC. PUB. 461, PP. 174-176 " A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


9919 Date July 1979 112120 552110 711100 719A00 632120 Gamma Doses from Irradiated Assemblies Under Water. Rinard, P.M. L A - 7 9 1 4 - M S A V A I L A B I L I T Y - N T I S 54.50 LOASL

Special Models for Approximate Calculations - Geometric

Transformat ions or Geometry Computations

CATEGORY NUMBER 632200 6619 Date March 1978

329000 632200 717000 "Sensing" the Elliptical Torus. Cash'well, E.D.; Everett, C.J. L A - 7 1 8 7 - M S A V A I L A B I L I T Y - N T I S LOASL

ft

6625 Date February 1978 632200 SNAKE: A Solid Angle Calculational System. Thompson, J.K.; Lewallen, M.A.; Trapp, T.J. NUREG/CR-0004 A V A I L A B I L I T Y - N T I S $4.50 BANW

6697 . . Date March 1978 111110 121100 610000 632200 810000 794000 SUPERDAN: Computer Programs for Calculating

Dancoff Factor of Spheres, Cylinders, and Slabs. the

Knight, J.R. y

O R N L / N U R E G / C S D / T M - 2 A V A I L A B I L I T Y - N T I S $6.00 OARNL

6933 Date March 1978 32COOO 632200 INGEN: A General-Purpose Mesh Generator for Finite

vElement Codes. Cook, W.A. , L A - 7 1 3 5 - M S A V A I L A B I L I T Y - N T I S LOASL

7058 ': Date January 1977 121100 121200 632200 Geometric Factors in Radiation Physics Measurements. Ghose, A.M. NBS SPEC. PUB. 461, PP. 47-54 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


7103 , Date July 1976 111110 112B00 310000 632200 Applying Methods from Photometry and the Theciry of

Radiant Heat Exchange to the Transfer of Ionizing Radiation. n

Mironov, V.N. ERDA-TR-125 , PP. 46-53 A V A I L A B I L I T Y - N T I S RUSSIA „ J

8789 Date March 1979 632200 FFCG - A Free-Form Input Combinatorial Geometry

Package." Fraley, S.K. O R N L / C S D / T M - 7 3 A V A I L A B I L I T Y - N T I S $4.50 OARNL

9023 Date April 1979 32COOO 632200 " OASIS: A General Purpose Mesh Generator for Finite Ele-

ment Codes. Gerhard, M.A. M -101 A V A I L A B I L I T Y - L A W R E N C E L IVERMORE LABO-

RATORY, UNIVERSITY OF CAL IFORNIA , LIVERMORE, CA 94550

L A L L

'v/

258'

1 Special Models for Approximate 0 Calculations - Special Shielding Formulas

CATEGORY NUMBER 632300 <••

D U N - S A - 1 5 1 . A V A I L A B I L I T Y - N T I S

,;>nDOUGLA

Jj 6442 . . . Date Dec.

632110 632300 , Theory and Use of Maniscalco T w o - Medium Buildup

tors. Hungerford, H.E. CONF-770401, PP.668

Date June 1978 - ^ p ' K 6935 I 1 1 ? 1 0 7 1 0 0 0 0 717000 793000 795254 853100

..Shielding Calculations for the Intense Neutron Source Facil-ip Fac4';£' " i ty . Final Report. «

Henninger, R.J.; Macdonald, J.L.; Dudziak, D.J.

&?i^#v&(LA-7332^MS* ' "" -> A V A I L A B I L I T Y - S C I E N C E PRESS, 8 B R O O ^ Q ^ ; ^ ' . . ^ y ^ I L A B I L I T Y - N T , I S $4.00'

C'vi*'1

-679

-id. v.C' v l i ' f c r f Battat, M.E.;

u DR., PRINCETON, NJ 08540

- I N '•.^'""ub'ASL


rium Beam Injectors. Kim, J. O R N L / T M - 6 1 8 9 A V A I L A B I L I T Y - N T I S $4.50 O A R N L o a

8456 ^ Date October 1978 112760 220000 2230^0 632300 861000 Generic Assessment of Radiation Exposures to Workers in

a Portable Smelter and to the Surrounding Population. Randolph, M.L.; Watson, A.P.; O'Donnell, F.R. O R N L / T M - 6 4 4 2 * A V A I L A B I L I T Y - N T I S O A R N L ^

Engineered Shields and Shielding Projects

7110 ! . Date July 1976 11,U 10 421140 421130 521230 7J0000 719A00 Investigation of the Absolute Fluxes and Spectra of Fast,

Neutrons Striking the Reactor Vessel in the Second Unit of the Novo-Voronezhskaya AES. ( q -

Barinov, A.L. ; VikinJ V.A.; Glushchenko, A.I.; Yegorov, Yu.A.; Kovalenko, V.V.; Luk'yanov, M.A.; Orlov,

• , Yu.V.; Razumovskiy, M.V.; Tsofin, V.I. E R D A - T R - 1 2 5 , PP. 106-118 j A V A I L A B I L I T Y - N T I S ' RUSSIA ,. 0

7111 Date July 1976 111110 421130 421200 521230 522230 710000 719A00


the Novo-Voronezhskaya AES's Second Unit. Glushchenko, A.I . ; Orlov, Yu.V.;'Satarin, V.Ye. E R D A - T R - 1 2 5 , PP. 119-126 * ° A V A I L A B I L I T Y - N T I S RUSSIA


6424. Date Dec. 1977 111210 710006 Shield Analyses for Intense 2.2pJ(14-MeV) Neutron

Sources. Battat, M.E.; Dudziak, D.J. CONF-770401, PP.520-526 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


&

6804. . Date September 5, 1970 111110 710000 740000 853100 853300 853400 853700 N Reactor Shielding. Davis, H.S.

8802 Date February 1979,;-, 111110 32A000 551110 719A00 710000 721100 810000 A Low Pressure Drop Reactor Cavity Shield System. Klotz, R.J.;,, Cavanaugh, G.P.; Kassawara, R.P.;

McLaughlin, D.J.; Pilver, 'A.B. ORNL/RSIC-43,PP.137-148;

ANS/SD-79/16,PP.137-148 o A V A I L A B I L I T Y - N T I S COE

8803 ^ : . . .' Date0February 1979 o , 111110 329000 710000 719A00 721100 795207 810000 Radiation Streaming and Reactor Cavity Shield Design at

T V A PWR Plants-, :

Francis, C.C.; Galbreth, T.M.; Zobel, W. t ORNL/RSIC-43 ,PP.149-162;

ANS/SD-79/16,PP.149-162

259' Q

A V A I L A B I L I T Y - N T I S TVA

8805 Date February 1979 111110 795144 710000 721100 719AOO 810000 0

Shield Design Against Neutron Streaming,in the Vicinity of a BWR Pressure Vessel.

Seifferth, L.; Przibram, E.; Hock, R. ORNL/RSIC-43,PP. 178-192;

ANS/SD-79/16,PP.178-192 -A V A I L A B I L I T Y - N T I S *& GERMAN




NUREG/CR 70134; O R N L / N U R E G / T M - 2 1 5 AVAILAB1LI7-Y' :--DEP., NTIS O A R N L ,

9195 Date September 1977 ^ 111220 710000 750000 " PEP Radiation Shielding Tests in SLAC A Beam. u Ash, W.; DeStaebler, H.; Harris, J.; Jenkins, T.; Murray, J. S L A C - T N - 7 7 - 5 ; PEP-252 A V A I L A B I L I T Y - D E P . , NTIS STL A C

9421 !'Date 1977 111210 620000 710000 717000 810000 Neutral Beam System for an Ignition Tokamak. Fasolo, J.; Fuja, R.; Jung, J.;' Moenich, J.; Norem, J.; Praeg,

W.; Stevens, H. CONF-771029- 177 A V A I L A B I L I T Y - N T I S , PC A02 /MF A01 ARGONN

9422 Date 1977 111210 620000 710000 717000 810000 Mechanical Design and Analysis for an EPR First

Wall/Blanket/Shield System. Stevens, H.C.; Misra, B.; Youngdahl, C.K. CONF-771029- 194 " A V A I L A B I L I T Y - N T I S , PC A02/MF A01 ARGONN r ' o

Fuel Reprocessing and Fabrication c? CATEGORY N U M B E R 711100

6626 Date February 1978 . 111110 329000 711100 (> i " Critique of the Solid Angle Method. Oden, D.R.; Thompson, J.K.; Lewallen, M.A.; Trapp, T.J. NUREG/CR-0005 A V A I L A B I L I T Y - N T I S S5.25 » BANW

8850. Date September 1978 010000 122100 711100 712000 810000 Fuel Handling, Reprocessing' and Waste and Related

Nuclear Data Aspects. Kusters, H.; Lalovic, M.; Wiese, W.H. CONF-780921, PP.518-550 i f A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL ,

75f775 PARIS CEDEX 16, FRANCE GERMAN

9260 Date July 1979 „ 0 112760 421200 424000 711100 870094 870095 A Nondestructive Assay System for Use in Decommission-

ing a Plutonium-Handling Facility. Roche, C.T.; Vronichi'J.J.; Bellinger, F.O.; Perry, R.B. A N L - 7 9 - 6 0 A V A I L A B I L I T Y - A R G O N N E N A T I O N A L LABORA-

TORY,, ILL. ARGONN


for Radionuclides Occurring in Routine Releases from Nuclear Fuel-Cycle Facilities. Vol.II."

Dunning, D.E.,Jr.; Bernard, S.R.; Walsh, P.J.f Killough, G.G.; Pleasant, J.C.

NUREG/CR -0150,VOL.2; O R N L / N U R E G / T M - 190/V2

A V A I L A B I L I T Y - N T I S OARNL,

9388 Date October 1979 010000 111210 711100 717100 0

Hybrids for Direct Enrichment and Self-Protected Fissile Fuel Protection.

Conn, R.W.; Kan.trowitz, F.; Vogelsang, WvF. UWFDM-316 AVAILABIL ITY- -FUSION ENGINEERING PRO-

GRAM, NUCLEAR ENGINEERING DEPT., UNIVERSITY OF WISCONSIN, MADISON, W p 53706

U - W I

260'

9531 Date February 1979 424000 711100 719B00 Design and Evaluation of a Nondestructive Fissile Assay

Device for HTGR Fuel Samples. McNeany, S.R.; Knoll, R.W.; Jenkins, J.D. O R N L / T M - 6 6 1 0 A V A I L A B I L I T Y - N T I S S4.50 O A R N L

9760 Date 1979 111210 329000 711100 717100 795203 Monte Carlo Statistical Weighting Methods for External

Source Driven Multiplying Systems. Ragheb, M.M.H.; Maynard, C.W. CONF - 790402,VOL. 11, PP.7 - 21 - - 7 - 35 A V A I L A B I L I T Y - H C - - A N S V IRGIN IA SECTION,


U - W I O

9919 Date July 1979 112120 552110 711100 719A00 632120 Gamma Doses from Irradiated Assemblies Under Water. Rinard, P.M. L A - 7 9 1 4 - M S A V A I L A B I L I T Y - N T I S S4.50 LOASL

9933 Date May 1980 111110 122110 122210 711100 793000 794000 810000 FCXSEC: Multigroup Cross-Section Libraries for

Nuclear Fuel Cycle Shielding Calculations. FordT W.E.,111; Webster, C.C.; Diggs, B.R.; Pevey, R.E.;

Croff, A.G. O R N L / T M - 7038; ENDF-287 A V A I L A B I L I T Y - N T I S O A R N L ->

9991 Date August 1980 111110 122110 329000 711100 793000 794000 810000 KENO Calculations of Light Water Fuel Lattices. Hebert, M.J.; Handschuh, J.A.; Pilat, E.E.; Harris, D.R.;

Mayer, J.A. ORNL/RSIC-44 , PP.107-120 A V A I L A B I L I T Y - N T I S , PC A16 /MF A01 YAAEC

10010. . . : Date August 1980 I I I I I O 329000 711100 810000 Applicability,of Monte Carlo Code K E N O - I V . Yamakoshi, H. ORNL /RS IC-44 , PP.345-349

0 A V A I L A B I L I T Y - N T I S , PC A16 /MF A01

JAPAN

10062 Date April 1980 111110 711100 Materials Management in an Internationally Safeguarded

Fuels Reprocessing Plant. Hakkila, E.A.; Cobb, D.D.; Dayem, H.A.; Dietz, R.J.; Kern,

E.A.; Markin, 'J.T.; Shipley, J.P.; Barnes, J.W.; Schein-man, L.

LA-8042, VOL.1 A V A I L A B I L I T Y - N T I S $4.00 LOASL

10063 Date April 1980 111 110 711'00 Materia1- Management in an Internationally Safeguarded

Furls Reprocessing Plant. Hakkila, E.A.; Cobb, D.D.; Dayem, H.A.; Dietz, R.J.; Kern,

E.A.; Markin, J.T.; Shipley, J.P.; Barnes, J.W.; Schein-man, L.

LA-8042, VOL.11 A V A I L A B I L I T Y - N T I S S7.25 LOASL

10064 Date Apr i l 1980 111110 711100 Materials Management in an Internationally Safeguarded

Fuels Reprocessing Plant. Hakkila, E.A.; Baker, A.L.; Cobb, D.D.; Dayem, H.A.;

Dietz, R.J.; Foley, J.E.; Gutmacher, R.G.; Markin, J.T.; Menlove, H.O.; Ostenak, C.A.;' Phillips, J.R.; Reilly, T.D.; Shipley, J.P.; Smith, D.B.; Thomas, C.C.,Jr.;

" Whitty, W.J.; Barnes, J.W.; Bennett, J.E.; Beyerlein, A.L.; Burkhart, L.E.; Cermak, A.F.; Engler, D.R.

LA-8042, VOL.I I I A V A I L A B I L I T Y - N T I S LOASL

Shipping Casks t>


6205 Date October 1975 11170U 112940 32AOOO 329000 521130 522130 712000

810000 795217 795254 795291 Shielding Analysis for the Sealed Storage Cask Concept. Zimmerman, M.G. BNWL-1953 A V A I L A B I L I T Y - N T I S 0

BANW

261 0

6441 Date Dec. 1977 329000 712000 An Examination of Neutron Shielding for a Spent Fuel Ship-

ping Cask. Ueki, K.; Yamakoshi, H.; Takeuchi, K. CONF-770401, PP.660-667 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTON E


8382 Date September 1978 712000 842000 870098 Polyethylene Pellets in the Design and Construction of a

Storage Safe, a Transport Vessel and a Portable Shield for Californium-252. (Notes)

Sharma, S.C.; Hood, J.T. H E A L T H PHYS., 35(3), 496-498 U - M N

A V A I L A B I L I T Y A 0 3 / M F A01

FRANCE

-NT IS (U.S. SALES O N L Y ) , PC

8733 4, - s D a t e February 1979

112120 410000 7120'0fij6300C Safety Analysis Repoi tJTor Packaging: The O R N L Tung-

sten-Shielded Cask^Addendum 1. Evans, J.H.; Mouring, R.W. O R N L / E N G / T M - 3 / A 1 j(

A V A I L A B I L I T Y - N T I S $4.50 fl O A R N L

8850. Date September 1978 010000 122100 711100 712000 810000 Fuel Handling, Reprocessing and Waste and Related

Nuclear Data Aspects. Kusters, H.; Lalovic, M.; Wiese, W.H. CONF-780921, PP.518-550 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,


938,3 Date 1977 111110 712000 713000 810000 Radiation Shield Design for LMFBR Spent-Fuel Shipping

Casks. Dupree, S.A. SAND-77 -0971C; CONF-771109-68 A V A I L A B I L I T Y - N T I S S A N D I A

9900 ; Date 1978 111110 112120 322000 712000 795142 810000 Calculation of Gamma-Rays and Fast Neutrons Fluxes

with the Program M E R C U R E - 4 . ^ Baur, A.; Dupont, C.; Totth, B. C E A - C O N F - 4 4 9 3 ; C O N F - 7 8 U 1 5 8 - 1

9992 Date August 1980 010000 122110 329000 712000 KENO V - The Newest KENO Monte Carlo Criticality

Program. Landers, N.F.; Petrie, L .M. O R N L / R S I C - 4 4 , PP.121-128 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 O A R N L

Fast Reactors



mal Operation of L iqu id-Meta l -Cooled Fast Breeder Reactors.

Erdman, C.A.; Kelly, J.L.; Kirbiyik, M.; Reynolds, A.B. E P A - 5 2 0 / 3 - 7 5 - 0 1 9 A V A I L A B I L I T Y - D E P T . OF N U C L E A R ENGINEER-

ING, V I R G I N I A UNIV. , CHARLOTTESVILLE , VA.

U - V A

6372 Date Dec. 1977 713000

'-> Design of FFTF Shields. Bunch, W.L. CONF-770401, PP.35-43 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

& DR., PRINCETON, NJ 08540 HANFOR

6373 Date Dec. 1977 713000 A Summary of the O R N L Shield Design Supporting Analy-

sis for the FFTF. Engle, W.W.,Jr.; Mynatt, F.R.; Emmett, M.B.; Williams,

M.L. CONF-770401, PP.44-53 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


262'

6381 Date Dec. 1977 312000 713000 Spatio-Energetic Sensitivity of the Equivalent Thermal

Flux on the Intermediate Heat Exchanger of a Typical Fast Breeder Rcactor.

Boioli, A.; Fiorini, L.; Moreau, J.; Suntinger, G. CONF-770401, PP. 132- 139 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6397 Date Dec. 1977 713000 721200 A Study of Fast Neutron Streaming Through the Core Sup-

port-Plant Shield of a LMFBR. Suzuki, I.; Inous, T.; Oka, Y.; Wakabayashi, H.; An, S.;

Sasaki, K.; Miyasaka, S. CONF-770401, PP.271-279 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6382 Date Dec. 1977 312000 713000 861000 870011 Fast Reactor Shield Sensitivity Studies for

Steel-Sodium-Iron Systems, Oblow, E.M.; Weisbin, C.R. CONF-770401, PP.140-148 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR.. PRINCETON, NJ 08540 O A R N L

6408 Date Dec. 1977 112760 719A00 719B00 713000 Prediction of Primary Circuit Contamination in Power

Reactors. Beslu, P.; Costa, L.; Frejaville, G.; Pepin, P. CONF-770401, PP.374-391; ATOMKERNENERGIE,



6385 Date Dec. 1977 010000 713000 721100 Radiation Streaming The Continuing Problem of

Shield Design. Avery, A.F. j, CONF-770401, PP.169-178; ATOMKERNENERGIE,


DR., PRINCETON, NJ 08540 ENGLAN 0

6392 Date Dec. 1977 713000 210000 l>

Irradiation Effects and Design of LMFBR Permanent Rcac-tor Structures.

Blackburn, L.D.; Knecht, R.L. CONF-770401, PP.230-237; ATOMKERNENERGIE,


DR., PRINCETON, NJ 08540 WEE *

6394 Date Dec. 1977 713000 721200 870011 Neutron Transport Through Straight and Once Bent

Sodium Pipe in Shielding of Fast Reactors. Burian, J.; Jansky, B.; Osmera, B.; Otopal, P.; Rataj, J.:

Petrov, E.; Trykov, L.; Nikolajev, A.; Semenov, V. CONF-770401, PP.246-252 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 RUSSIA 0

6421 Date Dec. 1977 713000 BN-350 Reactor Shielding Studies. Bakumenko, O.D.; Zvonarev, A.V.; Kulakovsky, M.Ja.;

Koleganov, Ju.F.; Pomerantsev, G.V.; Sergeev, V.A. Tverdovsky, N.D.; Savitsky, V.I.; Tsurukin, Ju.P. Usanov, V.I.

CONF-770401, PP.494-500; ATOMKERNENERGIE, 30(4), 305-307(1977)

A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROCKSTONE DR., PRINCETON, NJ 08540

RUSSIA

6428 Date Dec. 1977 713000 Shield Design and Streaming Calculations for the Sodi-

um-Cooled PEC Reactor. Prosperi, M.; Tavoni, R.; Travaglini, N. CONF-770401, PP.554-562 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 ITALY °


Calculations in LMFBR. Nishimura, T.; Kinjo, H. CONF-770401, PP.680-687 Q


JAPAN o

263'


with Various Source Spectra on H A R M O N I E and TAPIRO.

Calamand, D.; Desprets, A.; Rancurel, H.; Vienot, R.; Esti-ot, J.C.; Trapp, J.P.; Bargellini, M.L.; Bozzi, L.; Martini, M.; Moioli, P.; Antonini, D.; De Carli, A.; Rado, V.

CONF-770401, PP.795-803 A V A l L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

D R , PRINCETON, NJ 08540 FRANCE

o 6460 Date Dec. 1977

111110 551110 795209 713000 Measurements and Calculations of Neutron Fluxes Through

a Simulation of the CRBR Upper Axial Shielding. Maerker, R.E.; Muckenthaler, F.J. CONF-770401, PP.812-818 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6461 Date Dec. 1977 " 010000 713000 UK Fast Reactor Shield Design and Performance. Butler, J.; Brindley, K. W. CONF-770401, PP.819-832 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE



Meteer, J.W. ICP-1050-3 A V A I L A B I L I T Y - D E P . , NTIS ALCC

6584 Date 1976 111110 122310 713000 870092 870094 The Importance of Fast Fission Cross Sections in Fast Reac-

tors. o Bohn, E.M.; McKnight, R.D. A N L - 7 6 - 9 0 , PP.31-44 A V A I L A B I L I T Y - N T I S ARGONN

6612 Date December 1977 o 111110 010000 719BOO 713000 810000 Shielding and Control Materials for the Gas-Cooled Fast

Breeder Reactor.

Simnad, M.T. G A - A - 1 4 4 7 8 A V A I L A B I L I T Y - N T I S $14.50 GEAC


Theory Neutronics Results for Perturbation Analyses. Vondy, D.R.; Fowler, T.B. ORNL-5376 A V A I L A B I L I T Y - N T I S $6.00 O A R N L


Fast-Reactor Structural Materials. Smith, A.; McKnight, R.; Smith, D. A N L / N D M - 4 1 A V A I L A B I L I T Y - N T I S ARGONN


Standard Fast Reactor with the OSKAR-75 System of Constants.

Bobkov, Yu.G.; Usachev, P.N. A N L - T R A N S - 1 0 8 6 ; FEI-659 ( I N RUSSIAN) A V A I L A B I L I T Y - N T I S RUSSIA

6674 Date November 1976 122100 112120 713000 Intercomparison of Recent Evaluations for the Capture

Cross Sections of Some Fission-Product Nuclides. Gruppelaar, H.; Janssen, A.J.; Dekker, J.W.M. ECN-12 A V A I L A B I L I T Y - S T I C H T I N G ENERGIEONDER-

ZOEK CENTRUM NEDERLAND, PETTEN NETHER

6679. Date 1977 010000 111110 531000 532000 713000 Overview of Gamma-Ray Energy Deposition and Spectra

in Fast Reactor Environments. Gold, R. H E D L - S A l238;"CONF-771036-7 ? AVA ILAB IL I ' l , '>F.P„ NTIS WEE

264'

6709 Date September 1976 111110 111210 121100 210000 713000 717000 861000 A Systematic Approach to the Radiation Damage Problem

in Fission and Fusion Reactor Structural Alloys. Bullough, R.; Eyre, B.L.; Kulcinski, G.L. U W F D M - 1 8 4 A V A I L A B I L I T Y - N U C L E A R ENGINEERING

D E P A R T M E N T , U N I V E R S I T Y OF WISCONSIN, M A D I S O N , W I S C O N S I N

U - W I

6817 Date 1978 010000 112120 713000 Status of Fission Product Yields Required for Fast Reactor

Dosimetry. o Lammer, G.; Lammer, M. I A E A - 2 0 8 , VOL. I , PP.301-318 A V A I L A B I L I T Y - I N I S M I C R O F I C H E CLEARING-

HOUSE BELGIU



6890 Date November 1977 010000 112120 532000 610000 713000 The Distribution of Fission Product Decay Heat. Turland, B.D.; Peckover, R.S. " C L M - P - 5 1 0 A V A I L A B I L I T Y - U K A E A RESEARCH GROUP,


E N G L A N

6910 Date May 1978 112120 532000 713000 Decay Heat for the Fast Test Reactor (FTR). Schmittroth, F. H E D L - T M E - 7 7 - 13 A V A I L A B I L I T Y - N T I S $5.25 H A N F O R «

6943 Date June 1978 111110 325000 551110 713000 810000 Test of the Diffusion Theory Difference Equations in Slab

Geometry (Computer Code VANCER) . Vbndy, D.R.; Fowler, T.B.

O R N L - 5 3 8 1 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

6979 Date August 1978 111110 325000 551110 713000 Benchmark Calculations for a Sodium-Cooled Breeder

Reactor by Two- and Three-Dimensional Diffusion Methods- I I . (Tech. Note)

BuckeL'G.; Kufner, K.; Stehle, B. N U C L . SCL ENG., 67(2), 257-259 G E R M A N

7049 Date August 1977 111110 112120 713000 870094 Fast Reactor Fission Yields for 239-Pu and 241-Pu. Maeck, W.J. ICP-1050-11 A V A I L A B I L I T Y - A L L I E D C H E M I C A L CORPORA-

T I O N , I D A H O C H E M I C A L PROGRAMS A L C C


W A S H I N G T O N , D.C. 20402 c

I N D I A

7074 Date January 1977 010000 111110 32AOOO 325000 32F000 521130 713000

810000 Neutron Transport Studies in Fast Reactor Shields. Vaidyanathan, R.; Murthy, K.P.N.; Singh, R.S. NBS SPEC. PUB. 461, PP. 163-165 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


7091 Date February 1974 112930 220000 222000 713000 719A00 719BOO Projections of Radioactive Wastes to be Generated by the

U.S. Nuclear Power Industry.c-Blomeke, J.O.; Kee, C.W.; Nichols, J.P. O R N L - T M - 3 9 6 5 A V A I L A B I L I T Y - O A K RIDGE N A T I O N A L LABO-

RATORY O A R N L

265'

7096 Date October 1976 111110 312000 325000 713000 795217 The Spatial Variation of the Damage Energy and Gas Pro-

duction in the Experimental Volume of a L i (D,N) Neutron Radiation Damage Facility.

Alsmiller, R.G.,Jr.; Barish, J. O R N L / T M - 5 5 5 4 A V A I L A B I L I T Y - N T I S O A R N L

8192 Date 1978 111110 122310 312000 521130 713000 870090 870092 Nuclear Data Sensitivity Coefficients for

( 2 3 3 - U — 2 3 2 - T h ) Fueled LMFBR. Turski, R.B.; McKnight, R.D. CONF-780401 - 1 5 A V A I L A B I L I T Y - D E P . , NT IS A R G O N N

8023 Date June 1978 111110 122110 511110 551110 713000 793000 794000

122310 E N D F / B - I V , L I B - I V , and the CSEWG Benchmarks. Kidman, R.B. L A - 7 3 5 5 - M S A V A I L A B I L I T Y - L O S ALAMOS SCIENTIFIC LAB.,


8033 Date August 1978 111110 230000 325000 551110 713000 887000 793000

794000 „ Preliminary Neutronic Study of Actinide Transmutation in

a Fast Reactor. Williams, M.L.; McAdoo, J.W.; Flanagan, G.F. O R N L / T M - 6 3 0 9 A V A I L A B I L I T Y - N T I S S4.50 O A R N L

8111 Date June 1978 713000 870008 870096 Subcritical Reactivity Monitoring: Neutron Yields from a Spontaneous (alpha,n) Reactions in FFTF Fuel. Ombrellaro, P.A.; Johnson, D.L. H E D L - T M E - 7 8 - 3 9 A V A I L A B I L I T Y - D E P . , NTIS (U.S. SALES O N L Y ) HANFOR

8114 Date August 1978 111110 122110 713000 810000 Preparation of Nuclear Data for Detailed Calculation of the

Neutron Spectrum in Fast Systems. Vo'iyakov, V.V.; Voropaev, A.I.; Abdullaev, Kh.Sh.; Voro-

tyntsev, M.F.; Van'kov, A.A.; Krivtsov, A.S.; Pivovarov, V:A.

INDC(CCP) - 124/LV A V A I L A B I L I T Y - I A E A N U C L E A R DATA SECTION,

K A R N T N E R R ING 11, A-1010 V I E N N A IAEA

8193 Date 1978 111110 122310 312000 32A000 521130 713000 794000 Uncertainties in the Breeding Ratio of a Large LMFBR. Marable, J.H.; Weisbin, C.R. CONF-780401 -16 A V A I L A B I L I T Y - D E P . , NTIS O A R N L

8201 Date March 1975 111110 122110 713000 810000 Nuclear Data and Multigroup Methods in Fast Reactor Cal-

culations. Gur,- Y. 1A— 1312; THESIS A V A I L A B I L I T Y - I S R A E L ATOMIC ENERGY COM-

MISSION ISRAEL a

8270 Date August 1°78 010000 112120 713000 719AOO 870092 870094 Needs and Accuracy Requirements for FPND in the Physics

Design of Power Reactor Cores. Rowlands, J.L. IAEA 213, PP.41-60 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) ENGLAN

0 8424 , . . . . .<«> . . . Date October 1978

020000 325000 52)130 713000 810000 Comparison of Calculations of Standard Fast Reactors

(Using the Baker Model)^ " o Voropaev, A.I.; Van'kov, A.A.; Tsybulya, A.M. INDC(CCP)-125 /LV A V A I L A B I L I T Y - I A E A NUCLEAR DATA SECTION,

<, KARNTNER RING 11, A-1010 V I E N N A U - W I

8435 Date January 1979 111 iQ0 112930 122110 329000 32A000 325000 551110

713000 793000 794000 795222 795320 Neutronic Analysis of LMFBRs During Seveje Core Dis-

ruptive Accidents. Tomlinson, E.T. ^ O R N L / C S D - 3 5 ~~

266'

A V A I L A B I L I T Y - N T I S S5.25 O A R N L




8576 Date November 1978 020000 010000 I22HIU 122310 713000 810000 Nuclear Data Needs for Fast Breeder Reactor Shielding. Oblow, E.M.; Perey, F.G. CONF-781117-5 A V A I L A R I L I T Y - D E P , NTIS OARNL

8585 Date 1977 010000 111110 210000 421140 430000 713000 717000



McElroy, W.N.; Bennett, R. A,;,.Johnson, D.L. EUR-5667E/F,PT.I, PP.1-26; CONF-750935.PT.I,

PP. 1-26 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


WEE


the European Countries. ' Farinelli, U. EUR-5667E/F,PT.I, PP.27-40; CONF-750935,PT.I,


T I O N S OF THE EUROPEAN COMMUNITIES, BOITE POSTAL 1003 - LUXEMBOURG

ITALY ' ,

8588 Date 1977 111110 210000 521130,;713000 719A00 795254 861000


Outside the Reactor Core.

Hehn, G.; Stiller, P. " EUR-5667E/F.PT.I, PP.52-62; CONF-750935,PT.I,



GERMAN

8592 Date 1977 111110 020000 421110 713000 <v> Neutron Spectrometry Data in LMFBR Benchmark and

Standard Neutron Fields. De Leeuw-Gierts, G.;De Leeuw, S.; Helmick, H.H.; Rog-

ers, J.W. EUR-5667E/F,PT.I, PP.99-1,18; CONF-750935,PT.I,



BELGIU


tors. Etherington, E.W. EUR-5667E/F,PT.I, PP.375-413;


TIONS OF THE ' EUROPEAN COMMUNIT IES, BOITE POSTAL 1003 - LUXEMBOURG

NETHER

8616 Date 1977 111110 423250 532000 713000 TLD Gamma-Ray Energy Deposition Measurements in

the Zero Energy Fast Reactor Zebra. Knipe, A.D. 0

EUR-5667E/F.PT.I, PP.633-647; CONF-750935,PT.I, PP.633-647

A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-TIONS OF THE EUROPEAN COMMUNITIES, BOITE POSTAL 1003 - LUXEMBOURG

ENGLAN

8618 Date 1977 111110 210000 422110 423250 532000 713000 810000 Dosimetry Work in Connection with Irradiations in the High

Flux(Materials Testing Reactor BR2. Debrue, J.;De Leeuw-Gierts, G.; De Leeuw, S.; Raedt, Ch.

de; Fabry, A.; Leenders, L.; Maene, N.; Menil, R. EUR-5667E/F,PT.I, PP:i700-737;

CONF-750935,PT.I, PP.700-737 0

267 a

AVAILABILITY -OFFICE FOR OFFICIAL PUBLICA-TIONS OF THE EUROPEAN COMMUNITIES, BOITE POSTAL 1003 - LUXEMBOURG

FRANCE

8624 Date 1977 111110 210000 220000 713000 795179 Sensitivity of Fluenee-to-Dose Conversion to Changes in

Fast Pulse Reactor Spectra. Kazi, A.H.; Dunn, T.A.; Saccenti, J.C. EUR-5667E/F.PT.I, PP.808-822;

CONF-750935,PT.I, PP.808-822 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-» TIONS OF. THE EUROPEAN COMMUNITIES,

"'BOITE POSTAL 1003 - LUXEMBOURG A R M Y


ysis. Marable, J.H.; Weisbin, C.R. O ORNL/RSIC-42 , PP.25-48 ° A V A I L A B I L I T Y - NTIS OARNL

8653 Date February 1979 111110 122310 32A000 521130 713000 810000 312000 Controlled Cross-Section Adjustment by Integral Data. Salmi, U.; Wagschal, J.J.; Ya'ari, A.; Yeivin, Y. ORNL/RSIC-42 , PP.49-59 A V A I L A B I L I T Y - N T I S ISRAEL

8632 : Date 1977 111110 421140 713000 719A00 870092 Intercomparison of Reactor Dosimetry Cross Sections Mea-

sured in a Thermal Reactor, in a Fast Reactor and with an Enriched Uranium Fission Plate.

Kimura, I.; Kobayashi, K. EUR-5667E/F,PT.II , PP.142-151; i< CONF-750935,PT.II, PP.142- 151 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


JAPAN

8636 Date 1977 111110 020000 32AOOO 421140 511120 713000 810000 Fast Neutron Spectrum and Dosimetry Studies in the Cou

pled Fast Reactivity Measurements Facility. Rogers, J.W.; Harker, Y.D.; Millsap, D.A. EUR-5667E/F,PT.II , PP.277-295;


TIONS OF T H E EUROPEAN COMMUNITIES, BOITE POSTAL. 1003 - LUXEMBOURG

AEROJE

%

C 8645 Date December 1978 .112120 713000 719A00 795309 870092 870094 Radiation Source Terms:in LWR and LMFBR Spent Fuel

Final Report. Tech. Services Agreement 78-156. Stamatelatos, M.G. EPRI -NP-948

( A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, INC., LA JOLLA, CALIFORNIA 0

SCA

8674 . . . Date February 1979 1U110 122310 32A000 312000 521130 713000 719A00

795204 795254 861000 810000 ° The Use of Error Files in Uncertainty Analysis and DataH

Adjustment. / / Chestnutt, M.M.; MCracken, A.K. ORNL/RSIC-42 , PP.363-373 A V A I L A B I L I T Y - N T I S ENGLAN

8695 Date June 1978 111110 210000 421140 521230 713000 810000 The Zero-Power Basis of Fast Reactor Dosimetry.-1

Sanders, J.E. AEEW-R-1183 A V A I L A B I L I T Y - U K A E A , ATOMIC ENERGY

ESTABLISHMENT, WINFRITHTDORCHESTER, DORSET, GREAT BRITAIN

ENGLAN

8709 Date 1978 020000 11II10 32A000 329000 551120 552220 713000

795254 795320 795203 810000 U.S. Integral and Benchmark Experiments. Maicnschein, F.C. CONF-781117-2

oAVAILABIL ITY-DEP. , NTIS OARNL

8710 Date 1978 010000 111110 32A000 329000 312000 551110 552210

713000 719B00 793000 794000 795254 795320 810000 Methods for; U.S. Shielding Calculations: Applications to

FFTF and CRBR Designs. " Engle, W.W Jr.; Mynatt, F.R.; Disney, R.Ki CONF-781117-3 ' 0 t?

c5> <0

n* 2 6 8

A V A I L A B I L I T Y - D E P . , NTIS O A R N L o

8767 Date January 1979 010000 713000 717100 717500 Status and Prospects of Advanced Fissile Fuel Breeders. Kostoff, R.N. CONF-790103 A V A I L A B I L I T Y - N T I S $7.25 DOE

8770 Date January 1979 111110 122110 521130 713000 810000 " Comparison of Some Multigroup Nuclear Data Sets on

Existing Fast Neutron Assemblies. Cuculeanu, V.; Mocioiu, D.; Constantinescu, D. I N D C ( R U M ) - 9 / G V • <„ A V A I L A B I L I T Y - I A E A NUCLEAR DATA SECTION,

KARNTNER RING 11, A-1010 V IENNA R O M A N I

8872 Date September 1978 122310 713000 Adjustment of Evaluated Neutron Capture Cross-Sections

(« of Neodymium Isotopes to Integral STEK and CFRMF Data.

Gruppelaar, K.; Dekker, J.W.M.; Janssen, A.J.; Rieffe, H.Ch.

CONF-780921, PP.1167-1171 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL,

75775 PARIS CEDE"; 16, FRANCE NETHER

O O

8880 Date 1979 111110 330000 713000 Application of Integral Transport Theory with Linearly


Boehme, R. D O E - T R - 7 1 ; KFK-2501 ( IN GERMAN) A V A I L A B I L I T Y - U S D O E TECHNICAL INFORMA-

T ION CENTER, OAK RIDGE, TENN. GERMAN

8786 Date February 1979 111110 325000 713000 Exposure Calculation Code Module for Reactor Core Analy-

sis: BURNER. Vondy, D.R.; Cunningham, G.W. ORNL-5180 A V A I L A B I L I T Y - N T I S $9.25 O A R N L

8843 Dale September 1978 010000 122310 713000 887000 Determination of Transactinide Nuclear Data Required

Accuracy for Burn-up Calculation in Fast Reactors. Usachev, L.N.; Bobkov, Yu.G.; Kolesov, V.E.; Krivtsov, A.S. CONF-780921, PP.181-186 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL,


9072 Date April 1979 111110 325000 329000 521130 713000 Monte Carlo-Based Validation of the

E N D F / M C * * 2 - I I / S D X Cell Homogenization Path. Wade, D.C. A N L - 7 9 - 5 A V A I L A B I L I T Y - N T I S $5.25 ARGONN

9107 Date June 1979 111110 020000 32A000 325000 521130 795134 795266

713000 793000 794000 SPECTRA-IV, Benchmark Spectra Based on L I B - I V . Kidman, R.B. LA-7861 - MS A V A I L A B I L I T Y - N T I S LOASL

8865 Date September 1978 /. \ 122310 713000 810000 • ; r

Consequences des Incertitudes sur les Donnees de Base dans les Calculs de Protection.

Estiot, J.C.; Rado, V.; Salvatores, M.; Trapp, J.P. CONF-780921, PP.993-998 ° A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL,


(>


trometry. ; De Leeuw-Gierts, G.; De Leeuw, S.; Rogers, J.W.; John-

son, L.O. o TREE-1358; BLG-525

^ A V A I L A B I L I T Y - N T I S $4.50 IDNEL ^

269'

9131 Date 1979 010000 713000 11

Physics Problems of Fast Reactor Shielding. Farinelli, U.; Nicks, R. ATOMIC ENERGY REV., 17(1), 129-179 ITALY

9292 Date 1978 111110 112110 423250 713000 Further Studies on the Mixed Field of Neutrons and Gam-

mas in a Fast Reactor, Using Solid State Dosimeters. Scarpa, G.; Aceto, A.; Moscati, M.; Furetta, C. EUR-5848,PP.737-746; CONF-770597.PP.737-746 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-

TIONS OF T H E EUROPEAN" COMMUNITIES, BOITE POSTALE 1003 - LUXEMBOURG ISBN 92-825-0256-2

I T A L Y


Reactor (FMSR). Burns, T.J.; White, J.R. O R N L / T M - 6 8 5 4 A V A I L A B I L I T Y - N T I S O A R N L



Kelly, G.N.; Simmonds, J.R.; Smith, H.; Stather, J.W. NRPB-R87 A V A I L A B I L I T Y - H M S O ISBN 0 85951 110 3 E N G L A N

9383 Date 1977 111110 712000 713000 810000 Radiation Shield Design for LMFBR Spent-Fuel Shipping

Casks. Dupree, S.A. SAND-77-0971C; CONF-771109-68 A V A I L A B I L I T Y - N T I S SANDIA

9403 Date December 1979 325000 713000 Improved Treatment of the Neutron Streaming Through

Control Rod Followers in a Sodium-Cooled Fast Reac-tor. (Tech. Note)

Yoshida, T. NUCL. SCI. ENG., 72(3), 361-365 GERMAN

9529 Date November 1977 111110 312000 32A000 325000 551110 713000 795320 Transport-Diffusion Comparisons for Small Core LMFBR

Disruptive Accidents. Tomlinson, E.T. O R N L / C S D / T M - 3 8 A V A I L A B I L I T Y - N T I S $5.25 OARNL



Kufner, K.; delMarmol, B.; Minsart, G. CON F - 790402/VOL.11, PP.4 - 35 - - 4 - 47 A V A I L A B I L I T Y - H C - - A N S V IRGINIA SECTION,

P.O. BOX 1260, LYNCHBURG, 24505; M F - - N T I S J ° °

GERMAN

9986 Date August 1980 010000 111110 111220 329000 713000 750000 810000 Monte Carlo Applications at Hanford Engineering Develop-

ment Laboratory. Carter, L.L.; Morford, R.J.-ORNL/RSIC-44 , PP.7-30 A V A I L A B I L I T Y - N T I S , PC A16 /MF A01 HANFOR

Fusion Reactor Shielding (CTR Neutronics)


6242 Date ,1977 121300 122115 32A100 514110 717000 Neutral Hydrogen Transport in a Two-Dimensional Toroi-

dal Plasma Using Multigroup, Discrete Ordinates Methodology.

Wienke, B.R.; Miller, W.R.,Jr.; Seed, T.J.; Rood, P.L. L A - U R - 7 7 - 8 3 9 A V A I L A B I L I T Y - T H E O R E T I C A L DIV., UNIV. OF

CALIF., LOS ALAMOS SCIENTIFIC LABORATO-RY, LOS ALAMOS, NEW MEXICO 87545

LO^SL

o 270



Torus Reactor (EBTR) Reference Design. Santoro, R.T.; Barnes, J.M. ORNL /TM-6085 A V A I L A B I L I T Y - N T I S S4.50 OARNL

6375 Date Dec. 1977 717000 ^ Shield Design for the Joint European TORUS. Avery, A.F.; Chestnutt, M.M. CONF-770401, PP.64-74 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6422 Date Dec. 1977 010000 717000 Important Aspects of Radiation Shielding for Fusion Reac-

tor Tokamaks. Abdou, M.A. CONF-770401, PP.501-511; ATOMKERNENERGIE,


DR., PRINCETON, NJ 08540 ARGONN

6423 Date Dec. 1977 717000 Shielding Problems in the "F INTOR" Design. Nicks, R.; Ponti, C.; Realini, G.; Van Heusden, H. CONF-770401, PP.512-519 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6425. . . : Date Dec. 1977 111210 717000 329000 795203 721100 Monte Carlo Analysis of the Effect^)? Penetrations on the

Performance of a Tokamak Fusion Reactor. Santoro, R.T.; Tang, J.S.; Alsmiller, R.G,Jr.; Barnes, J.M. CONF-770401, PP.527-535 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6436 Date Dec. 1977 329000 717000 ?. Calculation of Toroidal Fusion Reactor Blankets by Monte

Carlo. ~

Macdonald, J.L.; Cashwell, E.D.; Everett, C.J. CONF-770401, PP.622-627 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6437 Date Dec. 1977 329000 717000 A Neutron/Photon/Electron Shielding Study for a

Laser-Fusion Facility. Thompson, W.L. CONF-770401, PP.628-635 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6450 Date Dec. 1977 620000 717000 88 3000 312000 Optimal Iron-Water Shields for Fusion Reactors. Gilai, D.; Greenspan, E.; Levine, P:fPrice, W.G.,Jr. CONF-770401, PP.731-738 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6522 Date January 1978 111210 122110 122310 32A000 521130 717000 795042


Neutronics Data. (Thesis) Reupke, W.A. L A - 7 0 6 7 - T A V A I L A B I L I T Y - N T I S LOASL

6533 Date February 1978 111220 113100 220000 632300 717000 Health Physics^Aspects of Nuclear Radiations from Deute-

rium Beam Injectors. Kim, J. ORNL/TM-6189 A V A I L A B I L I T Y - N T I S $4.50 OARNL

O Q

6537 Date September 1977 717000 793000 795253 Feasibility Study of L iF-BeF /sub 2/ amd Chloride Salts

as Blanket Coolants for Fusion Power Reactors. Imamura, Y. 11

PPPL-1380 , AVAILABIL ITY-DEP. , NTIS

U - N J

271 <3



Arcipiani, B.; Palmiotti, G.; Salvatores, M. NUCL. SCI. ENG., 65(3), 540-544 I T A L Y


Test Reactor. Fillo, J.A.; Powell, J.R.; Benenati, R.; Makowitz, H. BNL-23411; CONF-771029-132 AVA ILAB IL ITY-DEP. , NTIS BROOKH


ment. A Technical Assessment. Scott, J.L. (Ch.) DOE/ET-0015 A V A I L A B I L I T Y - N T I S $6.50 DOE

Date March 1978 6619 329000 632200 717000 "Sensing" the Elliptical Torus. Cashwell, E.D.; Everett, C.J. L A - 7 1 8 7 - M S A V A I L A B I L I T Y - N T I S LOASL

6623 Date 1977 111210 210000 32AOOO 795266 717000 810000 52.1130 Neutron Spectra Characteristics for the Intense Neutron

Source, INS. Battat, M.; Dierckx, R.; Emigh, C.R. L A - U R - 7 7 - 1054; CONF-770523-2 AVA ILAB IL ITY -DEP. , NTIS LOASL


High-Energy Neutrons and Fission - Reactor Neu-trons in Metal.

Mitchell, J.B. UCRL-52,388 A V A I L A B I L I T Y - L A W R E N C E LIVERMORE LAB.,

'„ CALIFORNIA UNIV.

(Vfi % k W

4

L A L L



H.,IV; Dierckx, R.; Gold, R. CONF-771036-6 AVA ILAB IL ITY -DEP. , NTIS ARGONN

6678 Date September 1977 111210 32AOOO 551110 717000 795222 Neutron Wall Loading Characteristics of a Doublet Reac-

tor. Woods, T.J. GA-A-14632 ; CONF-771029-53 AVAILABIL ITY-DEP. , NTIS GEAC


6708 Date November 1977 113100 111600 423300 423120 717000 Radiation Protection Around a Controlled Fusion Research

Facility: The Tokamak of Fontenay-aux-Roses, TFR. UCRL-TRANS-11297 AVAILABIL ITY-DEP. , NTIS FRANCE

6709 Date September 1976 111110 111210 121100 210000 713000 717000 861000 A Systematic Approach to the Radiation Damage Problem

in Fission and Fusion Reactor Structural Alloys. Bullough, R.; Eyre, B.L.; Kulcinski, G.L. UWFDM-184 A V A I L A B I L I T Y - N U C L E A R ENGINEERING

DEPARTMENT, UNIVERSITY OF WISCONSIN. MADISON, WISCONSIN

U - W I

6734 D.Ue May, 197$ 111210 122310 312000 521130 795204 <17000 S70006

870092 861000

272'

Cross-Section Sensitivity Analysis of 235 -U and 238 -U Fission Rates Measured in a Graphite-Reflected Lith-ium Assembly. (Tech. Note)

Seki, Y.; Mackawa, H. ~ ,> N U C L . SCI. ENG., 66(2)^243-251 J A P A N

UWFDM-233 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,


U - W I

6765 Date September 1977 32A100 717000 795254 Multigroup Calculations of Low Energy Neutral Transport

in Tokamak Plasmas. Gilligan, J.G.; Gralnick, S.L.; Price, W.G.,Jr.; Kammash, T. PPPL-1384 A V A I L A B I L I T Y - N T I S U - N J

6771 Date'March 1978 111210 210000 717000 810000 First Wall and Divertor Plate Material Selection in Fusion

Reactors. Conn, R.W. U W F D M - 2 3 7 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,


U - W I


Thermonuclear Radiation. Hunter, T.O.; Abdel-Khalik, S.I.; Kulcinski, G.L. U W F D M - 2 2 1 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,

UN IV . OF WISCONSIN, MADISON, WISCONSIN 53706

U - W I

6768 Date October 1977 010000 111210 210000 717000 810000 Progress in Materials Research for Fusion Reactors. Kulcinski, G.L. U W F D M - 2 2 8 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,

N U C L E A R ENGINEERING DEPT., UNIVERSITY OF WISCONSIN, MADISON, WISCONSIN 53706

U - W I

6769 Date March 1978 010000 111210 111220 210000 717000 810000 Intense Sources of Fast Neutrons. Barschall, H.H. U W F D M - 2 3 1 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,

N U C L E A R ENGINEERING DEPT., UNIVERSITY OF WISCONSIN, MADISON, WISCONSIN 53706

U - W I

6770 Date Apri l 1978 111210 210000 717000 870029 , Surface Damage and Thermal Effects from Transient Ther-

monuclear Radiation in'Tnertial Confinement Fusion Reactors, - "'"i?''4"

Hunter, T.O.; Kulcinski, G.L.

6772. . f l Date April 1978 111210 329000 793000 795203 717000 810000 Three Dimensional Neutronics Analysis of the Mir-

rors-Beam Duct-Shield System for a Laser Driven Power Reactor.

Ragheb, M.M.H.; Klein, A.C.; Maynard, C.W. f, UWFDM S239 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,

NUCLEAR ENGINEERING DEPT., UNIVERSITY OF WISCONSIN, MADISOISf, WISCONSIN 53706

U - W I I.I

6877 Date July 1978 111210 421160 511110 511120 717000 870003 Neutron Spectra and Trit ium Production Measurements in

a Lithium Sphere to Check Fusion Reactor Blanket Cal-culations.

Bachmann, H.; Fritscher, U.; Kappler, F.W.; Rusch, D.; Werle, H.; Wiese, H.W.

NUCL. SCI. ENG., 67(1), 74-84 GERMAN

6935 Date June 1978 111210 710000 717000 793000 795254 853100 Shielding Calculations for the Intense Neutron Source Facil-

ity. Final Report. 0

Battat, M.E.; Henninger, R.J.; Macdonald,')J.L.; Dudziak, ** D.J.

L A - 7 3 3 2 - M S A V A I L A B I L I T Y - N T I S $4.00 LOASL

6946 . . . Date May 1978 112760 112930 222000 717000 Assessment of Radiological"Releases to the Environment

from a fusion Reactor Power Plant.

273'

Shank, K.E.; Oakes, T.W.; Easterly, C.E. O R N L / T M - 6 3 6 8 A V A I L A B I L I T Y - N T I S $5.25 O A R N L

700 0 Date September 1976 111210 717000 810000 o Tokamak Experimental Power Reactor. Stacey, W.M.,Jr.; Abdou, M.A.; Bertoncini, P.J.; et al. •CONF-760935-P1, PP. 21-45 0

A V A I L A B I L I T Y - N T I S ARGONN

700 1 Date September 1976 111210 717000 810000 ' General Atomic Company Experimental Power Reactor

Conceptual Design. Baker, C.C. £> CONF-760935-PI , PP. 47-58 A V A I L A B I L I T Y - N T I S

'•5 j 700 2 Date September 1976

111210 717000 810000 Results and Conclusions from O R N L Tokamak Experimen-

tal Power Reactor Conceptual Studies. Roberts, M. CONF-760935-P1. PP. 59-71 = A V A I L A B I L I T Y - N T I S O A R N L

O

700 3 Date September 1976 111210 717000 810000 rj

TETR - A Tokamak Engineering Test Reactor'to Qualify Materials and Blanket Components for Early DT Fusion,. Reactors.

Kulcinski, G.L.; Conn, R.W.; Maynard, C.W.; et al. CONF-760935-P1, PP. 73-93 „ " A V A I L A B I L I T Y - N T I S U - W I

7004 > ' • . . . . Date September 1976 „ 111210^17000 810000 Tokamak Engineering Technology Facility. Stacey, W.M.,Jr.; Abdou, M.A.; Bolta, C.C.; et al. CONF-760935-P1, PP. 95-105 A V A I L A B I L I T Y - N T I S

<f ARGONN ^ o

! j 7005 o. . Date September 1976 111210 717000 810000 The Field Reversed Mirror as a.Power Reactor. Condit, W.C,Jr.; Carlson, G.A.^Devoto, R.S.; Doggett, J.;

Neef, W. « i' " O

CONF-760935-P1, PP. 107-117 A V A I L A B I L I T Y - NTIS L A L L

i.

7006 Date September 1976 111220 717000 810000 Studies of Catalyzed-D and D - * * 3 H e Fusion Reactor

System. „ " Miley, G.H.; Southworth, F.H.; Choi, C.K.; Gerdin, G.A. CONF-760935-P1, PP. 119-133 A V A I L A B I L I T Y - N T I S U - I L

700 9 Date September 1976 111210 32A000 721100 717000 794000 795254 795222

794000 810000 Effects of Neutron Streaming Through Injection Ports on

Neutronic Characteristics of a Fusion Reactor. ",Ide, T.; Seki, Y.; Iida, H.

CONF-760935-P2, PP. 395-406 A V A I L A B I L I T Y - NTIS JAPAN „ " <

701 0 Date September 1976 111210 717000 810000 The Impact of Neutron Wall Loading on the Cost'of a Toka-

mak Fusion Power System. <==S3 Defreece, D.A.; Fuller, G.M.; Waganer, L.M. -CONF-760935-P2, PP. 421 -432 A V A I L A B I L I T Y - N T I S M C D O N N

//

o , „ 701 1 Date September 1976

J3l0000 111210 717000 810000 , '0 i) u

'What is Past is Prologue: Future., Directions in Tokamak Power Reactor Design Research.

Conn, R.W. CONF-760935-P2, PP. 539-553 A V A I L A B I L I T Y - N T I S f , U - W I

7012 Date September 1976 010000 111210 717000 810000 " , Mirror Machine Reactors. Carlson, G.A.; Moir, R.W. CONF-760935-P2, PP. 555-573 A V A I L A B I L I T Y - N T I S L A L L . 0 ,

' Q

~ £7013.". . . . ! . Date September 1976 '"> " VlOOOO 111210 717000 810000 A Technology Assessment of Laser Fusion Power Produc

tion. v - „

274

Booth, L.A.; Frank, T.G. CONF-760935-P2, PP. 575-589 A V A I L A B I L I T Y - N T I S LOASL

7015 Date September 1976 111210 717000 810000 Conceptual Design of the JAERI Demonstration Fusion

Reactor. Sako, K.; Tone, T.; Seki, Y.; et al. CONF-760935-P2, PP. 607-618 A V A I L A B I L I T Y - N T I S JAPAN

701 6 Date September 1976 010000 111210 717000 810000 The Elmo Bumpy Torus Reactor. McAlees, D.G.; Uckan, N.A.; Bettis, E.S.; et al. CONF-760935-P2, PP. 619-628 A V A I L A B I L I T Y - N T I S O A R N L

or V

701 7 Date September 1976 111210 717000 810000 Design Considerations for a Noncircular Tokamak Demon-

stration Plant. Kearney, D.; Bourque, R.; Chen, W.; et al. CONF-760935-P2, PP. 629-640 A V A I L A B I L I T Y - N T I S GEAC

7018 Date September 1976 010000 111210 111110 717000 A Brief Review of the Fusion-Fission Hybrid Reactor. Tenney, F.H. CONF-760935-P2, PP. 641-655 A V A I L A B I L I T Y - N T I S U - P A ,

7019 Date September 1976 010000 111110 111210 717000 810000 A Conceptual Design Study for a Laser Fusion Hybrid. Maniscalco, J.A. CONF-760935-P2, PP. 657r\675 A V A I L A B I L I T Y - N T I S L A L L

7020 Date September 1976 111210 111110 329000 521130 522130 717000 810000 Neutronic Study of a Laser Fusion Hybrid Reactor Design. Hansen, L.F.; Maniscalco, J.A. CONF-76Q935-P2, PP. 677-688; UCRL-78069

A V A I L A B I L I T Y - N T I S L A L L

7021? Date September 1976 010000 111110 111210 717000 810000 Mirror Hybrids - A Status Report. Lee, J.D.; Bender, D.J.; Moir , R.W.; Schultz, K.R. CONF-760935-P2, PP. 689-710 A V A I L A B I L I T Y - N T I S , \X< GEAC

702 2 Date September 1976 111110 111210 32A000 521130 717000 810000 870090

' 8 70092 The Quality of Fissile Fuel Bred in a Fusion Reactor Blan-

ket. Leonard, B.R.,Jr.; Jenquin, U.P. CONF-760935-P2, PP. 711-722 A V A I L A B I L I T Y - N T I S BANW

702 3 Date September 1976 111210 717000 887000 Design of a Beam-Driven Tokamak for Depletion of Acti-

nide Wastes. Rose, R.P. CONF-760935-P2, PP. 723-739 A V A I L A B I L I T Y - N T I S WEE

7025 Date September 1976 111210 521130 717000 870006 First Wall Studies of a Laser-Fusion Hybrid Reactor


702 8 Date September 1976 010000 111210 210000 32A000 329000 531000 532000

521 130 717000 810000 An Assessment of Nucleonic Methods and Data for Fusion

Reactors. Dudziak, D.J. CONF-760935-P3, PP. 819-832; L A - U R - 7 6 - 2 0 8 6 AV A l L A B I L I T Y - NTIS LOASL

702 9 Date September 1976 q

111210 32A000 551110 552110 721100 717000 810000 Neutronic and Photonic Analysis of U W M A K - I I I Blanket

and Shield in Noncircular Toroidal Geometry.

275'

Gohar, Y.; Maynard, C.W.; Cheng, E.T. CONF-760935-P3, PP. 833-844 A V A I L A B I L I T Y - N T I S U - W I


tions in Tokamaks. ' Abdou, M.A.; Milton, L.J.; Jung, J.C.; Gelbard, E.M. CONF - 76093 5 - P3, PP. 845-860 ' A V A I L A B I L I T Y - N T I S A R G O N N

7031 Date September 1976 111210 122310 312000 32AOOO 511110 870003 717000 Neutronic Data Consistency Analysis for Lithium Blanket

Shield Design. Reupke, W.A.; Muir , D.W. CONF-760935-P3, PP. 861-871; L A - U R - 7 6 - 2 0 9 2 A V A I L A B I L I T Y - N T I S U - G A

7032 Date September 1976 111210 112120 230000 32A000 795217 795254 717000


kets Containing S r -90 and 1-129. Parish, T.A.; Davidson, J.W.; Draper, E.L.,Jr. CONF-760935-P3, PP. 873-882 A V A I L A B I L I T Y - NT IS U - T X


Power Program. Williams, J.M.; Beal, J.W.; Coffman, F.E.; Henning, C.D.;

Zwilsky, K.M. n CONF-760935-P3, PP. 1075-1094 A V A I L A B I L I T Y - NTIS DOE

,7037 Date September 1976 010000 111210 717000 The Euratom Fusion Technology Programme. Hancox, R. CONF-760935-P3, PP. 1095-1103 A V A I L A B I L I T Y - N T I S jfy E N G L A N '

7038 Date September 1976 010000 111210 717000 The Fusion Technology Program in Japan. Mori, S. J CONF-760935-P3, PP. 1105-1112 1

A V A I L A B I L I T Y - NTIS JAPAN

7039 Date September 1976 010000 111210 717000 U.S. Laser Fusion Technology Program. Schriever, R.L. CONF-760935-P3, PP. 1113-1120 A V A I L A B I L I T Y - N T I S DOE

7033 Date September 1976 111210 32A000 521230 422130 717000 717100 870003

870006 870092 793000 795254 Fission-Rate Distributions in Li thium and Hybrid Fusion

Blanket Assemblies. Maekawa, H.; Seki, Y. " CONF-760935-P3, PP. 883-894 A V A I L A B I L I T Y - N T I S JAPAN K'

7040 Date September 1976 010000 111210 717000 Status of the JET Project and Its Supporting Technological

Programme. Bertolini, E. CONF-760935-P3, PP. 1121-1135 A V A I L A B I L I T Y - N T I S E N G L A N

7034 Date September 1976 111110 210000 870006 717000 Neutron Irradiation Effects on Graphite Cloth: Gray, W.J. CONF-760935-P3, PP. 1049-1059 A V A I L A B I L I T Y - N T I S B A N W

7041 Date September 1976 Q 010000 111210 717000 The EPRI Fusion Power Program - Status and Goals. Gough, W.C.

n CONF-760935-P3, PP. 1137-1152 V) A V A I L A B I L I T Y - N T I S

EPRI

o 276

7042 Date September 1976 010000 111210 112760 223000 210000 521130 522130


Reactors. Vogelsang, W.F. CONF-760935-P4, PP. 1303-1318; U W F D M - 1 7 8 A V A I L A B I L I T Y - N T I S U - W I

704 3 Date September 1976 010000 111210 717000 810000 An Assessment of Blanket and Shield Technology. Twining, B.G.; Powell, J.R. CONF-760935-P4, PP. 1433-1446 A V A I L A B I L I T Y - N T I S BROOKH

e> 704 4 Date September 1976

111210 210000 717000 810000 Radiation Damage Analysis as Applied to Fusion Reactor


Santoro, R.T.; Tang, J.S.; Alsmiller, R.G.,Jr.; Barnes, J.M. O R N L / T M - 5 8 7 4 A V A I L A B I L I T Y - N T I S $4.00 O A R N L ,

7130 Date March 1977 111210 32A000 521130 522130 531000 532000 717000


Experimentation Power Reactor. Santoro, R.T.; Baker, V.C.; Barnes, J.M. O R N L / T M - 5 4 6 6 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

( 8025 Date July 1978 112930 220000 222000 717000 810000 Application of Probabilistic Consequence Analysis to the



OF T E C H N O L O G Y U - M A

7050 Date September 1977 111210 122110 122210 32A000 312000 521130 522130


mental Power Reactor. Simmons, E.L.; Gerstl, S.A.W.; Dudziak, D.J. " a L A - 6 9 4 2 - M S A V A I L A B I L I T Y - N T I S $5.00 LOASL

h 7089 ' . . . Date March 1977

111210 717000 O R N L Fusion Power Demonstration Study: Interim Report. Steiner, D.; Bettis, E.S.; Huxford, T.J.; McAfee, W.J.;

McCoy, H.E.; Mense, A.T.; Reid, R.L.;\Scott, J.L.; Shannon, T.E.; Stoddart, W.C.T.; Watts, HiL.; Wells, W.M. ; Werner, R.W.; Wiffen, F.W.

O R N L / T M - 5 8 1 3 A V A I L A B I L I T Y - N T I S 55.50 O A R N L

7090 Date May 1977 111210 311000 329000 531000 532000 793000 717000


Penetration on the Performance of a Tokamak Fusion Reactor. : •

8032 Date September 1978 111210 122100 312000 32A000 511110 512210 717000

830000 842000 853100 861000 882000 £> Macroscopic Cross Section Sensitivity Study for Fusion

Reactor Shielding Experiments. Seki, Y.; Santoro, R.T.; Oblow, E.M.; Lucius, J.L. ORNL-5467 A V A I L A B I L I T Y - N T I S S4.50 O A R N L

8036 Date June 1978 111210 230000 717000 810000 0

Fusion Fuel Cycle Solid Radioactive Wastes. Gore, B.F.; Kaser, J.D.; Kabele, T.J. PNL-2719 A V A I L A B I L I T Y - N T I S BANW


Laser Fusion Reactors. Kulcinski, G.L. U W F D M - 2 5 0 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,

NUCLEAR E N G I N E E R I N G DEPT., UNIVERSITY OF WISCONSIN, MADISON, WISCONSIN 53706

277'

U - W I U - W I

8090 Date September 1978 222000 717000 Calculation'of Radiological Dose Due to Release of Tri t ium

Oxides from Controlled Thermonuclear Reactors. McKone, T.E.; Kastenberg, W.E. N U C L . TECHNOLOGY, 40(2), 170-184 U - C A


Thermonuclear Radiation (Part I). Hunter, T.O.; Kulcinski, G.L. U W F D M - 1 9 6 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,

N U C L E A R E N G I N E E R I N G DEPT., UN IVERSITY OF WISCONSIN, M A D I S O N , WISCONSIN 53706

U - W I

8188 Date June 1978 111210 210000 717000 841000 842000 844000 The Effects of Radiation on Electrical Insulators in Fusion

Reactors. * Phillips, D.C. A E R E - R - 8 9 2 3 A V A I L A B I L I T Y - N T I S E N G L A N

0 ("i

8207 Date October 1978 111210 210000 717000 Nucleonic Aspects of Synfuel Blankets. Dudziak, D.J.; Woodruff, G.L. L A - 7 4 8 5 - M S A V A I L A B I L I T Y - N T I S :LOASL

8130 Date October 1977 111110 111210 111220 121100 121200 531000 532000

/ ' J 17000 810000 Description of the Response of Materials to Pulsed Thermo-

nuclear Radiation. Part I I . Transient Energy Deposition, Temperatures, and Displacement Rate.

Hunter, T.O.; Kulcinski, G.L. U W F D M - 2 1 7 A V A I L A B I L I T Y - F U S I O N ' ' R E S E A R C H PROGRAM;

^ / N U C L E A R E N G I N E E R I N G DEPT., UN IVERSITY OF WISCONSIN, M A D I S O N , WISCONSIN 53706

U - W I

8133 Date July 1978 111210 210000 717000 862000 Effects of Bombarding Ions, on the Void Swelling Profile in

Nickel. O 1-1

Whitley, J.B.;,Kulcinski, G.L.; Smith, H.V.,Jr.; Wilkes, P. ' U W F D M - 2 5 2 | ° a

A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,-N U C L E A R E N G I N E E R I N G DEPT., UN IVERSITY O F W I S C O N S I N , M A D I S O N , WISCONSIN 53706

U - W I ' 0

£ 8135 . . . Date August 1978v^ 111210 521130 522130 532000 717000 795323 % Nucleonic Design for a Compact Tokamak Fusion Reactor

Blanket and Shield. Cheng, E.T.; Maynard, C.W.; Vogelsang, W.F.; Klein, A.C. U W F D M - 2 5 6 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,

N U C L E A R E N G I N E E R I N G DEPT., U N I V E R S I T Y OF WISCONSIN, M A D I S O N , WISCONSIN 53706

8214 Date October 1978 111210 32A000 329000 .531000 532000 5511'10 552120.,

717000 810000 /) Two- and Three-Dimensional Neutronics Calculations

for the TFTR Neutral Beam Injectors. Santoro, R.T.;.lAillieVR.A.; Alsmiller, R.G.,Jr.; Barnes, J.M. ORNL/TM-635"4; CONF-780622-29 ^ A V A I L A B I L I T Y - N T I S S5.25 O A R N L

8228 Date May 1977 111210 329000'521130 717000 810000 Effect of Particle Histories Termination Parameters on


Ragheb, M.M.H.; Gohar, Y.M.; Maynard, C.W. U W F D M - 1 9 2 ^ , q A V A I L A B I L I T Y - F U S I O N T E C H N O L O G Y ° PRO-

GRAM, N U C L E A R E N G I N E E R I N G DEPT., UN IVERSITY OF WISCONSIN, MADISON, WIS-CONSIN 53706

U - W I

u

o (I

8248 Date November 1978 210000 32AOOO 717000 795254(03) Sputtering Calculations with Discrete-Ordinates Method. Hoffman, T.J.; Dodds, H.L.,Jr.; Robinson, M.T.? Holmes,

D.K. NUCL. SCI. ENG., 68(2), 204-211 O A R N L

.5 ,278

825! Date November 1978 222000 71//000 869999 Tritium Pathways and Handling Problems in a Laser Fusion

Reactor. Larsen, E.M.; Abdel-Khal ik, S.I.; Ortman, M.S. NUCL. TECHNOLOGY, 41(1), 12-26 U - W I

8253 Date November 1978 111210 32AOOO 329000 717000 721100 Radiation Shielding of Major Penetrations in Tokamak

Reactors. Jung, J.; Abdou, A. NUCL. TECHNOLOGY, 41(1), 71-86 A R G O N N

8356 Date October 1977 717000 810000 Reactor Dosimetry Studies at the Coupled Fast Reactivity

Measurements Facility (CFRMF). Rogers, J.W.; Harker, Y.D.; Millsap, D.A.; Stepan, I.E. NUREG/CP-0004,VOL.3, PP.1237-1249 A V A I L A B I L I T Y - N T I S U - W I

8373 Date January 1978 111110 111210 32AOOO 521130 717000 795254 810000 TCT Hybrid Preconceptual Blanket Design Studies. Aase, D.T.; Bampton, M.C.C.; Doherty, T.J.; Leonard, B.R.;



WEST LAB. B A N W

it

8411 , Date Apr i l 1978 '111210 210000 717000 870023 Technical Assessment of Vanadium - Base Alloys for Fusion

Reactor Applications. Vol.1. Assessment of Data Base, Needs and Recommendations. Final Report.

Gold,o R.E.; Harrod, D.L.; Ammon, • R.L.; Buckman, R.W,,Jr.; Svedberg, R.C.

COO-4540 - l ( V O L ! l ) | A V A I L A B I L I T Y - N T I S S5.25

WEE

i, 8433 Date October 1978

111210 210000 717000 841000 842000 844000 Evaluation of Performance of Select Fusion Experiments

and Projected Reactors. Miley, G.H. N A S A CONTRACTOR REPORT 3043

O

A V A I L A B I L I T Y - N T I S NAASA

8459 Date October 1978 111,210 112760 112930 220000 223000 521130 531000


mak Fusion Power Plant. Willenberg, H.J.; Bickford, W.E. PNL-2823 A V A I L A B I L I T Y - N T I S PANL , J



RATORY L A L L

8465 Date June 1978 111210 21COOO 717000 861000 870003 810000 Materials Considerations for Inertially-Confined Fusion

Reactors (ICFR). , Hovingh, J. i> UCRL-81206 ; A V A I L A B I L I T Y - L A W R E N C E L IVERMORE LABO-

RATORY J

L A L L

8473 - Date January 1979 321000 325000 717000 Angular Effects in Toroidal Diffusion. Pomraning, G.C. NUCL. SCI. ENG., 69(1), ,6-13 U - C A

848 0 Date January 1979 717000 " O A Parametric Study of a Lithium-Cooled Tokamak Blan-

ket. Chao, J.; Mikic, B.B.; Todreas, N.E. ' ' NUCL. TECHNOLOGY, 42(1), 22-33 U - M A ''

848 1 Date January 1979 230000 793000 794000 717000 Preliminary Design and Neutronic Analysis of a Laser

Fusion Driven Actinide Waste Burning Hybrid Reactor.

a <3

279'

Berwald, D.H.; Duderstadt, J.J. NUCL. TECHNOLOGY, 42(1), 34-50 U - M I


etry to 44 MeV. (i Greenwood, L.R. " O A N L / F P P / T M - 1 1 5 A V A I L A B I L I T Y - N T I S $4.50 A R G O N N

n 8495 Date 1977

111210 210000 717000 810000 Radiation Considerations for Superconducting Fusion Mag-

nets. ,, Abdou, M.A. ( o CONF-770649-6 ° A V A I L A B I L I T Y - NTIS A R G O N N ((

8496 Date January 1978 111210 329000 32A000 551110 552110 793000 717000


Engineering, Trit ium and Neutronics. Project Staff - Argonne National Lab. GA-A14614.VOL.V; ANL/FPP/77-6 .VOL.V A V A I L A B I L I T Y - N T I S $8.00 GEAC

O A R N L

8555. Date February 1979 230000 717000 A Neutronic Assessment of Strontium-90 Transmutation

in Fusion Reactors. Parish, T.A. f / o NUCL. TECHNOLOGY, 42(2), 180-194 U - T X

0 8561. . . Date 1977 010000 111210 717000 Proceedings of the Seventh Symposium on Engineering

Problems of Fusion Research. Vol.1. Lubell, M.S.; Whitmire, C.,Jr. (Eds.) CONF-771029, VOL.1 A V A I L A B I L I T Y - I E E E SERVICE CENTER, S INGLE

PUBLICATION SALES DEPT., 445 HOES LANE, P ISCATAWAY, N.J. 08854!

O A R N L


Problems of Fusion Research. Vol.II. Lubell, M.S.; Whitmire, C.,Jr. (Eds.) CONF-771029,VOL.11 , A V A I L A B I L I T Y - I E E E SERVICE CENTER, S INGLE


O A R N L

8517 ! . . Date February 1979 ..© 020000 ,111210 122310 312000 32AOOO 551110 552110

795276 717000 721100^93000 794000 861000 853100 Cross Section'Sensitivity Analysis of a Proposed Neutron

Streaming Experiment with a Two-Dimensional Model. Sf


O R N L / T M - 6 5 8 8 A V A I L A B I L I T Y - N T I S $4.50' O A R N L ^

8518. . Date January 1979 ^ 111210 122310 32AOOO 52l'f30 551110 717000 793000



Seki, Y.; Santoro, R.T.; Oblow, E.M.; Lucius, J.L. O R N L / T M - 6 6 6 7 , A V A I L A B I L I T Y - N T I S $4.00

8563 Date 1977 111210 32A000 521130 717000 795254 810000 A Practical Blanket Design for a ;Toroidal Fusion Reactor. Bettis, E.S.; Barnes, J.M.; Huxford, T.J.; Liu, K.C.; Santoro,

R.T.; Watts, H.L.^ CONF-771Q29,VOL.11, PP.1453-1458 A V A I L A B I L I T Y - I E E E SERVICE CENTER, S INGLE


O A R N L

8564 Date 1977 111210 329000 531000 532000 717000 795203 J) Nuclear Heat Deposition in Cryosorption Pumps of a Fusion

Reactor. Iida, H.; Ide, T.; Seki, Y. >r CONF-771029,VOL.11, PP. 1658-1662 A V A I L A B I L I T Y - I E E E SERVICE CENTER, SINGLE

t PUBLICATION SALES DEPT., 445 HOES LANE, PISCATAWAY, N.J. 08853 0

JAPAN

280'

8566 Date 1977 ; r l 1210 32A000 521130 717000 810000 795254 Design of the Blanket and Shield for a High-Fie ld Com-

pact Tokamak Reactor (HFCTR). Cook, D.L.; Lidsky, L.M.; Herring, S.; Stephany, W. CONF-771029,VOL.11, PP.1713-1717 A V A I L A B I L I T Y - I E E E SERVICE CENTER, SINGLE

P U B L I C A T I O N SALES DEPT., 445 HOES LANE, P ISCATAWAY, N.J. 08853

U - M A

8567 '1 Date 1977 111210 223000 521130 522130 717000 795217 795254


PUBL ICAT ION SALES DEPT., 445 HOES LANE, -P ISCATAWAY, N.J. 08853

U - T X

0 8585 Date 1977

010000 111110 210000 421140 430000 713000 717000 719A00 719BOO 795112 810000

Neutron Environmental Characterization Requirements for Reactor Materials Development and Surveillance Pro-grams.

McElroy, W.N.; Bennett, R.A.; Johnson, D.L. EUR-5667E/F.PT. I , PP.1-26; CONF-750935,PT.I,

PP. 1 -26 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


WEE n

' 8591 % . . . Date 1977 111210 210000 421140 430000 717000 521130 795254



Odette, G.R. EUR-5667E/F,PT. I , PP.84-97; CONF-750935,PT.I,


T IONS OF THE EUROPEAN COMMUNIT IES, BOITE POSTAL 1003 - LUXEMBOURG ,

U - C A

8663 Date February 1979 111210 122310 32A000 312000 521130 551110 717000


Fusion Reactor Design. ^

Wu, T.; Maynard, C.W. ORNL /RS IC -42 , PP.191-217; U W F D M - 2 9 0 A V A I L A B I L I T Y - N T I S U - W I

8664 Date February 1979 111110 122310 32A000 312000 717000 810000 Uncertainty Analysis for Secondary Energy Distributions. Gerstl, S.A.W. O R N L / R S I C - 4 2 , 219-229 A V A I L A B I L I T Y - N T I S LOASL


Waste Management. (Tech. Note) Meldner, H.., NUCL. SCL ENG., 69(3), PP.438-441 L A L L

8727 Date 1977 111210 329000 717000 795203 810000 Three-Dimensional Analysis of the Effects of Penetrations -

on Radiation Shielding of a Tokamak Fusion Reactor. Ide, T. J A E R I - M - 7 3 6 0 A V A I L A B I L I T Y - J A P A N A T O M I C ENERGY

RESEARCH INSTITUTE, TOKAI , JAPAN JAPAN

8810 Date February 1979 111210 717000 Maximum Neutron Yields in Experimental Fusion Devices. Jassby, D.L. PPPL- 151,5 '--< 0

A V A I L A i j l L I T Y - N T I S U - N J ;.

U


nets. Abdou, M.A. * J. NUCL. MATER., 72(1-2), 147-167 A R G O N N

8859 Date September 1978 122310 111210 329000 421130 421200 511120 512220


Fusion-Fission Hybrid Reactors.

II 0

281

/ > - »

Hansen, L.F.; Wong, C.; Komoto, T.; Pohl, B.A. -CONF-780921, PP.766-771 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

" 75775 PARIS CEDEX 16, FRANCE L A L L

8859 .". Date September 1978 122310 U1210 329000^421130 421200 511120 512220

717000 717000^70096,870092 870029 870041 Neutron Spectra from Materials Used in Fusion and

Fusion-Fission Hybrid Reactors! Hansen, L.F.; Wong, C.; Komoto, T.; Pohl, B.A. CONF-780921, PP.766-771 ft A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, FRANCE L A L L • r,

"8869 Date September 1978 .010000 122100 717000 810000 Nuclear Data for Fusion Reactors. ° Jarvis,,O.N. CONF-780921, PP.1073-1087 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, FRANCE o E N G L A N

8894 Date February 1979 111210 329000 717000 810000 A Conceptual Design of the Fast-Linear Reactor (FLR)

for Fusion Power. t) Moses, R.W.; Kiakowski, R.A.; Mi l ler, R.L. L A - 7 6 8 6 - M S ., A V A I L A B I L I T Y - N T I S LOASL

L 8895 Date December 1978

&

010000 111210 122310 312000 717000 Cross-Section Sensitivity and Uncertainty Analysis for

Fusion Reactors (A Review). Dudziak, D.J. L A - U R - 7 9 - 1 6 8 A V A I L A B I L I T Y - L O S A L A M O S SCIENTIF IC LAB.,

o UNIVERSITY OF CAL IFORNIA , LOS ALAMOS, N E W MEXICO 87544

LOASL "

8908 Date May 26, 1978 111210 329000 717000 717100 810000 Nuclear Desipr) of the L L L - G A U/sub 3/Si Blanket.

0 Lee, J.D. UCRL-80588; C O N F ^ S O S O S ^ " -A V A I L A B I L I T Y - D E P . , NTIS " L A L L

h

8875 Date 1979 111210 210000 717000 810000 852000 ^ Radiation Damage in Diagnostic Windows for the TFTR^ Primak, W. CONF-790125-12 A V A I L A B I L I T Y - D E P . , NTIS A R G O N N a ,. c?

8876 ! Date 1979 010000 111210 210000 717000 810000 Effects of Irradiation on the Normal Metal of a Composite


Klabunde, C.E.; Coltman, R.R,Jr.; Williams, J.M. CONF-790125-25 A V A I L A B I L I T Y - D E P . , NTIS O A R N L

8887 Date March 1979 ^ 111210 210000 717000 861000 e

The Application of Martensitic Stainless Steels in Long Life-time Fusion First Wall/Blankets.

Rosenwasser, S.N.; Miller, P.; Dalessandro, J.A.; Rawls, J.M.; Toffolov, W.E.; Chen, W. ' i t ' ' '

GA-A15356 A V A I L A B I L I T Y - N T I S $4.00 GEAC

c

8909 Date January 1979 11210 210000 717000 810000 " "

Tokamak Reactors and Structural Materials. Conn, R.W. UWFDM-288 A V A I L A B I L I T Y - ' N U C L E A R ENGINEERING

DEPARTMENT, UNIVERSITY OF WISCONSIN, MADISON, WI 53706

U - W I

8924 Date June 1979 111210 717000 870004 Neutron Multiplication (jStudies in Beryllium for Fusion

Reactor Blankets. (Tech. Note) Basu, T.K.; Nargundkar, V.R.; Cloth, P.; Filges, D.; Tacza-

nowski, S. NUCL. SCI. ENG., 70(3), 309-313 G E R M A N

8932 O. . Date January 1979 010000 111210 121100 210000 521130 717000 795217

o795254 810000 Transmutation and Activation of Fusion Reactor Wall and

* * ; v ' Structural Materials. Jarvis, O.N. ft

Q 282'

O o

A'ERE-R-9298 A V A I L A B I L I T Y - H.M.S.O. E N G L A N

CONF-780508.VOL.1, PP.58-63 A V A I L A B I L I T Y - D E P . , NTIS DOE

8936 Date May 1978 010000 111210 717000 u \ \ . Magnetic Fusion Program in t£ie United States: An Over-

view and Perspective. Clarke, J.F. CONF-780508,VOL. l , PP.1-18M A V A I L A B I L I T Y - D E P . , NTIS U DOE » 0

and, Other <J

8937 Date May 1978 010000 111210 717000 Fusion - The Programme in the U.K.

Thoughts. Carruthers, R. CONF-780508,VOL. l , PP.19-27 A V A I L A B I L I T Y - D E P . , NTIS ENGLAN

8938 Date May 1978 010000 111210 717000 Development on Fusion Reactors in Japan. Mori, S.

: CONF-780508,VOL. l , PP.28-37 A V A I L A B I L I T Y - D E P . , NTIS JAPAN

8939 ". Date May 1978., 010000 111210 717000 The JET Project - Progress in •Construction and Manage-

ment. Bertolini, E. CONF-780508,VOL.1, PP.38-49 A V A I L A B I L I T Y - D E P . , NTIS ENGLAN

o 8940 Date May 1978

010000 111210 717000 Advanced Fusion Concepts Program. Dove, W.F. CONF-780508,VOL^.', PP.51-57 A V A I L A B I L I T Y DOE

-DEP., NTIS O

^ 8942 Date May 1978 010000 111210 717000 Tandem Mirror Reactor. Moir, R.W.; Barr, W.L.; Bender, D.J.; Carlson, G.A.; Dex-

ter,' W.L.; Doggett, J.N.; Fink, J.H.; Hamilton, G.W.; Lee, J.D.; Logan, B.G.; Neef, W.S.,Jr.; Peterson, M.A.; Rensink, M .E . (A

CONF-780508,VOL. l , PP.64^73 A V A I L A B I L I T Y - D E P . , NTIS L A L L

w

"8941 v . . Date May 1978 010000 1J 1210 717000 o Alternative Fusion Concepts: Engineering and Uti l i ty Con-

siderations. Gough, W.C.; Amherd, N.A.

8943 .». A . Date May 1978 010000 111210 717000 / / The Elmo Bumpy Torus (EBT) Reactor - A Status Report. Uckan, N.A.; Bettis, E.S.; Dandl, R.A.; Hedrick, C.L.; San-

toro, R.T.; Watts, H.L.; Yeh, H.T. CONF-780508,VOL. l , PP.74-82 AVA ILAB IL ITY -DEP.? NTIS " O A R N L

8944. Date May 1978 010000 111210 717000 The Reversed-Field Multiple Mirror Concept. Steinhauer, L.; Grossmann, W.; Seyler, C.E. CONF-780508,VOL. l , PP.83-89 ( { A V A I L A B I L I T Y - D E P . , NTIS M A S N

Ct 8945 Date May 1978

010000 111210 717000 " v Synfuels Production from Fusion Reactors. Fillo, J.A.; Powell, J.R.; Steinberg, M.; Salzano, F.; Benena-

ti, R.; Dang, V.; Fogelson, S.; Isaacs, H.; Kouts, H.; Kushner, M.; Lazareth, O.; Majeski, S.; Makowitz, H.; Sheehan, T.V.

CONF-780508,VOL. l , PP.193-202 <•* o A V A I L A B I L I T Y - D E P . , NTIS U - N Y

O 8947 Date May 1978

111210 32A000 551110 552110 795276 717000 810000 A BWTR (Boiling Water Tokamak Reactor) Blanket Study. Sze, D.K.; Maynard, C.W.; Sviatoslavsky, I.N.; Cheng,

E.T.; Wang, C.C.; Wrazel, J. CONF-780508,VOL. l , PP.239-248 N

A V A I L A B I L I T Y - D E P . , NTIS U - W I " „ ts,

o

8948. . . v Date May 1978 111210 32AOOO 521130 717000 795042 810000 Nucleonic Aspects of the 'L INUS' Imploding Blanket. Dudziak, D.J. CONF-780508,VOL.1, PP.254-261 A V A I L A B I L I T Y - D E P . , NTIS LOASL

8979 Date January 15, 1979 111210 717000 887000 Actinide Cross Section Data and Inertial Confinement

Fusion for Long Term Waste Disposal. Meldner, H. o UCRL-82177; CONF-781174-6 A V A I L A B I L I T Y - D E P . , NTIS L A L L

8950 Date May 1978 111210 122310 32A000 £21130 522130 620000 717000 A Minimum-Thickness Blanket/Shield with Optimum

Tri t ium Breeding and Shielding Effectiveness. Gerstl, S.A.W. CONF-780508,VOL.I , PP.269-278 A V A I L A B I L I T Y - D E P . , NTIS LOASL

i)

8951 Date May 1978 111210 210000 717000 870006 870014 An Assessment of Carbon and Silicon Carbide as First Wall

Materials in Inertial Confinement Fusion Reactors. Hopkins, G.R.; Price, R.J.; Bullock, R.E.; Dalessandro, J.A.;

Hovingh, J. CONF - 780508,VOL. 1, PP.324-333 A V A I L A B I L I T Y - D E P . , NTIS GEAC

8952 Date May 1978 111210 210000 717000 FWLTB - A Mathematical Model to Calculate the Life-

time of the Fusion Reactor First Wall. Daenner, W.; Raeder, J. C O N F - 780508, VOL. 1 „ PP.347 -356 A V A I L A B I L I T Y - D E P . , NTIS G E R M A N

8956 Date May 1978 010000 111210 210000 717000 810000 Materials Program for Magnetic Fusion Energy. Zwilsky, K.M.;'Cohen, M.M.; Finfgeld, C.R.; Reuther, T.C. CONF-780508,VOL. 1, PP.549-553 A V A I L A B I L I T Y - D E P . , NTIS DOE

C:>

8980 Date March 1979 -111210 717000 N U W M A K - A Tokamak Reactor Design Study. Chapter

I. Design Philosophy. Chapter I I . Overview and Summa-ry-

Badger, B.(Ed.) U W F D M - 3 0 6 A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-

GRAM, NUCLEAR E N G I N E E R I N G DEPARTMENT, UNIVERSITY OF WISCONSIN, M A D I S O N W I 53706

U - W I

9002 Date July 1979 111220 113100 717000 D - D Neutron and X - R a y Yields from High-Power Deu-

terium Beam Injectors. Kim, J. NUCL. TECHNOLOGY, 44(2), 315-321 O A R N L


Fusion Reactors. Verschiiur, K.A. ECN-79 -012 ° A V A I L A B I L I T Y - S T I C H T I N G ENERGIEONDER-

ZOEK C E N T R U M . NEDERLAND (ECN), POSTBUS 1, 1755 ZG PETTEN ( N H ) o

NETHER „ " ^ /

w

8960 Date May 1978 " 111210 717000 810000 " N U M A K " An Attractive Medium Field, Medium Size,

Conceptual Tokamak Reactor. Conn, R.W.; Kulcinski, G.L.; Maynard, C.W. CONF-780508,VOL.2, PP.1049-1059 A V A I L A B I L I T Y - N T I S U - W I 0

9028 Date August 1979 112710 329000 32A000 510000 750000 717000 793000

795178 795203 795276 M A G I K - - A Monte Carlo System for Computing

Induced Residual Activation Dose Rates. Barish, J.; Gabriel, T.A.; Alsmiller, R.G.,Jr. ORNL-5561 ^ A V A I L A B I L I T Y - ; N T l S S6.00 OARNL

1 9029 Date AugustM1979 111110 210000 717000 793000 810000 Calculated Irradiat ion Response of Materials Using Fission

Reactor ( H F I R , ORR, and E B R - I I ) Neutron Spectra. Gabriel, T.A. ; Bishop, B.L.; Wiffen, F.W. O R N L / T M - 6 3 6 1 ° A V A I L A B I L I T Y - N T I S $4.50 O A R N L

9030 Date October 1978 111210 210000 32A000 521130 717000 861C00 862000


Reactor Neutronic Performance. Barnes,, J.M.; Bishop, B.L.; Santoro, R.T.; Gabriel, T.A. O R N L / T M - 6 5 4 3 A V A I L A B I L I T Y - N T I S $4.00 O A R N L


Reactors. Barton, T.P.; Easterly, C.E. O R N L / T M - 6756 A V A I L A B I L I T Y - N T I S O A R N L


Electron-Beam-Fusion Microexplosives. Ragheb, M .M.H . ; Moses, G.; Maynard, C.W. U W F D M - 2 9 5 A V A I L A B I L I T Y - F U S I O N E N G I N E E R I N G PRO-

G R A M , N U C L E A R E N G I N E E R I N G DEPT., U N I V E R S I T Y OF W I S C O N S I N , M A D I S O N W I 53706 ' «

U - W I

9069 . . Date Mid-December 1978 111210 210000 32/\000 521130 810000 861000 717000

795323 j f . Minimiz ing Radioactivity and Other Features of Elemental

and Isotopic Tailoring of Materials for Fusion Reactors. Conn, R.W.; Okula, K.; Johnson, A .W. N U C L . T E C H N O L O G Y , 41(3), 389-400;-

U W F D M - 3 0 5 U - W I

9083 ' Date 1978 111210 230000 717000 Effects of Waste Management on the Impact of Fusion

Power. o

Botts, T.; Powell, J. BNL-24566; ,CONF-780508,VOL.2,PP.903-909 A V A I L A B I L I T Y - N T I S B R O O K H

9106 Date May 1979 111210 32C000 717000 795293 T R I D E N T - C T R User's Manual. Seed, T.J. L A - 7 8 3 5 - M A V A I L A B I L I T Y - N T I S LOASL

9114. . Date August 1979 112760 717000 795203 Dose Rates from Induced Activi ty in the TFTR Test Cell. Alsmiller, R.G.,Jr.; Barish, J.; Santoro, R.T.; Lil l ie, R.A.;

Barnes, J.M.; Ragheb, M . M . H . O R N L / T M - 6 9 0 4 A V A I L A B I L I T Y - N T I S O A R N L

9115 Date July 1979 111210 32A000 795209 717000 Shielding Calculations for the T F T R Neutral Beam Injec-

tors. Santoro, R.T.; Lil l ie, R.A.; Alsmiller, R.G.,Jr.; Barnes, J.M. O R N L / T M - 6 9 4 9 « A V A . I L A B I L I T Y - N T I S $4.50 O A R N L

9123 Date July 1979 111210 32A000 329000 521130 522130 717000C795203


Design. Gnmesey, R.A.; Nigg, D.W.; Scott, A.J.; Wheeler, F.J. TREE-1369 ^ A V A I L A B I L I T Y - D E P . ; NT IS $8.00 EDGERT 9

<5 , 9128Date October 1978 (Rev. January 1979)

111210 121100 32A000 510000 521130 717000 795254 810000

Discrete Transfer Cross Section Expansion for Time Depen-dent Neutron [Transport.

Beranek, F.; et al. U W F d M - 3 0 4 A V A I L A B I L I T Y - N U C L E A R E N G I N E E R I N G

D E P A R T M E N T , U N I V E R S I T Y OF WISCONSIN , M A D I S O N , W I 0

U - W I

O o

% 285

9146 Date September 1979 111210 32AOOO <717000 793000,795254 Neutronic Performance of Fusion Reactor Blankets with

Different Coolants and Structural Arrangements. V Chao, J.; Mikic, B.B.; Todreas, N.E. NUCL. TECHNOLOGY, 45(2), 113-120 U - M A

9188 Date October 1979 111220 421130 423135 423120 511120 717000 D-j'D Neutron Measurements on a 40-kV, 6 0 - A Neutral

ffBeam Test Facility. Kim, J.; Mihalczo, J.T. « O R N L / T M -7016 <i A V A I L A B I L I T Y - N T I S OARNL

9276 Date May 1978 620000 717000 Design of the Segment Gtructure'and Coolant Ducts for a

Fusion Reactor Blanket and Shield. Brians, D.A.; Stanbridge, J.R. " C L M - R - 1 8 4 A V A I L A B I L I T Y - D E P , NTIS (U.S. SALES ONLY) ENGLAN

9306 Date July 1979 111210 329000 521130 717000 793000 794000 795254

810000 Fast Rigorous Numerical Method for the Solution cf the


Takahashi, A.; et al. KFK-2832/1 A V A I L A B I L I T Y - K E R N F O R S C H U N G S Z E N T R U M

KARLSRUHE GMBH, KARLSRUHE (F.Rp GER-M A N Y ) . . G ' "

GERMAN (i

0 A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-

GRAM, NUCLEAR ENGINEERING DEPT., UNIVERSITY OF WISCONSIN, MADISON W I 53706

U - W I

9326 : . . . Date 1978 111210 32A000 521130 522130 717000 793000 795254

810000 Q Demonstration Tokamak Hybrid Reactor (DTHR) Blanket

Design Study, December 1978. Chi, J.W.H. (Ed.) WFPS-TME-106 A V A I L A B I L I T Y - F U S I O N POWER SYSTEMS

DEPT., WESTINGHOUSE ELECTRIC CORP, PENN.

WEE

9342 . ..Date September 1977 111210 32AOOO 521130 522130 793000 795254 717000 Fusion Blankets for Catalyzed D - D and D - * * 3 H e Reac-, ej

tors. Q Fillo, J.A.; Powell, J.R. „•• EPRI -ER-536 -SR, PP.57-67 A V A I L A B I L I T Y - B R O O K H A V E N , N A T I O N A L LAB-

ORATORY, UPTON, N Y 0

BROOKH

9386 Date August 1979 010000 111210 210000 717000 810000 A Critical Assessment of the Effects of Pulsed,Irradiation on

Materials. Ghoniem, N.M.; Kulcinski, G.L. UWFDM-311 A V A I L A B I L I T Y - F U S I O N E N G I N E E R I N G PRO-

GRAM, N U C L E A R E N G I N E E R I N G DEPT., UNIVERSITY OF WISCONSIN, MADISON, WI 53706

U - W I ^

9310 Date August 1979. 111210 32A000 521130 522130 717000 810000^ The Reversed-Field Pinch Reactor (RFPR) Concept. Hagenson, R.L.; Krakowski, R.A.; Cort, G.E. L A - 7 9 7 3 - M S " A V A I L A B I L I T Y - N T I S LOASL

, 9325 -o Date May 1979 111210 32A000 510000 521130 717000 795180 Neutron Moderation in ICF Pellets and Effects on Damage

.and Radioactive Inventory. -Beranek, F.; Conn, R.W. U W F D M - 3 1 0

, 0 Ct

9421 . Date 1977 111210 620000 710000 717000 810000 Neutral Beam System for an Ignition Tokamak. Fasolo, J.; Fuja, R.; Jung, J.; Moenich, J.; Norem, J.; Praeg,

W.; Stevens, H. C O N F - 7 7 1 0 2 9 - I77 " O AVAILABILITY-NTIS , PC A 0 2 / M F A01 A R G O N N

9422. . " .V. Date 1977 111210 620000 710000 717000 810000 Mechanical Design and Analysis for an EPR First

Wall/Blanket/Shield System.

Stevens, H.C.; Misra, B.; Youngdahl, C.K. CONF-771029-194 A V A I L A B I L I T Y - N T I S , PC A 0 2 / M F A01 A R G O N N

9427 Date August 1979 111210 111220 210000 717000 810000 Fusion Technology Development. Coffman, F.E.(Dir.) D O E / E T - O l 16/1 A V A I L A B I L I T Y - U . S . DOE, OFFICE OF FUSION

ENERGY, D IV IS ION OF DEVELOPMENT A N D TECHNOLOGY, WASHINGTON, D.C. 20545

DOE

9438 Date October 1979 111210 329000 521130 717000 793000 794000 795254



Takahashi, A.; Rusch, D. K F K - 2 8 3 2 / I I A V A I L A B I L I T Y - K E R N F O R S C H U N G S Z E N T R U M

KjARLSRUHE ( G E R M A N Y , F.R.) G E R M A N

9441 Date September 1979 1127 i0 122100 610000 717000 J93000 810000 G A M M O N Activation Library.

N Battat, M.E.; LaBauve, R.J.; Muir, D.W. L A - 8 0 4 0 - M S A V A I L A B I L I T Y - D E P . , NTIS, PC A03 /MF A01 LOASL

9443 Date 1977 111220 210000 717000 810000 Jet Target Intense Neutron Source. Meier, K.L. L A - U R - 7 7 - 2 3 9 8 ; CONF-771029-38 A V A I L A B I L I T Y - N T I S PC A 0 2 / M F A01 LOASL

9483 Date 1979 010000 111210 717000 717100 810000 Mirror Fusion Reactor Design. Neef, W.S.,Jr.; Carlson, G.A. CONF-790125, PT.A, PP.17-28; J. NUCLEAR


6 ING COMPANY - AMSTERDAM L A L L

9485 Date 1979 010000 111210,210000 717000 810000 The Material Implications of Design and System Studies for

Inertial Confinement Fusion Systems. Maniscalco, J.A.; Berwald, D.H.; Meier, W.R. CONF-790125, PT.A, PP.37-46; J. NUCLEAR


ING COMPANY - AMSTERDAM L A L L „

9486 Date 1979 ''010000 M 1210 111220 210000 717000 810000 Irradiation Sources for Fusion Materials Development. Holmes, J.J.; Straalsund, J.L. CONF-790125, PT.A, PP.447-451; J. NUCLEAR




Neutron Energy Effects. Goland, A.N. CONF-790125, PT.A, PP.453-461; J. NUCLEAR


ING COMPANY - AMSTERDAM BROOKH

9482 Date 1979 010000 111210 210000 717000 Tokamak Reactors and Structural Materials. Conn, R.W. CONF-79Q125, PT.A, PP.9-16; J. NUCLEAR

MATER:, 85 A N D 86, A V A I L A B I L I T Y - N O R T H - H O L L A N D PUBLISH-

ING C O M P A N Y - A M S T E R D A M U - W I

9488. Date 1979 010000 111220 210000 410000 717000 The Fusion Materials Irradiation Test Facility at Hanford. Pottmeyer, E.W.,Jr. CONF-790125, PT.A, PP.463-465; J. NUCLEAR

MATER., 85 A N D 86, AV A I L A B I L IT Y - N O R T H - H O L L A N D PUBLISH-


287'

9489 Date 1979 111220 210000 717000 Measurements and Calculations of f^Ieutron Spectra from 35

MeV Deuterons on Thick Lithium for the F M I T Facili-' ty-


CONF-790125, PT.A, PP.467-471; J. N U C L E A R MATER., 85 A N D 86,

A V A I L A B I L I T Y - N O R T H - H O L L A N D PUBLISH-ING C O M P A N Y - A M S T E R D A M

HANFOR


Be(d,n) Sources, E /sub d/ = 1 4 - - 4 0 MeV. Greenwood, L.R.; Heinrich, R.R. CONF-790125, PT.A, PP.473-477; J. N U C L E A R


I N G C O M P A N Y - A M S T E R D A M A R G O N N

9491 Date 1979 111220 122100 121100 210000 717000 810000 Helium Accumulation Fluence Dosimetry for Fusion Reac-

tor Materials Irradiations. Kneff, D.W.; Farrar, H.,IV CONF-790125, PT.A, PP.479-483; J. N U C L E A R


I N G COMPANY - A M S T E R D A M ROI

9492 Date 1979 111110 210000 717000 870022 870023 870041 New Approach to Simulation of Helium and Simultaneous

Damage Production in Fusion Reactors - In Reactor Tr i t ium Trick.

Andresen, H.; Harling, O.K. CONF-790125, PT.A, PP.485-489; J. N U C L E A R

MATER., 85 A N D 86, A V A I L A B I L I T Y - N O R T H - H O L L A N D PUBLISH- ,

I N G C O M P A N Y - A M S T E R D A M U - M A


Their Implications. Schilfgens, J.O.; Simons, R.L.; Mann, F.M.; Carter, L.L. CONF-790125, PT.A, PP.491-495; J. N U C L E A R

MATER., 85 A N D 86,

A V A I L A B I L I T Y - N O R T H - H O L L A N D ING C O M P A N Y - A M S T E R D A M

HANFOR

PUBLISH-

9494 Date 1979 111210 210000 717000 870013 Fusion-Fission Neutron Damage Ratio for Alumina. Evans, B.D.; Stapelbroek, M . CONF-790125, PT.A, PP.497-502; J. NUCLEAR


ING C O M P A N Y - A M S T E R D A M N A V Y

9495 Date 1979 111210 111220 210000 717000 870029 870079 The Nature of High Energy Neutron Damage in Copper and

Gold. Narayan, J.; Ohr, S.M. CONF-790125, PT.A, PP.515-519; J. N U C L E A R

MATER. , 85 A N D 86, A V A I L A B I L I T Y - N O R T H - H O L L A N D PUBLISFf-

ING C O M P A N Y - AMSTERDAM O A R N L

9497 Date 1979 111210 210000 717000 810C00 Predicting the Effects of Radiation upon the Constitution of

Fusion Reactor Materials. Gittus, J.H.; Miodownik, A.P. CONF-790125, PT.A, PP.621-625; J. NUCLEAR


ING C O M P A N Y - A M S T E R D A M E N G L A N

9542 Date September 1979 111210 32A000 717000 521130 522130 810000 First Wall and Cavity Design Studies for a Light Ion Beam

Driven Fusion Reactor. Moses, G.A.; Abdel-Khalik, S.I.; Drake, D.; Engelstad,

R.L.; Kulcinski, G.L.; Lewis, R.; Lovell, E.; McCarville, T.; Peranich, L.; Peterson, R.R.; Ragheb, M.M.H. ; Spencer, R.

U W F D M - 3 2 0 A V A I L A B I L I T Y - F U S I O N E N G I N E E R I N G PRO-

GRAM, DEPARTMENT OF , N U C L E A R ENGINEERING, UN IV . OF WISCONSIN, M A D I -SON, W I 53706

U - W I

288'

9543 Date October 1979 111210 717000 810000 First Wall Protection in ICF Reactors by Inert Cavity Gases. Moses, G.A.; Peterson, R.R. U W F D M - 3 2 3 '' A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-

G R A M , DEPARTMENT OF NUCLEAR ENGINEERING, UNIV . OF WISCONSIN, MADI -SON, W I 53706

U - W I

9637 Date March 1980 210000 717000 795180 Neutron Moderation in Inertial Confinement Fusion Pellets

and Effects on Damage and Radioactive Inventory. Beranek, F.; Conn, R.W. NUCL . TECHNOLOGY, 47(3), 406-411 U - W I


Fusion Reactors. Verschuur, K.A. E C N - 6 4 A V A I L A B I L I T Y - N E T H E R L A N D S ENERGY

RESEARCH F O U N D A T I O N ECN, P.O. BOX 1, 1755 ZG PETTEN (NH) , T H E N E T H E R L A N D S

NETHER j.

9765 Date December 1978 111210 32A000 795254 793000 521130 522130 717000

810000 870003 Thermal-Hydraul ic and Neutronic Considerations for

Designing a Li thium-Cooled Tokamak Blanket. Mikic, B.; Todreas, N . COO-2431 - 2 A V A I L A B I L I T Y - D E P . , NTIS, PC A 0 6 / M F A01 U - M A


Program of the United States of America. (Introductory Paper No. 1)

Head, C.R. I A E A - T E C D O C - 2 2 3 , PP.1-7 A V A I L A B I L I T Y - M F O N L Y - IN IS M I C R O F I C H E

CLEARINGHOUSE, IAEA, W A G R A M E R -STRASSE 5, P.O. BOX 100, A -1400 V I E N N A , A U S T R I A

DOE

9781 Date December 1979 010000 111210 122100 717000 810000 Nuclear Data Requirements for Fusion Reactor Design -

Neutronics Design, Blanket Neutronics and Tr i t ium Breeding. (Review Paper No .A l )

Constantine, G. I A E A - T E C D O C - 2 2 3 , PP.11-29 A V A I L A B I L I T Y - M F ' O N L Y - IN IS M ICROFICHE

CLEARINGHOUSE, IAEA, W A G R A M E R -STRASSE 5, P.O. BOX 100, A-1400 V I E N N A , A U S T R I A

E N G L A N

9782 Date December 1979 010000 111210 210000 717000 810000 Review of Nuclear Heating in Fusion Reactors. (Review

Paper No.A2) Seki, Y. I A E A - T E C D O C - 2 2 3 , PP.31-45 A V A I L A B I L I T Y - M F O N L Y - IN IS M ICROFICHE

CLEARINGHOUSE, IAEA, W A G R A M E R -STRASSE 5, P.O. BOX 100, A-1400 V I E N N A , AUSTRIA

JAPAN

9783 Date December 1979 010000 111210 717000 810000 Nuclear Data Requirements for Transmutation and Activa-

tion of Reactor Wall and Structural Materials. (Review Paper No.A3)

Jarvis, O.N. I A E A - T E C D O C - 2 2 3 , PP.47 - 74 '' A V A I L A B I L I T Y - M F O N L Y - IN IS M ICROFICHE

CLEARINGHOUSE, IAEA, W A G R A M E R -STRASSE 5, P.O. BOX 100, A -1400 V I E N N A , AUSTRIA

E N G L A N



Qaim, S.M. I A E A - T E C D O C - 2 2 3 , PP.75-89 A V A I L A B I L I T Y - M F O N L Y - IN IS MICROFICHE

CLEARINGHOUSE, IAEA, WAGRAMER-STRASSE 5, P.O. BOX 100, A -1400 V I E N N A , AUSTRIA

G E R M A N

9785. Date December 1979 010000 111210 122100 122200 717000 810000 Nuclear Data Requirements for Fusion Reactor Shielding.

(Review Paper No.A5)

289'

Abdou, M.A. I A E A - T E C D O C - 2 2 3 , PP.91-110 A V A I L A B I L I T Y - M F O N L Y - IN IS M ICROFICHE

CLEARINGHOUSE, IAEA, WAGRAMER-STRASSE 5, P.O. BOX 100, A -1400 V I E N N A , AUSTRIA

U - G A it

978 7 Date December 1979 010000 111210 312000 32A000 717000 810000 Cross-Section Sensitivity and Uncertainty Analysis for

Fusion Reactors - A Review. (Review Paper No.Bl ) Dudziak, D.J. I A E A - T E C D O C - 2 2 3 , PP.121-138 A V A I L A B I L I T Y - M F O N L Y - IN IS M ICROFICHE


LOASL "<>/

(f 978 8 \ . . W . Date December 1979

010000 111210 122100 123000'/17000 810000 Theoretical Approach to Nuclear Data Required for Fusion

Reactor Calculations. (Review Paper No.B2) Seeliger, D. I A E A - T E C D O C - 2 2 3 , PP.139-152 A V A I L A B I L I T Y - M F O N L Y - IN IS MICROFICHE

CLEARINGHOUSE, ; IAEA, WAGRAMER-STRASSE 5, P.O. BOX 100, A-1400 V I E N N A , AUSTRIA }?

G E R M A N

BELGIU

9791 Date December 1979 010000 111210 122100 717000 810000 Status of 14-MeV Neutron Cross Section Data. (Review

Paper N0.B6) Csikai, J. I A E A - T E C D O C - 2 2 3 , PP.199-222 \) A V A I L A B I L I T Y - M F O N L Y - IN IS M ICROFICHE

CLEARINGHOUSE, IAEA, W A G R A M E R -STRASSE 5, P.O. BOX 100, A-1400 V I E N N A , AUSTRIA

H U N G A R

9821 ? Date May 1980 32B000 717000 Application of Generalized Variational Principles to Con-

trolled Thermonuclear Reactor Neutronics Analysis. (Tech. Note)

Cheng, E.T. NUCL. SCI, ENG., 774(2), 147-153 GEAC .j

v-9825 ;". Date March 1980

112720 210000 717000 870007 Gamma Irradiation of Nitrate-Based Salts. Breon, S.R.; Chellew, N.R.; Clemmer, R.G.; Hoh, J.C. A N L / F P P / T M - 1 2 9

/ A V A I L A B I L I T Y - N T I S , PC A 0 3 / M F A01 - A R G O N N


tor Calculations. (Review Paper No.B3) Bhat, M.R. I A E A - T E C D O C - 2 2 3 , PP.153-183 A V A I L A B I L I T Y - M F O N L Y - IN IS MICROFICHE


BROOKH

9790 Date December 1979 010000 122100 717000 810000 Neutron Reaction Data in the MeV Range. (Review Paper

No.B4) Liskien, H. I A E A - T E C D O C - 2 2 3 , PP.185-197 A V A I L A B I L I T Y - M F O N L Y - IN IS MICROFICHE


9826 Date March 1980 111210 32AOOO 521130 522130 795254 717000 844000 Evaluation of Organic Moderator/Coolants for Fusion

Breeder Blankets. Romero, J.B. A N L / F P P / T M - 1 3 0 A V A I L A B I L I T Y - N T I S , PC A 0 3 / M F A01 A R G O N N

9840 Date March 1980 111210 312000 32A000 521130 717000 795254 795204

810000 Sensitivity Analysis of Neutronics Calculations in the Pre-

liminary Design of JAERI Experimental Fusion Reactor. (Revised)

Yamauchi, M.; Scki, Y.; Iida, H. J A E R I - M - 8 7 3 9 A V A I L A B I L I T Y - D I V I S I O N OF T E C H N I C A L

INFORMATION, JAPAN ATOMIC ENERGY RESEARCH INSTITUTE, T O K A I - M U R A , N A K A - G U N , I B A R A K I - K E N , JAPAN

JAPAN

290'

9931 Date Apr i l 1980 111210 717000 ETF Mission Statement Document. ETF Design Center Team O R N L / T M - 6 7 3 3 A V A I L A B I L I T Y - N T I S , PC A 0 8 / M F A01 O A R N L "

9965 Date June 1980 111210 210000 717000 870022 Assessment of Titanium Alloys for Fusion Reactor

F i rs t -Wal l and Blanket Applications (Research Project 1045-3) Final Report.

Jones, R.H.; Leonard, B.R.,Jr.; Johnson, A.B.,Jr. EPRI -AP-1433 A V A I L A B I L I T Y - R E S E A R C H REPORTS CENTER,

BOX 50490, PALO ALTO, CA 94303 B A N L


Problems. Goldstein, M.; Greenspan, E. O R N L / R S I C - 4 4 , PP.169-187 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 O A R N L y

10132 Date 1980 111210 717000 Proceedings of Brookhaven National Laboratory's

Fusion/Synfuel Workshop, Held on August 27-29, 1979.

Fillo, J. A.; et al. „ BNL-51,188 A V A I L A B I L I T Y - N T I S BROOKH

U - N J

° 10155 Date August 1980 111210 717000 Neutron Spectra from Beam-Heated Fusion Plasmas. Scheffel, J.; et al. T R I T A - P F U - 8 0 - 0 9 A V A I L A B I L I T Y - R O Y A L INST ITUTE OF TECH-

NOLOGY, STOCKHOLM, SWEDEN, PLASMA PHYSICS A N D FUSION RESEARCH

SWEDEN

10156 Date January 1980 111210 717000 The National Mirror Fusion Program Plan. Borchers, R.R.; et al. UCAR-10 ,042-80 A V A I L A B I L I T Y - L A W R E N C E L IVERMORE LAB.,

. L IVERMORE, CA L A L L

Fission-Fusion Hybrid Systems


6231 Date September 1977 111210 717100 810000 870092 870090 A U - 2 3 3 Fusion-Fission Power System Without Repro-

cessing. Schultz, K.R.; Brogli, R.H.; Hopkins, G.R.; Jonzen, M.;

Shirley, G.W. GA-A14635 A V A I L A B I L I T Y - N T I S $6.00 GEAC

10146. . . Date August 1980 111210 122310 32A100 521130 717000 810000 SENSIT: A Cross-Section and Design Sensitivity and


10154 Date September 1980 111210 717000 Neutron Flux Measurements Around PLT. Zank, G.; et al. PPPL-1696 A V A I L A B I L I T Y - P R I N C E T O N UNIVERSITY , NEW

JERSEY, P L A S M A PHYSICS LABORATORY

6704 Date February 1. 1977 010000 717100 Fusion-Fission Hybrid Reactors: A Capsule Introduction. Holdren, J.P. UCID-17397 A V A I L A B I L I T Y - N T I S $3.50 L A L L

6773 Date Apr i l 1978 010000 111210 717100 810000 Notes on Fusion Hybrid Reactors. Conn, R.W.; Moses, G.A.; Abdel-Khal ik, S.I. U W F D M - 2 4 0 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,

N U C L E A R E N G I N E E R I N G DEPT., UNIVERSITY OF WISCONSIN, M A D I S O N , WISCONSIN 53706

291 a

U - W I

6865 Date January 23, 1978 717100 Nuclear Design of Fast Hybrid Blankets. Lee, J.D. UCRL-80651; CONF-771155-2 A V A I L A B I L I T Y - D E P . , NTIS L A L L

7024 Date September 1976 111110 111210 717100 810000 Some Systems Economic Considerations of Pure Fusion

Breeders of Fissile Nuclear Fuel. Bussard, R.W. CONF-760935-P2, PP. 741-755 A V A I L A B I L I T Y - N T I S ENGR O

7027 Date September 1976 VJ

111110 111210 32AOOO 521130 717100 810000 793000 795254

Fusion-Fission Neutronics Calculations for the Laser Sole-noid;

Woodruff, G.L.; Quimby, D.C. CONF-760935-P2, PP. 787-798 " c

A V A I L A B I L I T Y - N T i S H

M A S N

7033 Date September 1976 111210 32AOOO 521230 422130 717000 717100 870003



/f Perry, R.T.; McKinnon, M.A.; Teofilo, V.L.; Aase, D:T. B N W L - S A - 6 4 2 0 ; CONF-771029-221 '' A V A I L A B I L I T Y - D E P . , NT IS J

B A N W

8231 Date October 1978 111210 329000 521130 717100 810000 795203 Monte Carlo Statistical "Weighting Methods for Exter-

nal-Source-Driven Mult iplying Systems. Ragheb, M.M.H. ; Maynard, C.W. U W F D M - 2 6 5 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,


U - W I

8467 Date November 1978 < 111110 111210 329000 717100 795203 810000 Three-Dimensional Neutronics Analysis of the Solase-H

Laser Fusion Fissi le-Enrichment-Fuel-Factory. Ragheb, M.M.H. ; Youssef, M.Z.; Abdel-Khal ik , S.I.;

Maynard, C.W. U W F D M - 2 6 6 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,

N U C L E A R ENGINEERING DEPT., U N I V E R S I T Y OF WISCONSIN, MADISON, WISCONSIN 53706

u - w i

8471 Date November 1978 010000 111110 111210 717100 Laser Fusion Hybrids - Technical, Economic and Prolifera-

tion Considerations. , " Moses, G.A.; Conn, R.W.; Abdel-Khal ik , S.I. U W F D M - 2 7 2 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,


U - W I

7035 Date September 1976 111110 111210 521130 522130 717100 32AOOO 810000

793000 795254 Natura l -Uranium L ight -Water Breeding Hybrid Reac-

tors. Greenspan, E.; Schneider, A.; Filai, D.; Levine, P. CONF-760935-P3, PP. 1061-1073

<? A V A I L A B I L I T Y - , ^ T I S ISRAEL " !

8190. . Date October 1977 111110 111210 32A000 521130 717100 810000 795254 Neutronics and Thermal Hydraulics of a Tokamak Hybrid

Blanket.


Nuclear Data. Kotov, V.V.; Maynard, Ch.W.; Markovskii, D.V.; Shatalov,

G.E. L A - T R - 7 8 - 6 5 ; IAE-2817 ( I N RUSSIAN) A V A I L A B I L I T Y - L O S A L A M O S SCIENTIFIC LAB. RUSSIA

8548 Date February 1979 717100 Neutron-Induced Fission in a DT-Plutonium Plasma.

Part I: Fission Fragment Slowing Down.

/ 292

Perkins, S.T> NUCL . SCL ENG., 69(2), 137-146 " L A L L

8549 Date February 1979 717100 " Neutron-Induced Fission in a DT-Plutonium Plasma.

Part I I : Enhancement of Neutron Production and Fusion Rate.

Perkins, S.T. NUCL. SCI. ENG., 69(2), 147-155 L A L L

8767 Date January 1979 010000 713000 717100 717500 Status and Prospccts of Advanced Fissile Fuel Breeders. Kostoff, R.N. V CONF-790103 A V A I L A B I L I T Y - N T I S $7.25 DOE

8790 Date Apri l 1979 010000 111210 717100 810000 An Optimization of the Fission-Fusion Hybrid Concept. Saltmarsh, M.J.; Grimes, W.R.; Santoro, R.T. O R N L / P P A - 7 9 / 3 A V A I L A B I L I T Y ^ O A K RIDGE N A T I O N A L LABO-

RATORY, OAK RIDGE, TENNESSEE,,. O A R N L

8807 Date March 1979 111210 32A000 521130 522130 717100 793000 794000






tant Fuel Assembly from the Fusion - Fission Fuel Factory, SQLASE-H .

Youssef, M.Z'.; Conn, R.W.; Moses, G.A. U W F D M - 2 6 3 A V A I L A B I L I T Y - N U C L E A R ENGINEERING


U - W I

8860 Date September 1978 111210 551110 717100 870092 810000 Neutronic Studies of a 233-U Fusion Breeder. Hansen, L.F.; Maniscalco, J.A. CONF-780921, PP.772-777 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL,


8861.. . Date September 1978 010000 122310 521230 717100 810000 Neutron Data for the Hybrid Reactor Calculation. Markovskii, D.V.; Shatalov, G.E. CONF-780921, PP.783-791 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL,



870092 0 Reproduction of the Weale Experiment Results with Modi-

fied E N D F / B - I V U -238 Data. Segev, M.; Krumbein, A. CONF-780921, PP.1028-1032

' A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL , 75775 PARIS CEDEX 16, FRANCE

.. ISRAEL

8908 Date May 26, 1978 111210 329000 717000 717100 810000

^ Nuclear Design of the L L L - G A U/sub 3/Si Blanket. Lee, J.D. ^ UCRL-80588; CONF-780508-27 A V A I L A B I L I T Y - D E P . , NTIS L A L L >:

8946 Date May 1978 111210 32A000 521130 522130 717100 793000 795254


tion Tokamak Hybrid Reactor. Chapin, D.L.; Chi, J.W.H.; Kelly, J.L. CONF-780508,VOL.I, PP.230-238 A V A I L A B I L I T Y - D E P . , NTIS WEE


Electron - Beam - Fusion M icroexplosi ves. Ragheb, M.M.H.; Moses, G.; Maynard, C.W. U W F D M - 2 9 5

293'

A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-GRAM, NUCLEAR ENGINEERING DEPT., UNIVERSITY OF WISCONSIN, M A D I S O N W I 53706

U - W I

9068 Date August 1979 " 717100 % Characteristics of a Beam-Driven Deuterium-Fueled

Fusion-Fission Reactor System. Schoepf, K.F.; Harms, A.A. NUCL. SCL ENG., 71(2), 170-181 C A N A D A

9127 Date May 1979 111210 329000 717100 795203 810000 S O L A S E - H - A Laser Fusion Hybrid Study. Conn, R.W.; Abdel-Khalik,-S.I.; Moses, G.A.; Cooper,

G.W.; Howard, J.E.; Kulcinski, G.L.; Larsen, E.; May-nard, C.W,; Ragheb, M.M.H.; Sviatoslavsky, I.N.; Vogelsang, W.F.; Wolfer, W.G.; Ortman, M.; Smatlak, D.L.; Watson, R.; Youssef, M.Z.


GRAM, NUCLEAR ENGINEERING DEPT.,' UNIVERSITY OF WISCONSIN, MADISON WI 53706 u £/

U - W I

9163 Date May 1979 111210 717100 . c. Design Study of a Fusion-Driven Tokamak Hybrid Reac-

tor for Fissile Fuel Production. Vol.1. (Research Project 4 7 3 - 1 - 3 ) Final Report.

Rose, R.P. EPRI -ER-1083, VOL.1 A V A I L A B I L I T Y - R E S E A R C H REPORTS CENTER,

BOX 10090, PALO ALTO, CA 94303 EPRI

9164 Date May 1979 111210 717100 Design Study of a Fusion-Driven Tokamak Hybrid Reac-

tor for Fissile Fuel Production. Vol.2. (Research Project 4 7 3 - 1 - 3 ) Final Report.

Rose, R.P. EPRI -ER-1083, VOL.2 A V A I L A B I L I T Y - R E S E A R C H REPORTS CENTER,

BOX 10090, PALO ALTO, CA 94303 EPRI

9191 Date July 1379 M11210 32AOOO 329000 793000 794000 717100 810000 Workshop Summaries f9r the Third US/USSR Symposium

on Fusion-Fission^Reactors. Jassby, D.L. PPPL-1550 A V A I L A B I L I T Y - N T I S U - N J

i j 9324 Date June 1979

010000 111210 717100 A Survey of Fusion-Fission System Designs and Nuclear

\ ' ; Analyses. Youssef, M.Z.; et al. U W F D M - 3 0 8 A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-

GRAM, NUCLEAR ENGINEERING DEPT., UNIVERSITY OF WISCONSIN, M A D I S O N W I 53706

U - W I

9388 Date October 1979 010000 111210 711100 717100 0

Hybrids for Direct Enrichment and Self-Protected Fissile Fuel Protection.

Conn, R.W.; Kantrowitz, F.; Vogelsang, W.F. U W F D M - 3 1 6 A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-

GRAM, NUCLEAR ENGINEERING DEPT., UNIVERSITY OF WISCONSIN, MADISON, W I 53706

U - W I

9389 Date October 1979 010000 111210 717100 810000 869999 A Brief Summary of Different Trit ium Sources for a Tri t i -

umless Hybrid Reactor. Mos°.s, G.A. U W F D M - 3 1 7 A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-

GRAM, NUCLEAR ENGINEERING DEPT., UNIVERSITY OF WISCONSIN^ MADISON, WI 53706

U - W I

9483 • Date 1979 010000 111210 717000 717100 810000 Mirror Fusion Reactor Design.

INeef, W.S.,Jr.; Carlson, G.A. CONF-790125, PT.A, PP.17-28; J. NUCLEAR


ING COMPANY - AMSTERDAM L A L L

294'

9484 Date 1979 010000 111210 717100 810000 Materials Implications of Fusion-Fission Reactor Designs.

^Schultz, K.R. V

CONF-. 7.90125, PT.A, PP.29-36; J. NUCLEAR , 85 A N D 86,

A V / , {•• , \ T Y - N O R T H - H O L L A N D PUBLISH-j tv lPANY - A M S T E R D A M

GEAC

9736 Date M i d - A p r i l 1980 717100 Reaction Rate Calculations in Uranium and Thorium Blan-

kets' Surrounding a Central Deuterium-Tri t ium Neutron Source.

Krumbein, A.D.; Lemanska, M.; Segev, M.; Wagschal, J.J.; Yaari, A.

NUCL. TECHNOLOGY, 48(2), 110-116 ISRAEL

9541 Date August 1979 ' 1H210 717100 810000

Implementation Considerations of Coupling Dedicated Fis-sile and Fusile Productions Fusion and Fusion Reactors.

Ragheb, M.M.H. U W F D M - 3 0 9 A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-

GRAM, DEPARTMENT OF NUCLEAR ENGINEERING, UN IV . OF WISCONSIN, MADI -SON, WI 53706

U - W I

9760 Date 1979 111210 329000 711100 717100 795203 t'f Monte Carlo Statistical Weighting Methods for External

Source Driven Multiplying Systems. Ragheb, M.M.H. ; Maynard, C.W. " • CONF-790402,VOL. lVPP.7-21 - - 7 - 3 5 A V A I L A B I L I T Y - H C - - ANS V I R G I N I A SECTION,


U - W I

9544 Date June 1979 111210 32AOOO 521130 717100 793000 795254 810000


Blankets With and Without Tr i t ium Breeding. Henderson, D.L.; Moses, G.A. U W F D M - 3 3 4 A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-

GRAM, DEPARTMENT OF NUCLEAR ENGINEERING, UNIV . OF WISCONSIN, MADI -SON, W I 53706 '

U - W I

<••9786 Date December 1979 010000 111210 717100 810000 122100 Neutron Data for Hybrid'-Reactor Calculations. (Review

Paper N0.A6) ',*' a Markovskii, D.V.; Shatalov, G.E. ' I A E A - T E C D O C - 2 2 3 , PP. 111-118 A V A I L A B I L I T Y - M F ONLY - IN IS MICROFICHE


RUSSIA

9546 Date December 1979 010000 111210 717100 810000 Summary of the Fusion - Fission Hybrid Fuel Cycle Analy-

sis (Tritiumless Hybrids?). Moses, G.A. (Comp.) U W F D M - 3 3 7 A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-

GRAM, DEPARTMENT OF NUCLEAR ENGINEERING, UNIV . OF WISCONSIN, MADI -SON, W I 53706

U - W I


tor Calculations. (Review Paper No.B3) Bhat, M.R. IAEA-TECDOC-223 , PP.153-183 A V A I L A B I L I T Y - M F O N L Y - IN IS MICROFICHE

CLEARINGHOUSE, IAEA, WAGRAMER-STRASSE 5, P.O. BOX 100, A-1400 V I E N N A , AUSTRIA ,10

BROOK.H

9636 Date March 1980 717100 Tri t ium and Fissile Fuel Exchange Between Hybrids, Fission

Power Reactors, and Trit ium Production Reactors. Youssef, M.Z.; Conn, R.W.; Vogelsang, W.F. NUCL. TECHNOLOGY, 47(3), 397-405 U - W I

9820 Date May 1980 111110 111210 717100 A Separation Method for the Transport Equation and Sensi-

tivity Theory for Fusion-Fission Hybrid Analysis. Youssef, M.Z.; Conn, R.W. NUCL. SCI. E N G , 74(2), 130-139 U - W I

295'

9866 Date September 1979 111210 717100 810000 Minerals Resource Implications of a Tokamak Fusion Reac-

tor Economy. Cameron, E.; Conn, R.W.; Kulcinski, G.L.; Sviatoslavsky, I. U W F D M - 3 1 3 A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-

GRAM, N U C L E A R ENGINEERING DEPT., U N I V . OF WISCONSIN, MADISON, W I 53706

U - W I 1 *

9937 Date March 1980 111210 717100 810000 Nuclear Development Needs-1 for Fusion-Fission Hybrid

Reactors. Jassby, D.L. PPPL-1647 A V A I L X B I L I T Y - N T I S $4.00 U - N J .

Accelerator Breeder n

9868 Date December 1979 111210 717100 The Fusion Fission Hybr id- -Roles in the Energy Econo-

CATEGORY NUMBER 717S00

my. Perry, R.T.; Leonard, B.R.,Jr.; Teofilo, V.L. U W F D M - 3 5 4 A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-

GRAM, N U C L E A R ENGINEERING DEPT., U N I V . OF WISCONSIN, MADISON, WI 53706

U - W I

J) y/ 9869 •. . . Date September 1979

1 112-30 32A000 521130 522130 717100 793000 795254 Blanket Design Study for a Commercial Tokamak Hybrid




WEE

" ^ = ^ 9 8 9 7 Date January 1980 111210 32A000 521130 717100 793000 795254 810000 Evaluation of DD and DT Fusion Fuel Cycles for Different

Fusion-Fission Energy Systems. Gohar, Y. A N L / F P P / T M - 1 3 2 A V A I L A B I L I T Y - N T I S , PC A03 /MF A01 A R G O N N

9935 Date January 1980 010000 717100 Fusion-Fission Energy Systems Evaluation. Teofilo, V.L.; Aase, D.T.; Bickford, W.E.; Leonard, B.R.,Jr.

McCormick, N.J.; McGrath, R.T.; Morrison, J.E. Perry; R.T.; Ribe, F.L.; Rockwood, A.D.; Schulte, S.C, Willingham, C.E.; Woodruff, G.L.

PNL-3116 A V A I L A B I L I T Y - N T I S P A N L

6599 Date 1977 010000 111220 717500 810000 A Brief History of the M T A Project. Van Atta, C.M. ^ , CONF-770107, PP.9-2SK A V A I L A B I L I T Y - N T I S L A L L

6600 Date 1977 010000 111220 717500 810000 Linear, Accelerator Breeder for Energy, Security. Steinberg, M. CQNF-770107, PP.41-68 A V A I L A B I L I T Y / - N T I S BROOKH

6601 Date 1977 010000 111220 717500 810000 High Current Linear Accelerators and Nuclear Power. Tunnicliffe, P.R. CONF-770107, PP.69-84 A V A I L A B I L I T Y - N T I S CANADA'

6602 Date 1977 010000 111220 717500 810000 , Analysis of Accelerator Breeder Concepts with LMFBR,

GCFR, and Molten Salt-Type Blankets. f j Mynatt, F.R. CONF-770107, PP.85-106 A V A I L A B I L I T Y - N T I S O A R N L

7026 Date September 1976 111210 111110 717500 810000 Breeding of Fissile Fuel with Linear Fusion Sources. Oliver, D.; Cooper, B. CONF-760935-P2, PP. 775-786

296'

o AVAILABILITY-NTIS PHIC

8767 Date January 1979 010000 713000 717100 717500 Status and Prospects of Advanced Fissile Fuel Breeders. Kostoff, R.N. CONF-790103 ^ A V A I L A B I L I T Y - N T I S $7.25 ' y DOE D

8862 Date September 1978 010000 717500 Accelerator Breeding of Fissile Material. Taschek, R.F. ^ CONF-780921, PP.792-808' A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL ,

75775 PARIS CEDEX 16, FRANCE LOASL O

8901 Date May 1979 111220 717500 870090 870092 870094 Concept Evaluation of a Nuclear Design for Electronuclear

Fuel Production: Evaluation of ORNL's Proposed T M F - E N F P .

Burns, T.J.; Bartine, D.E.; Renier, J.P. O K N L / T M - 6 8 2 8 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

9641 Date October 1978 010000 717500 Accelerator Breeder Concept. Bartholomew, G.A.; Fraser, J.S.; Garvey, P.M. AECL-6363 <• A V A I L A B I L I T Y - D E P . , NTIS (U.S. SALES ONLY) ,

PC A 0 3 / M F A01 !' C A N A D A

Ship Propulsion


JAPAN

6387 Date Dec. 1977 )i 718000 721100 V , , Mockup Experiment and Analysis for the Primary Shield oL

the Nuclear Ship Mutsu. " \\ Miyasaka, S.; Asaoka, T.; Taji, Y.; Ise, T.; Koyama, K.;

Tsutsui, T.; Takeuchi, M.; Fuse, T.; Miura, T.; Yamaji, Y.; Miyakoshi, J.; Tubosaka, T.; Furuta, K.; Kawakita,

^ T.; Natume, H.; Nishizaki, T.; Okumura, Y. CONF-770401, PP.188-196; ATOMKERNENERGIE,

30(4), 269-274,^ A V A I L A B I L I T Y ' - S C I E N C E PRESS, 8 BROOKSTONE


6464 Date Dec. 1977 111110 421140 551120 718000 731300 721200 795195 Mock -Up Experiment of Radiation Streaming Through

Coolant Pipe Penetration. Tsubosaka, A.; Miyakoshi, J.; Furuta, K.; Kawakita, T.;

Natume, H.; Nishizaki, T.; Okumura, Y.; Miyasaka, S.; Asaoka, T.; Taji, Y.; Ise, T.; Koyama,' K.; Tsutsui, T.; Takeuchi, M.; Fuse, T.; Miura, T.; Yamaji, A.

CONF-770401, PP.849-856 i i 'AVAILABIL ITY, r SCIENCE PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 JAPAN ^

L i g h t - W a t e r Cooled Reactors

CATEGORY N U M B E R 719A00

6293 Date October 1977 111110 020000 329000 719A00 Improvement of Reference Nuclear Data for Commercial

Power Reactor Analysis and Design. Levitt, L.; Magurno, B.; Rose, P. EPRI -NP-556 A V A I L A B I L I T Y - E L E C T R I C POWER RESEARCH

INSTITUTE, 3412 H I L L V I E W AVENUE, PALO ALTO, CAL IFORNIA 94304

EPRI

6386 Date Dec. 1977 718000 721100 Radiation Streaming of N.S. Mutsu and Its Repair Plan. Osanai, M.; Miyakoshi, J.; Tsubosaka, A.; Miyasaka, S. CONF-770401, PP.179-187; ATOMKERNENERGIE,

30(4), 265-268' § >• A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 ' *

6320 Date January 1977 112120 222000 632110 719A00 Development of a Model for the Assessment of Radiation

Fields Around Nuclear Power Plant Components. Lauridsen, K. RISO REPORT N0.353 A V A I L A B I L I T Y - S A L E S DISTRIBUTORS: JUL.

GJELLERUP, 87, SOLVGADE, DK-1307 COPEN-HAGEN K, D E N M A R K

297 <

D E N M A R

6374 Date Dec! 1977 719A00 Shielding Design Features of the Floating Nuclear Plant. Billings, M.P.; Capo, M.A. " CONF-770401, PP.54-63; ATOMKERNENERGIE,


DR., PRINCETON, NJ 08540 OFPS

638 9 Date Dec. 1977 719A00 721100 795209 795203

i j \ Neutrons and Gamma-Ray Streaming in the Annulus w. Between the Reactor Pressure Vessel and the Sacrificial

Shield of the Caorso Nuclear Power Station. Barbucci, P.; Di Pasquantonio, F. CONF-770401, PP.205-213 AVA ILAB IL ITY-SCIENCEPRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 083*40 I T A L Y

639 0 Date Dec. 1977 719A00 721100 Empirical Solution of Radiation Streaming Problems in the

Ai r Gap Around the Pressure Vessel of a PWR. Francis, C.C. ° CONF-770401, PP.214-222 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 TV A

6399 Date Dec. 1977 t? 010000 223000 719AOO Radiation Exposure and Protection Problems in Nuclear

Power Plants U.S. Overview. Verna, B.J. CONF-770401, PP.288-299; ATOMKERNENERGIE ,


DR., PRINCETON, NJ 08540 NUPE

<0 6402. . . ? . . . ' ; . . .o Date Dec. 1977

223000 719A00 o Radiation Exposure in the Operating PWR Plants and Spe-

cific Design Features for Occupational Dose Reduction. Mani, V.; Lingappan, K.G. CONF-770401, PP.317-324 A V A I L A B I L I T Y - S C I E N C E PRESS, 8'BROOKSTONE

DR., PRINCETON, NJ 08540 U N E C I

<•':'-v 6403 Date Dec. 1977

223000 719AOO Experience with Occupational Radiation Exposure inPWRs

Built by Kraftwerk Union. Hecht, G. ( f ^ CONF-770401, PP.325-332; ATOMKERNENERGIE ,


DR., PRINCETON, NJ 08540 G E R M A N ^

6391 Date Dec. 1977 719A00 721100 722100 Shielding Against Neutron Streaming in Pressurized Water

Reactors. Devillers, C.; Payen, J.P. CONF-770401, PP.223-229; ATOMKERNENERGIE,



L Dec. 1977 6393 719A00 210000 Determination of Radiation Damage to StructuraljCompo-

nents Outside the Core of PWRs. Koban, J.; Leitz, G.; Hehn, G.; Issler, L. CONF-770401, PP.23.8-245 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 G E R M A N

o %/f • . »

«UW? 1 • <3f

6404. Date Dec. 1977 223000 719A00 Radiological Experience in Swedish Boiling Water Reactors. Elkert, J. CONF-770401, PP.333-341 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 ^ SWEDEN

'•-a u " 0

6406 ."Date Dec. 1977 223000 719A00 « „<•- ^ " v " -Radiation Safety of Nuclear Power Plants with Large Chan-

nel-Type Reactors. r o " o 1 ' <;

Egorov, Yu.A.; Polushkin, K.K.; Sklyarov, V.p.; Cerkaskov, Yu.M. •' -= . " u

CONF0-770401, PP.353-363 ' „ " ,, u S / 0

A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE DR., PRINCETON, NJ 08540,, -v f *

RUSSIA io ., * t V

298'

6407 Date Dec. 1977 010000 112760/719A00 An Overview of the Activated Corrosion Product Reduction

Program at U.S. Power Reactors. Murphy, T.D. CONF-770401, PP.364-373; ATOMKERNENERGIE ,


DR., PRINCETON, N,J 08540 N U R C

6440 Date Dec. 1977 329000 32A000 532000 719A00 Evaluation of Uncertainties in the Gamma-Ray Heating

Analysis of a PWR. West, J.T.,I I I ')/



6408 •. Date Dec. 1977 l'?2760 719A00 719B00 713000

^Prediction of Primary Circuit Contamination in Power Reactors. •

Beslu, P.; Costa, L.; Frejaville, G.; Pepini P. CONF-770401, PP.374-391; ATOMKERNENERGIE ,



6451. .,.; Date Dec." 1977 532000 719A00 A Three-Dimensional Synthesis Approach to Reactor

Internal Gamma-Ray Heating. " West, J.T.,III; Whitmarsh, C.L. CONF-770401, PP.739-745 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

" DR., PRINCETON, NJ 08540 O A R N L 0

VI.

6409 : Date Dec. 1977 112760"719A00 223000 EPRI Programs in Power Reactor Radiation Control. Shaw, R.A.; Uhl, D.L. CONF-770401, PP.392-400 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 EPRI

?: .'> 6469 . . Date Dec. 1977 112?20 423250 532000 719A00

V

Spatial Distribution of Fission Product Energy. Johnson, W. R..; Bass, R.B.; Litt ig, G.A.; Robinson, F.L.;

o Bracke, T.P. CONF^77040VPP.889-896 . AV5UCABIL1TY-SCIENCE PRESS, 8 BROOKSTONE

DR:, PRINCETON, NJ 08540 « U - V A <

6411., Date Dec. 1977 112760 223000 719A00 Analysis of Dose Rates Near the Circuit of a PWR After

Shutdown. 0

Beslu, P.; Frejaville, G.; Lalet, A.; Devillers, C. CONF-770401, PP.409-415 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

! DR., PRINCETON, NJ 08540 FRANCE

o'' ii 6470. . . v Date Dec. 1977 421200 112770 222000 719A00 r 'O u

In Situ .Measurements with a Mobile Ge(Li) Spectrometer Around a Nuclear Power Plant.

Finck, R.; Liden, K.; Persson, R.B.R. CONF-770401, PP.897-904 A V A I L A B I L I J Y - S C I E N C E PRESS, 8 BROGKSTONE


6414 Date Dec. 1977 223000 719A00 Digital Radiation Monitoring System Employing Distrib-

uted Microprocessors. Warman, E.A.; Ingeneri, S.M.; Newman, B.M.; Sowdon,

T.L. CONF-770401, PP.434-441 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR.. PRINCETON, NJ 08540 STONE

6477 Date September 1974 223000 719A00 ' Compilation and Analysis of Data on Occupational Radia-

tion Exposure Experienced at Operating'Nuclear Power Plants.

Pelletier, C.A.; Simmons, L.; Barbier, M.; Keller, J.H. NESP REPORT

, A V A I L A B I L I T Y - A T O M I C I N D U S T R I A L FORUM, INC., 475 PARK A V E N U E SOUTH, NEW YORK, NEW YORK 10016 $7.00 "

SCA »!

o

299

6543 Date October 1977 111110 325000*511110 719A00 870092 Analysis of Homogeneous U233 and U235 Critical Assem-

blies with E N D F / B - I V Data (AWBA Development Program). v<| ((

Ullo, J.J.; Hardy, J.,Jr. WAPD - T M -1299 A V A I L A B I L I T Y - W E S T I N G H O U S E ELECTRIC

"CORPORATION, BETTIS A T O M I C POWER DIV I -S ION

BETTIS S>

6746 Date September 1977,„, l l l l 10..U2110 112400 112500 32A000 511110 551110

"512210 552210 719A00 793000 795254 795276 PWR and BWR Radiation Environments for Radiation

Damage Studies. ri

Gritzner, M.L. ; Simmons,,;G.L.; Albert, T.E.; Straker, E.A. E P R I - N P - 1 5 2 , F I N A L REPORT A V A I L A B I L I T Y - S C I E N C E APPLICATIONS INC.,

L A JOLLA, CALIF. EPRI v-^ '

6544 .Ibate December 1977 ' 111110 020000 329000 719AOO 820000 870092 Monte Carlo Analyses to T R X Sligh't ly%nriched-H /sub

2/ O Critical Experiments with, E N D F / B - I V and Related Data Sets. ( A W B A Development Program).

Hardy, J.,Jr. W A P D - T M - 1 3 0 7 A V A l L A B I L I T Y - W E S T I N G H O U S E ELECTRIC

CORPORATION, BETTIS A T O M I C POWER DIVI -S ION

BETTIS

0

6609. . . . Date December 1977 111110 210000 311000 32A000 551110 795276 719A00

861000 810000 v-, Calculations of Neutron Flux Levels in the Pressure Vessel

of an LWR. Final Report (Research Project 827-2). Livesay, R.B.; Wells, M.B. E P R I - N P - 6 1 7 A V A I L A B I L I T Y - R A D I A T I O N RESEARCH ASSOCI-

ATES, INC. RARA

6627 Date March 1978 122310 312000 521130 719A00 870092 870013 870001


for the T R X - 2 Thermal Lattice. Tomlinson, E.T.; Lucius, J.L.; Drischler, J.D. ORNL-5336; ENDF-253 A V A I L A B I L I T Y - N T I S S8.00 O A R N L

6695 Date Apri l 1978 111110 122310 311000 312000 719A00 795217 870092

870094 Sensitivity and Uncertainty Analysis for Functionals of

Time-Dependent Nuclide Density Field. Williams, M.L.; Weisbin, C.R. ORNL-5393 ; ENDF-263 A V A I L A B I L I T Y - N T I S $6.00 O A R N L

6810 Date 1978 010000 210000 421130 421140 511120 719A00 861000 Power Reactor Pressure Vessel Benchmarks. Rahn, F.J. IAEA-208 , VOL.I , PP.105-140 A V A I L A B I L I T Y - I N I S M I C R O F I C H E CLEARING-

HOUSE EPRI

o D

6854 Date February 1977 111110 323000 540000 719A00 Neutron Spectrum Calculating Module of the Program

BETTY. '' 0

Gado, J. K F K I - 7 7 - 1 4 A V A I L A B I L I T Y - D E P , NT IS (U.S. SALES O N L Y ) G E R M A N ,,

0 6

p L W R

6858 '. . Date June 1978 112120 112730 532000 719A00 870092 Fission Product Source Terms for the

Loss-of-Coolant Accident: Summary Report. Lorenz, R.A.; Collins, J.L.; Malinauskas, A.P. NUREG/CR-0091 ; O R N L / N U R E G / T M - 2 0 6 A V A I L A B I L I T Y - N T I S O A R N L

6899 Date October 1977 111110 122110 421140 430000 521230 719A00 795112

795233 810000 ^ Neutron Metrology in the L.F.R. Neutron Flux Density

Spectrum in the Inner Graphite Reflector of the L.F.R. Zsolnay, E.M. o E C N - 7 7 - 1 3 4 (RESTRICTED D ISTRIBUT ION) A V A I L A B I L I T Y - ST ICHT ING ENERGIEONDER-

ZOEK C E N T R U M N E D E R L A N D (ECN), VOORTZETTING V A N DE S T I C H T I N G REAC-

<TOR C E N T R U M (RCN) , W E S T E R D U I N W E G 3, PETTEN (NH) , T H E N E T H E R L A N D S

NETHER

<> 300

6903 Date December 1976 112120 329000 532000 719A00 795187 Analysis of Post LOCA Gamma Ray Effects in Representa-

tive Light Water Reactors. Volume 1. Final Report. Steinberg, H.; Lichtenstein, H.; Cohen, M.O. E P R I - N P - 4 2 5 ( V O L . l ) A V A I L A B I L I T Y - N T I S M A A G

7111 Date July 1976 111110 421130 421200 521230 522230 710000 719A00


the Novo-Voronezhskaya AES's Second Unit. Glushchenko, A.I.; Orlov, Yu.V.; Satarin, V.Ye. E R D A - T R - 1 2 5 , PP. 119-126 A V A I L A B I L I T Y - N T I S RUSSIA

6904 Date Apri l 1978 112120 532000 719A00 Spatial Distribution of Fission Product Gamma-Ray


Bass, R.B.; Johnson, W.R. EPRI -NP-672 , V O L U M E 1 A V A I L A B I L I T Y - U N I V E R S I T Y OF V I R G I N I A ,

SCHOOL OF ENGINEERING A N D APPLIED SCI-ENCE, CHARLOTTESVILLE, VA. 22901

U - V A

6978 Date August 1978 112760 719AOO A Calculation Model for Predicting Concentrations of

Radioactive Corrosion Products in the Primary Coolant of Boiling Water Reactors.

Uchida, S.; Kikuchi, M.; Asakura, Y.; Yusa, H.; Ohsumi, K. NUCL. SCL ENG., 67(2), 247-254 JAPAN ~

7091 Date February 1974 112930 220000 222000 713000 719A00 719BOO Projections of Radioactive Wastes to be Generated by the


RATORY O A R N L

7110 Date July 1976 111110 421140 421130 521230 710000 719A00 Investigation of the Absolute Fluxes and Spectra of Fast


Barinov, A.L.; Vikin, V.A.; Glushchenko, A.I.; Yegorov, Yu.A.; Kovalenko, V.V.; Luk'yanov, M.A.; Orlov, Yu.V.; Razumovskiy, M.V.; Tsofin, V.I.

E R D A - T R - 1 2 5 , PP. 106-118 A V A I L A B I L I T Y - NTIS RUSSIA

7112 , Date July 1976 111110 421140 721100 721200 719A00 853800 861000 Passage of Neutrons with Intermediate Energies Through

Shielding with Complex Irregularities. Bolyatko, V.V.; Sakharov, V.M.; Suvorov, A.P.; Kharizo-


8047 Date May 1978 111110 423140 719AOO 721200 Neutron Streaming Measurements at an 850 -MWe Pres-


Ritchie, J.C. H E A L T H PHYS., 34(5), 479-483 NURC

8088 Date Mid-August 1978 112930 222000 719AOO 79521 1 Potential Radiological Consequences of a Multiple Stream

Generator Tube Rupture. Fray, R.R. NUCL. TECHNOLOGY, 40(1), 52-61 PAGE

8120 Date September 1978 111110 112120 325000 719A00 795217 Revised Uranium-Plutonium Cycle PWR and BWR Mod-

els for the ORIGEN Computer Code. Croff, A.G.; Bjerke, M.A.; Morrison, G.W.; Petrie, L.M. O R N L / T M - 6 0 5 1 A V A I L A B I L I T Y - N T I S $7.50 O A R N L

8198 Date September 1978 020000 422110 719A00 870092; 870094 Clean Critical Experiment Benchmarks for Plutonium Recy-

cle in LWRs. 1 Smith, R.I.; Konzek, G.J. EPRI -NP-196 , VOL.2

301'

A V A I L A B I L I T Y - B A T T E L L E PACIFIC NORTH-WEST LABORATORIES, R I C H L A N D , W A S H I N G T O N 99352

B A N W

823 5 Date Apr i l 1975 111110 329000 719A00 870092 Monte Carlo Analysis of Direct Measurements of the Ther-

mal Eta(0.025 eV) for 2 3 3 - U and 235 -U (LWBR Development Program).

Ullo, J.J.; Goldsmith, M. W A P D - T M - 1 2 1 7 A V A I L A B I L I T Y - D E P . , NTIS BETTIS

823 6 Date Apri l 1975 111110 329000 719A00 870092 Monte Carlo Analysis of Thermal Spectrum Averaged Mea-

surements of Eta of 2 3 3 - U and 2 3 5 - U (LWBR Development Program).

Goldsmith, M.; Ullo, J.J. W A P D - T M - 1 2 1 8 A V A I L A B I L I T Y - D E P . , NTIS BETTIS

8237 Date August 1978 111110 112110 329000 719A00 RCPOl - A Monte Carlo Program for Solving Neutron

and Photon Transport Problems in Three-Dimensional Geometry and Detailed Energy Description (LWBR Development Program).

Candelore, N.R.; Gast, R.C.; Ondis, L.A., I I W A P D - T M - 1 2 6 7 A V A I L A B I L I T Y - N T I S a BETTIS

8270 Date August 1978 010000 112120 713000 719A00 870092 870094 Needs and Accuracy Requirements for FPND in the Physics

Design of Power Reactor Cores. Rowlands, J.L. I A E A 213, PP.41-60 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) E N G L A N

8476 Date January 1979 112720 631000 223000 719AOO An Empirical Formula Predicting Shutdown Dose Rate of

the Recirculation Pipes in Boiling Water Reactors. (Tech. Note) .


NUCL. SCL ENG., 69(1), 78-85

JAPAN


Loss-of-Coolant Accidents and Hypot'neticai Core Meltdown Accidents.

Albrecht, H.; Malinauskas, A.P. CONF-781147-1 A V A I L A B I L I T Y - D E P . , NTIS G E R M A N

8585 Date 1977 ,010000 111110 210000 421140 430000 713000 717000



McElroy, W.N.; Bennett, R.A.; Johnson, D.L. ; ' EUR-5667E/F.PT.I , PP.1-26; CONF-750935,PT.I,


T IONS OF THE EUROPEAN C O M M U N I T I E S , BOITE POSTAL 1003 - LUXEMBOURG

WEE


the European Countries. Farinelli, U. EUR-5667E/F,PT.I , PP.27-40; CONF-750935,PT.I,



I T A L Y


siderations in L W R Pressure Vessels. Serpan, C.Z.,Jr. EUR-5667E/F,PT.I , PP.41-51; CONF-750935,PT.I,


TIONS OF T H E EUROPEAN COMMUNIT IES , BOITE POSTAL 1003 - L U X E M B O U R G

NURC C{:

8588 Date 1977 111110 210000 521130 713000 719A00 795254 861000

795276

302'

Prediction of Radiation Damage in Structural Materials Outside the Reactor Core.

Hehn, G.; Stiller, P. EUR-5667E/F,PT. I , PP.52-62; CONF-75()935,PT.I,

PP.52-62 A V A I L A B I L I T Y - O F F I C E FOR OFF IC IAL PUBLICA-


G E R M A N


Research Reactor. Allen, E.J.; Kerr, H.T. EUR-5667E/F,PT. I , PP.414-423;

CONF-750935.PT.I, PP.414-423 A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L PUBLICA-

T IONS OF T H E EUROPEAN C O M M U N I T I E S , BOITF. POSTAL 1003 - L U X E M B O U R G

O A R N L

8632 Date 1977 111110 421140 713000 719A00 870092 Intercomparison of Reactor Dosimetry Cross Sections Mea-

sured in a Thermal Reactor, in a Fast Reactor and with an Enriched Uranium Fission Plate.

Kimura, I.; Kobayashi, K. EUR-5667E/F.PT. I I , PP.142-151;

CONF-750935,PT.I I , PP.142-151 A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L PUBLICA-


JAPAN

8644 Date November 1978 112930 719A00 • Sources of Radioiodine at Pressurized Water Reactors Final

Report (Research Project 274-1). Pelletier, C.A.; Cline, J.E.; Barefoot, E.D.; Hemphill, R.T.;

Voilleque, P.G.; Emel, W.A. E P R I - N P - 9 3 9 A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, INC.,

ROCKVILLE , M A R Y L A N D , NUCLEAR ENVI -R O N M E N T A L SERVICES DIV.

SCA

SCA o

8655 Date February 1979 111110 122310 719A00 810000 Sensitivity of Water Reactor Fuel Cycle Parameters and

Costs to Nuclear Data. Becker, M.; Harris, D.R.; Quan, B.; Ryskamp, J.M. O R N L / R S I C - 4 2 , PP.75-87 A V A I L A B I L I T Y - NTIS U - N Y

8656 Date February 1979 111110 122310 123000 719A00 Nonlinear Model Fitting of Thermal Neutron Data and its


Thompson, J.K. O R N L / R S I C - 4 2 , PP.89-104 A V A I L A B I L I T Y - N T I S B A N L


istic Reactor Operating Histories. Trapp, T.J.; Spinrad, B.I. O R N L / R S I C - 4 2 , PP.105-118 A V A I L A B I L I T Y - N T I S P A N L

8659 Date February 1979 111110 122310 210000 421140 7I9A00 861000 795112

430000 Use of H E D L Codes in the Sensitivity and Uncertainty



O R N L / R S I C - 4 2 , PP.135-143 A V A I L A B I L I T Y - N T I S H A N F O R

8645 Date December 1978 112120 713000 719A00 795309 870092 870094 Radiation Source Terms in LWR and LMFBR Spent Fuel

Final Report. Tech. Services Agreement 78-156. Stamatelatos, M.G. E P R I - N P - 9 4 8 A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, INC.,

LA JOLLA, C A L I F O R N I A

8671 . Date February 1979 111110 122310 719A00 810000 Sensitivity of L W R Fuel Cycle Costs to Uncertainties in

Detailed Thermal Cross Sections. Ryskamp, J.M.; Becker, M.; Harris, D.R. O R N L / R S I C - 4 2 , PP.329-342 A V A I L A B I L I T Y - N T I S U - N Y

303'

8674 Date February 1979 111110 122310 32A000 312000 521130 713000 719A00


Adjustment. Chestnutt, M.M. ; MCracken, A.K. O R N L / R S I C - 4 2 , PP.363-373 A V A I L A B I L I T Y - N T I S E N G L A N

8678 Date March 1979 112120 32AOOO 552110 795217 719A00 795320 861000 Calculated, Two-Dimensional Dose Rates from a PWR

Fuel Assembly. Croff, A.G.; Hermann, O.W.; Alexander, C.W. O R N L / T M - 6 7 5 4 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8715 Date February 1979 111110 122310 312000 719AOO Sensitivity of Nuclear Fuel Cycle Cost to Uncertainties in

Nuclear Data. Becker, M.; Harris, D.R. E P R I - N P - 9 8 5 A V A I L A B I L I T Y - R E N S S E L A E R P O L Y T E C H N I C

INSTITUTE, DEPT. OF N U C L E A R ENGINEER-ING, TROY, NEW YORK 12181

U - N Y

8740 Date August 1978 112120 222000 719A00 887000 Magnox Fuel Inventories: Experiment and Calculation

Using a Point Source Model. Nair, S. R D / B / N - 4 3 4 9 , A V A I L A B I L I T Y - C E N T R A L ELECTRICITY GEN-

E R A T I N G BOARD, HEADQUARTERS SERVICES, REPROGRAPHIC SECTION, COUR-T E N A Y HOUSE, 18 W A R W I C K LANE, L O N D O N ECAP 4EB

E N G L A N

8781 Date December 1978 112930 112710 112760 222000 719A00 Calculation of Releases of Radioactive Materials in Gaseous



NUREG-0016 (REV. l ) A V A I L A B I L I T Y - N T I S N U R C

8791 Date February 1979 010000 111110 223000 719A00 721100 722100 Radiation Streaming in Power Reactors. Lahti, G.P.; Lee, R.R.; Courtney, J.C. (Eds.) O R N L / R S I C - 4 3 ; A N S / S D - 7 9 / 1 6 A V A I L A B I L I T Y - N T I S $9.25 O R A N L

8792 Date February 1979 010000 111110 223000 32A000 521110 522110 610000


LWRs. Rahn, F.; Ti l l , H. ORNL/RSIC-43,PP.1 -21; ANS/SD-79/16,PP.1 - 2 1 A V A I L A B I L I T Y - N T I S EPRI

8793 Date February 1979 111110 32A000 329000 223000 719A00 721100 722100


siderations. Simmons, G.L. ORNL/RSIC-43,PP.22-27;

ANS/SD-79/16,PP.22-27 A V A I L A B I L I T Y - N T I S SCA

8794 Date February 1979 111110 223000 32A000 329000 719A00 721100 722100


niques to PWR Cavity Shield Design. Cavanaugh, G.P. ORNL/RSIC-43,PP.28-42;


8795 Date February 1979 111110 223000 32A000 721100 722100 795198 719A00 Reactor Cavity Radiation Streaming. Cardito, J.M.; Eastman, E.A.B.; Allen, P.R.; Wainio, K.M. ORNL/RSIC-43,PP.43-53;

ANS/SD-79/16,PP.43-53 A V A I L A B I L I T Y - N T I S STONE

8796 Date February 1979 111110 223000 32A000 521130 522130 551110 552210

721100 722100 719AOO 795254 795203 795276 810000 Methodology for the Analysis and Design of a PWR Reactor

Cavity Shield System.

304'

Celnik, J. ORNL/RSIC-43,PP.54-67;


8797 Date February 1979 111110 329000 721100 722100 793000 719A00 610000


Harmonics Expansion of Albedo Data. Albert, T.E.; Simmons, G.L. ORNL/RSIC-43.PP.68-75;


879 8 Date February 1979 111110 223000 329000 721100 721200 722100 620000


ing Solutions. Iotti, R.C.; Yang, T.L. ORNL/RSIC-43 ,PP.76- 109;

ANS/SD-79/16,PP.76-109 A V A I L A B I L I T Y - N T I S EBASCO

879 9 Date February 1979 111110 223000 721200 719A00 Measured Distribution of Neutrons Inside Containment of

a PWR. Butler, H.M.; Ohnesorge, W.F.; Auxier. J.A. ORNL/RSIC-43,PP.110-113;

ANS/SD-79/16,PP. 110-113 A V A I L A B I L I T Y - N T I S O A R N L

8S00 Date February 1979 111110 422140 721200 7I9A00 A Survey of Neutrons Inside the Containment of a Pressur-

ized Water Reactor. Hankins, D.E.; Griff ith, R.V. ORNL/RSIC-43.PP.114-126;

ANS/SD-79/16,PP. 114- 126 A V A I L A B I L I T Y - N T I S L A L L

8801 Date February 1979 111110 32A000 329000 721100 719A00 794000 795203

795276 810000 Calculations of the Neutron Environment Inside a PWR

Containment.

Hopkins, W.C. ORNL/RSIC-43,PP. 127 -136;

A N S / S D - 79 /16,PP. 127 - 136 A V A I L A B I L I T Y - N T I S BECHTE

880 2 Date February 1979 111110 32A000 551110 719AOO 710000 721100 810000 A Low Pressure Drop Reactor Cavity Shield System. Klotz, R.J.; Cavanaugh, G.P.; Kassawara, R.P.;

McLaughlin, D.J.; Pilver, A.B. ORNL/RSIC-43,PP.137-148;


880 3 Date February'l 979 111110 329000 710000 719A00 721100 795207 810000 Radiation Streaming and Reactor Cavity Shield Design at

TV A PWR Plants. Francis, C.C.; Galbreth, T.M.; Zobel, W. O R N L / R S I C - 43,PP. 149 -162;

ANS/SD-79/16,PP.149-162 A V A I L A B I L I T Y - N T I S TVA

8804 Date February 1979 111110 329000 719A00 721100 810000 Radiation Shielding for BWR Shield Wall Penetrations. Gillett, T.C.; Warkentin, J.K. ORNL/RSIC-43,PP.163-177;

ANS/SD-79/16,PP.163- 177 A V A I L A B I L I T Y - N T I S B R A U N

8805 Date February 1979 111110 795144 710000 721100 719A00 810000 Shield Design Against Neutron Streaming in the Vicinity of

a BWR Pressure Vessel. Seifferth, L.; Przibram, E.; Hock, R. ORNL/RSIC-43,PP.178-192;

A N S / S D - 79/16,PP. 178-192 A V A I L A B I L I T Y - N T I S G E R M A N



Hep, J.; Valenta, V.; Veverka, O. ZJE-199

h

305'

AVAILABILITY-SKODA WORKS, NUCLEAR POWER CONSTRUCTION DEPARTMENT, INFORMATION CENTRE, PLZEN - CZECHO-SLOVAKIA

CZECHO

8915 Date July 1978 112760 719A00 Deposition of Iron Oxide on Heated Surfaces in Boiling

Water. Asakura, Y.; Kikuchi, M.; Uchida, S.; Yusa, H. NUCL. SCI. ENG., 67(1), 1 - 7 JAPAN

8927 Date June 1979 223000 719A00 Occupational Radiation Exposure at French Power Plants:

Measurement and Prediction. Beslu, P.; Frejaville; G.; Jeanson, P. NUCL. TECHNOLOGY, 44( 1), 84 - 90 FRANCE

8929 Date June 1979 112720 223000 719A00 Getting at the Source: Reducing Radiation Fields. Shaw, R.A. NUCL. TECHNOLOGY, 44(1), 97-103 EPRI

8962 Date April 1979 111110 111600 210000 521230 719A00 795254 861000


tamination of Neutron Dosimetry Procedures Used for Reactor Pressure Vessel Applications. °

Simmons, G.L. (( EPRI-NP-1056 AVAILABILITY-SCIENCE , APPLICATIONS,


SCA


Reactor Applications. Rose, P.F.; Pearlstein, S.; Ozer, O. EPRI -NP-1098-SY AVAILABILITY-NATIONAL NUCLEAR DATA

CENTER, BROOKHAVEN NATIONAL LABORA-TORY, UPTON, NEW YORK 11973

BROOKH

8971 ' Date January 23, 1979 112720 422200 424000 719A00 810000 Neutron Shielding Requirements for the Loft Densitome-

,. ters. Wheeler, F.J.; McCracken, R.T. LTR-141-97 AVAILABILITY-DEP., NTIS IDNEL „

8973 ' Date April 1979 112710 223000 222000 719A00 Gamma Dose Measurements at Zion and Fort Calhoun Sta-


Kynaston, R.L.; Mclsaac, C.V.; Underwood, D.R. NUREG/CR-0755 AVAILABILITY-NTIS S7.25 IDNEL

9006 Date June 1978 111110 325000 551110 719A00 810000 A Nodal Method for Solving Transient Fewgroup Neutron

Diffusion Equations. Shober, R.A •. ANL-78-51 AVAILABILITY-NTIS $6.00 ARGONN


Reactors (AWBA Development Program). Hardy, J.,Jr.; Ullo, J.J.; Steen, N.M. WAPD-TM-1449 AVAILABILITY-BETTIS ATOMIC POWER LABO-


9130. Date June 1979 112930 222000 719A00 AIRWAY - A FORTRAN Computer Program to Esti-


Rider, J.L. W A P D - T M - 1275 AVAILABILITY-BETTIS ATOMIC POWER LABO-


9190 Date November 1978 010000 020000 111110 719A00 Sources of Neutronics Data Involving Thorium of 233-U

and Light Water Moderation.

306'

<i J :

Davenport, L.C. PNL-2917 A V A I L A B I L I T Y - P A C I F I C NORTHWEST LABORA-

TORY, R I C H L A N D , WASHINGTON PANL

9316 Date October 1979 112120 312000 719A00 Sensitivity Theory Applied to a Transient Ther-

mal-Hydraulics Problem. Weber, C.F.; Oblow, E.M. O R N L / T M - 6 9 0 0 A V A I L A B I L I T Y - N T I S O A R N L

(>*

9371 Date September 1979 111220 424000 719A00 Use of Sealed Tube Neutron Generators for Verification of

LWR Fuel Assemblies. Lee, D.M. L A - 7 9 9 6 - M S A V A I L A B I L I T Y - N T I S LOASL

9434 Date 1979 111110 410000 421140 719A00 I B R - 2 Reactor Physical Star t -Up. The Results of Mea-

suring the I B R - 2 Leakage Neutron Spectrum. Arkhipov, V.A., et al. < J INR-P13-12466 " A V A I L A B I L I T Y - J O I N T INSTITUTE FOR

NUCLEAR RESEARCH, DUBNA RUSSIA

9448 Date August 1979 111110 122310 32A000 521130 793000 794000 719AOO



Jenquin, U.P.; Thompson, J.K.; Trapp, T.J.; Kottwitz, D.A. NUREG/CR-0965; PNL-3071 A V A I L A B I L I T Y - D E P . , NTIS, PC A05 /MF A01 PANL i.-

9456 Date 1979 111110 210000 719A00 861000 Radiation Damage and Annealing of C r - M o - V Steel. Vacek, M.; Havel, S.; Brunovsky, M. ZJE-239 A V A I L A B I L I T Y - S K O D A WORKS, NUCLEAR

POWER CONSTRUCTION DEPT., INFORMA-T I O N CENTRE, P L Z E N - CZECHOSI .pVAKIA

CZECHO

9467 Date Mid-December 1979 112120 112930 719AOO Fission Product Source Terms for the Light Water Reactor

Loss-of-Coolant Accident. Lorenz, R.A.; Collins, J.L.; Malinauskas, A.P. NUCL. TECHNOLOGY, 46(3), 404-410 O A R N L

9469 Date Mid-December 1979 112930 719A00 Release of Fission and Activation Products During Light

Water Reactor Core Meltdown. Albrecht, H.; Matschoss, V.; Wild, H. NUCL. TECHNOLOGY, 46(3), 559-565 G E R M A N

9593 Date 1978 112120 719A00 Release of Fission and Activation Products During LWR

Core Meltdown. Albrecht, H.; Matschoss, V.; Wild, H. I N I S - M F - 4 9 5 6 A V A I L A B I L I T Y - D E P . , NTIS (U.S. SALES ONLY) ,

PC A02 /MF A01 G E R M A N

9804 Date December 1979 111 110 719A00 Three Core Concepts for Producing Uranium-233 in Com-

mercial Pressurized Light Water Reactors for Possible Use in Water-Cooled Breeder Reactors (AWBA Development Program).

Conley, G.H.; et al. W A P D - T M - 1310 A V A I L A B I L I T Y - B E T T I S A T O M I C POWER LAB.,

WEST MIFFL IN , PA BETTIS

9845 Date March 1980 112120 532000 719A00 793000 T M I - 2 Decay Power: LASL Fission-Product and Acti-


England, T.R.; Wilson, W.B. ^ L A - 8 0 4 1 - M S , REVISED A V A I L A B I L I T Y - N T I S LOASL

307'

9919 .,. Date July 1979 112120 552110 711100 719A00 632120 Gamma Doses from Irradiated Assemblies Under Water. Rinard, P.M. L A - 7 9 1 4 - M S A V A I L A B I L I T Y - N T I S $4.50 LOASL

9990 Date August 1980 111110 329000 719A00 T R I M A R A N : A Threee Dimensional Multigroup PI Monte

Carlo Code for Criticality Studies. Ermumcu, G.; Gonnord, J.; Nimal, J.C. ORNL/RSIC-44 , PP.95-106 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 FRANCE

9996 Date August 1980 , 010000 329000 721100 719A00 795187 Radiation Streaming with S A M - C E . De Gangi, N.; Cohen, M.O.; Waluschka, E.; Steinberg, H.A. ORNL/RSIC-44 , PP.151-155 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 M A A G

Gas-Cooled Reactors

CATEGORY NUMBER 719B00

6388 Date Dec. 1977 719BOO Fort St. Vrain Plant Shielding Design and Measurements. Su, S.; Engholm, B.A.; Sund, R.E. CONF-770401, PP.197-204 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6396 Date Dec. 1977 719B00 329000 Neutron and Gamma-Ray Transport Studies in the

Helium Ducts and Turbogroups of a High Temperature Reactor with Helium Turbine (HHT) Using the Monte Carlo Method.

Taormina, A.; Kypreos, S. CONF-770401, PP.262-270 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


9999 Date August 1980 010000 329000 719AOO 795376 The Monte Carlo Lattice Program K I M . Cupini, E.; De Matteis, A.; Simonini, R. ORNL /RS IC-44 , PP.189-196 A V A I L A B I L I T Y - N T I S , PC A16 /MF A01 I T A L Y

10000 Date August 1980 111110 329000 424000 719A00 795154 An Analysis of Ex-Core Detector Response to

Core-Water Level Using Monte Carlo Techniques. Cacciapouti, R.J.; Lucier, R.D.; Harris, D.R.; Napolitano,

D. ORNL/RSIC-44 , PP.197-201 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 YAAEC

10072 Date July 1980 112730 112930 719A00 Fission Product Source Terms for the LWR

Loss-of-Coolant Accident. Lorenz, R.A.: Collins, J.L.; Malinauskas, A.P. NUREG/CR-1288; O R N L / N U R E G / T M - 3 2 1 A V A I L A B I L I T Y - N T I S O A R N L

6408 Date Dec. 1977 112760 719A00 719B00 713000 ^ Prediction of Primary Circuit Contamination in Power*

Reactors. j j f Beslu, P.; Costa, L.; Frejaville, G.; Pepin, P. CONF-770401, PP.374-391; ATOMKERNENERGIE,



6430 Date Dec. 1977 010000 719B00 Application of an Advanced Shielding Analysis System to

Gas Cooled Fast Reactor Designs. Bartine, D.E.; Williams, L.R.; Slater, C.O. CONF-770401, PP.570-579 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6466 Date Dec. 1977 111700 719BOO 795203 887000 Calculations of Neutron Radiation Levels^from HTGR

Spent Fuel. Sund, R.K.; Engholm, BfA.; Su, S. CONF-770401, PP.865-872

308


GEAC

6467 Date Dec. 1977 111110 422140 719B00 721200 795276 Analysis of a Fuel - Pin Neutron - Streaming Experiment to

Test Methods for Calculating Neutron Damage to the GCFR Grid Plate.

Slater, C.O.; Emmett, M.B. CONF-770401, PP.873-880 A V A I L A B I L I T Y - S C I E N C E P R E S S , 8 BROOKSTONE


6612 Date December 1977 111110 010000 719B00 713000 810000 Shielding and Control Materials for the Gas-Cooled Fast

Breeder Reactor. Simnad, M.T. G A - A - 1 4 4 7 8 A V A I L A B I L I T Y - N T I S $14.50 GEAC

6944 Date May 1978 111110 112120 210000 421200 719B00 810000 Distribution of Fission Products in Peach Bottom HTGR

Fuel Element F03-01. Dyer, F.F.; Wichner, R.P.; Martin, W.J.; Fairchild, L.L. O R N L / T M -5996 A V A I L A B I L I T Y - N T I S $10.75 O A R N L

8585 Date 1977 010000 111 110 210000 421140 430000 713000 717000



McElroy, W.N.; Bennett, R.A.; Johnson, D.L. EUR-5667E/F.PT.I , PP.1-26; CONF-750935,PT.I,

PP. 1 -26 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


WEE '

8710 Date 1978 010000 111110 32AOOO 329000 312000 551110 552210

713000 719B00 793000 794000 795254 795320 810000 Methods for U.S. Shielding Calculations: Applications to


8866 Date September 1978 111110 422110 551120 719BOO 810000 Fast Neutron Dose in High-Temperature Gas-Cooled


Neef, R.D.; Druke, V.; Khamis, H.; Litzow, W. CONF-780921, PP.1022-1027 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,



U.S. Nuclear Power Industry. < Blomeke, J.O.; Kee, C.W.; Nichols, J.P. O R N L - T M - 3 9 6 5 A V A I L A B I L I T Y - O A K RIDGE N A T I O N A L LABO-

RATORY O A R N L

8455 Date October 1978 112120 719B00 Distribution of Fission Products in Peach Bottom HTGR

Fuel Element E01-01. Wichner, R.P.; Dyer, F.F.; Martin, W.J.; Fairchild, L.L. O R N L / T M - 6 3 5 3 A V A I L A B I L I T Y - N T I S O A R N L

9020 Date December 1977 112760 719B00 A Review of Fission Product Plateout Investigations at Gen-

eral Atomic. Hanson, D.L. GA-A14555 A V A I L A B I L I T Y - N T I S $5.25 GEAC

9110 Date August 1979 111110 32AOOO 329000 551110 552210 719B00 795320

795203 810000 Analysis of the O R N L / T S F GCFR Grid-Plate Shield


309

9592 Date 1978 112120 719BOO Metallic Fission Product Releases from HTR-Spherical

Fuel Elements. Helmbold, M.; Amian, W.; Stoever, D.; Hecker, R. . I N I S - M F - 4 9 5 5 ; CONF-781022-93 A V A I L A B I L I T Y - D E P . , NT IS (U.S. SALES ONLY) ,


9759 Date 1979 111110 329000 719B00 Monte Carlo Computation of Directional Diffusion Coeffi-

cients. Gelbard, E.M.; Pego, R. CONF-790402,VOL.11, P P . 7 - 9 - - 7 - 1 9 A V A I L A B I L I T Y - H C - - ANS V I R G I N I A SECTION,


A R G O N N

9763 Date 1979 111110 330000 719BOO 794000 An Interface-Currents Integral Transport Model for

Treating Doubly Heterogeneous, Multisystem Geome-tries.

Westfall, R.M.; Bjerke, M.A. .. CONF-790402.VOL.i l , PP.7-71 - - 7 - 8 3 A V A I L A B I L I T Y - H C - - A N S V I R G I N I A SECTION,


O A R N L

9855 Date May 1980 111110 312000 32A000 551110 552210 795204 795254


Gas-Cooled Fast Reactor (GCFR). Slater, C.O.; Tomlinson, E.T.; Williams, L.R. O R N L / T M - 7 2 4 6 A V A I L A B I L I T Y - N T I S , PC A 0 5 / M F A01 O A R N L

10074 Date July 1980 111110 112760 870006 795217 719B00 Carbon-14 Production in the Peach Bottom HTGR Core. Wichner, R.P.; Dyer, F.F. ORNL-5597 A V A I L A B I L I T Y - N T I S O A R N L

H e a v y - W a t e r Cooled Reactors

CATEGORY N U M B E R 719C00

0 ' 1

6253 Date 1977 111110 421140 421130 421200 719C00 Neutron and Gamma-Ray Spectra Measurement on the

Model of the KS-150 Reactor Radial Shielding. Holman, M.; Hogel, J.; Marik, J.; Xovarik, K.; Franc, L.;

Vespalec, R. ZJE-197 A V A I L A B I L I T Y - SKODA WORKS, NUCLEAR

POWER CONSTRUCTION DEPARTMENT, I N F O R M A T I O N CENTRE, PLZEN - CZECHO-SLOVAKIA

CZECHO

6400 Date Dec. 1977 223000 719COO Design Measures to Minimize Radiation Exposure of Staff

for a Commercial Nuclear Power Plant. Keenan, F.; Pugh, I.G.; Youell, F.P. CONF-770401, PP.300-308; ATOMKERNENERGIE ,


D R , PRINCETON, NJ 08540 SCOTLA

6401 Date Dec. 1977 223000 719C00 Design Worth of Radiation Exposure Reduction. Collins, R.; James, R.A. CONF-770401, PP.309-316 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6405 Date Dec. 1977 112770 223000 719C00 Measurement and Prediction of Gamma-Ray Sources and

Dose Rates in the Vicinity of the Winfr i th SGHWR. Miller, P.C.; Avery, A.F.; Carter, M.D.; Chestnutt, M.M. CONF-770401, PP.342-352 A V A I L A B I L I T Y -SCIENCE PRESS, 8 BROOKSTONE


\ 6410 Date Dec. 1977

112120 223000 719C00 The Contribution of Fission Products to Radiation Fields in

a Pressurized Heavy Water Reactor. Neil, B.C.J.

310



Ducts, Mazes, Voids, and S t reaming -Neut rons - Calculation


6427 Date Dec. 1977 010000 719C00 The Methods of Calculation Used in Ihe Design of Shielding

Within the Primary Containment of a Commercial SGHWR.

Dutton, L.M.C.; Solari, P.A. CONF-770401, PP.545-553 AVA ILAB IL ITY ! , SCIENCE PRESS, 8 BROOKSTONE


6385 Date Dec. 1977 010000 713000 721100 Radiation Streaming The Continuing Problem of

Shield Design. Avery, A.F. IJ CONF-770401, PP.169-178; ATOMKERNENERGIE,



6429. . . : Date Dec. 1977 719C00 Shield Design of a 100 MW(th ) Research Reactor Chamany, B.F. CONF-770401, PP.563-569 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 I N D I A

9468 Date Mid-December 1979 112930 719C00 Space-Time Neutronic Analysis of Postulated

Loss-of-Coolant Accidents in C A N D U Reactors. Luxat, J.C.; Frescura, G.M. NUCL. TECHNOLOGY, 46(3), 507-516 C A N A D A

Pebble-Bed Reactors

CATEGORY NUMBER 719D00

6386 Date Dec. 1977 718000 721100 Radiation Streaming of N.S. Mutsu and Its Repair Plan. Osanai, M.; Miyakoshi, J.; Tsubosaka, A.; Miyasaka, S. CONF-770401, PP.179-187; ATOMKERNENERGIE ,



6387 Date Dec. 1977 718000 721100 Mockup Experiment and Analysis for the Primary Shield of

the Nuclear Ship Mutsu. Miyasaka, S.; Asaoka, T.; Taji, Y.; Ise, T.; Koyama, K.;

Tsutsui, T.; Takeuchi, M.; Fuse, T.; Miura, T.; Yamaji, Y.; Miyakoshi, J.; Tubosaka, T.; Furuta, K.; Kawakita, T.; Natume, H.; Nishizaki, T.; Okumura, Y.

CONF-770401, PP.188-196; ^ T O M K E R N E N E R G I E , 30(4), 269-274


JAPAN

6398 Date Dec. 1977 719D00 S2A000 870006 V\ Neutron Dosage at Steel Components in the THTR. Wahsweileri H.G.; Hehn, G. CONF-770401, PP.280-287 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 G E R M A N «:

o o-

oc

6389 Date Dec. 1977 719AOO 721100 795209 795203 Neutrons and Gamma-Ray Streaming in the Annulus

Between the Reactor Pressure Vessel and the Sacrificial Shield of the Caorso Nuclear Power Station.

Barbucci, P.; Di Pasquantonio, F. CONF-770401, PP.205-213 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


O 311

639 0 Date Dec. 1977 719A00 721100, Empirical Solution of Radiation Streaming Problems in the

Ai r Gap Around the Pressure Vessel of a PWR. Francis, C.C. CQNF-770401, PP.214-222 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 T V A

O 639 1 Date Dec. 1977

719AOO 721100 722100 Shielding Against Neutron Streaming in Pressurized Water

Reactors. Devillers, C.; Payen, J.P. CONF-770401, PP.223-229; ATOMKERNENERGIE,


DR., PRINCETON, NJ 08540 FR.ANCE

6425 i Date Dec. 1977 111210 717000 329000 795203 721100 Monte Carlo Analysis of the Effects of Penetrations on the

Performance of a Tokamak Fusion Reactor. Santoro, R.T.; Tang, J.S.; Alsmiller, R.G.,Jr.; Barnes, J.M. CONF-770401, PP.527-535 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6438 Date Dec. 1977 329000 721100 A Study of Applicability of an Albedo Monte Carlo Method

for Neutron Streaming Calculation. Kawai, M.; Yamauchi, M.; Kadotani, H.; Suzuki, I. CONF-770401, PP.636-644 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6439. . . P Date Dec. 1977 329000 721100 Neutron Streaming Through Conical Ducts, de Beer, G.P. CONF-770401, PP.645-651 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 SAFRIC


Calculations in LMFBR.

Nishimura, T.; Kinjo, H. CONF-770401, PP.680-687 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6465 Date Dec. 1977 329000 721100 722100 795090 795187 Intercomparison of Monte Carlo Calculations and Measure-

ments of the Neutron and Gamma-Ray Streaming in Multibend Ducts.

Vogt, D.G. CONF-770401, PP.857-864 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE




Neutronic Characteristics of a Fusion Reactor. Ide, T.; Seki, Y.; Iida, H. CONF-760935-P2, PP. 395-406 A V A I L A B I L I T Y - N T I S JAPAN


and Shield in Noncircular Toroidal Geometry. Gohar, Y.; Maynard, C.W.; Cheng, E.T. _____ CONF-760935-P3, PP. 833-844 A V A I L A B I L I T Y - N T I S U - W I

7112 Date July 1976 111 110 421140 721100 721200 719A00 853800 861000 Passage of Neutrons with Intermediate Energies Through



8253 Date November 1978 111210 32AOOO 329000 717000 721100 Radiation Shielding of Major Penetrations in Tokamak

Reactors. Jung, J.; Abdou, A. NUCL. TECHNOLOGY, 41(1), 71-86 A R G O N N

o

o o 312 f

8517 Date February 1979 020000 111210 122310 312000 32A000 551110 552110




O R N L / T M - 6 5 8 8 A V A I L A B I L I T Y - N T I S $4:50 O A R N L

8796 Date February 1979 111110 223000 32A000 521130 522130 551110 552210

721100 722100 719A00 795254 795203 795276 810000 Methodology for the Analysis and Design of a PWR Reactoro

Cavity Shield System. , <•„ fCelnik, J. / M ORNL/RSIC-43,PP.54-67;

ANS/SD-79 /16 , PP.54-67 * A V A I L A B I L I T Y - N T I S BURNS

V 8791 Date February 1979

010000 111 110 223000 719A00 721100 722100 Radiation Streaming, in Power Reactors. Lahti, G.P.; Lee, R.R.; Courtney, J'.'C. (Eds.) O R N L / R S I C - 4 3 ; A N S / S D - 7 9 / 1 6 A V A I L A B I L I T Y - N T I S $9.25 OR A N L

8793 Date February 1979 111110 32A000 329000 223000 719A00 721100 722100


siderations. Simmons, G.L. ORNL/RSIC-43,PP.22-27;


8797 Date February 1979 111110 329000 721100 722100 793000 719AOO 610000


Harmonics Expansion of Albedo Data. Albert, T.E.; Simmons, G.L. ORNL/RSIC-43,PP.68-75;

ANS/SD-79 /16 , PP.68-75 A V A I L A B I L I T Y - N T I S SCA

r-u'v 8798 '>:,:?. Date February 1979

111110 223000 329000 721100 721200 722100 620000 719A00 422110

Reactor Cavity Streaming—The Problem and Engineer-ing Solutions.

Iotti, R.C.; Yang, T.L. ORNL/RSIC-43,PP.76-109;

ANS/SD-79 /16 , PP.76-109 A V A I L A B I L I T Y - N T I S EBASCO

8794 Date February 1979 " 111110 223000 32A000 329000 719A00 721100 722100




8801 Date February 1979 111110 32A000 329000 721100 719A00 794000 795203

795276 810000 Calculations of the Neutron 'Environment Inside a PWR

Containment. Hopkins, W.C. ORNL/RSIC-43,PP. 127 - 136;

ANS/SD-79/16,PP.127-136 A V A I L A B I L I T Y - N T I S BECHTE

8795 Date February 1979 111110 223000 32AOOO 721100 722100 795198 719A00 Reactor Cavity Radiation Streaming. Cardito, J.M.; Eastman, E.A.B.; Allen, P.R.; Wainio, K.M. ORNL/RSIC-43,PP.43 - 53;

ANS/SD-79/16,PP.43-53 A V A I L A B I L I T Y - N T I S STONE ''

8802 Date February 1979 111110 32A000 551110 719A00 710000 721100 810000 A Low Pressure Drop Reactor Cavity Shield System. Klotz, R.J.; Cavanaugh, G.P.; Kassawara, R.P.;


ANS/SD,-79/16,PP.137-148 A V A I L A B I L I T Y - N T I S COE (I O

313

8803 Date February 1979 111110 329000 710000 719A00 721100 795207 810000 Radiation Streaming and Reactor Cavity Shield Design at

T V A PWR Plants. Francis, C.C.; Galbreth, T.M.; Zobel, W. ORNL/RSIC-43,PP.149-162;

ANS/SD-79/16,PP.149-162 . A V A I L A B I L I T Y - N T I S T V A

880 4 Date February 1979 111110 329000 719A00 721100 810000 Radiation Shielding for BWR Shield Wall Penetrations. Gillett, T.C.; Warkentin, J.K. ORNL/RSIC-43,PP.163-177;

ANS/SD-79/16,PP.163-177 A V A I L A B I L I T Y - N T I S B R A U N

880 5 Date February 1979 111110 795144 710000 721100 719A00 810000 Shield Design Against Neutron Streaming.in the Vicinity of

a BWR Pressure Vessel. SeifTerth, L.; Przibram, E.; Hock, R. ORNL/RSIC-43,PP. 178 -192;

ANS/SD-79/16,PP.178-192 A V A I L A B I L I T Y - N T I S G E R M A N

8969 Date May 1979 111110 329000 721100 870011 Contributon Monte Carlo. Dubi, A.; Gerstl, S.A.W. L A - 7 8 4 9 - M S A V A I L A B I L I T Y - N T I S LOASL °

o

9996 Date August 1980 010000 329000 721100 719A00 795187 Radiation Streaming with S A M - C E . 1

De Gangi, N.; Cohen, M.O.; Waluschka, E.; Steinberg, H.A. O R N L / R S I C - 4 4 , PP. 151-155 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 M A A G

10005 : Date August 1980 010000 329000 721100 853100 870011 Deep-Penetration Calculations. " Thompson, W.L.; Deutsch, O.L.; Booth, T.E. > " ' O R N L / R S I C - 4 4 , PP.267-294 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 LOASL



Ueki, K. O R N L / R S I C - 4 4 , PP.329-344 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 JAPAN

Ducts, Mazes, Voids, and S t r eaming -Neu t rons - Exper imen t


6394 Date Dec.01977 713000 721200 870011 Neutron Transport Through Straight and Once Bent

Sodium Pipe in Shielding of Fast Reactors. ^ Burian, J.; Jansky, B.; Osmera, B.; Otopal, P.; Rataj, J.;



" J" o" 6397 . DaitfDec. 1977

713000 721200 A Study of Fast Neutron Streaming Through the Core Sup-

port-Plant Shield of a LMFBR. Suzuki, I.; Inous, T.; Oka, Y.; Wakabayashi, H.; An, S.;

Sasaki, K.; Miyasaka, S. CONF-770401, PP.271-279 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 — JAPAN

10002 Date August 1980 111220 721100 795372 870011 853100 Calculational Problem for Deep Penetration of Neutrons

Through a One-Bend Sodium Duct. Sartori, E. O R N L / R S I C - 4 4 , PP.219-229 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 FRANCE



Natume, H.; Nishizaki, T.; Okumura, Y.; Miyasaka, S.; Asaoka, T.; Taji, Y.; Ise, T.; Koyama, K.; Tsutsui, T.; Takeuchi, M.; Fuse, T.; Miura, T.; Yamaji, A.

o 314

0



6467 Date Dec. 1977 111110 422140 719B00 721200 795276 Analysis of a Fuel-Pin Neutron-Streaming Experiment to

Test Methods for Calculating Neutron Damage to the GCFR Grid Plate.

Slater, C.O.; Emmett, M.B. CONF-770401, PP.873-880 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


7112 '1. Date July 1976 111110 421140 721100 721200 7WAQ0 853800 861000 Passage offNeutrons with Intermediate Energies' Through

Shielding with Complex Irregvinrities. Bolyatko, V.V.; Sakharov, V.M.; Suvortv, A.P,: Kharizo-

menov, Yu.V. ERDA-TR-125 , PP. 127-139 A V A I L A B I L I T Y - N T I S RUSSIA

8047.9 ' , , ' . . Date, May 1978 1 111 10 423140 719A00 721200, Neutron Streaming Measurements at an 850<-MWe Pres-


Ritchie, J.C. : H E A L T H PHYS., 34(5), 479-483

N U R C

8798 Date February 1979 1 11110 223000 329000 72UOO 721200 722100 620,000'

719A00'422110 Reactor Cavity Streaming--The Problem and Engineer-

ing Solutions. Iotti, R.C.; Yang, T.L. O R N L / R S I C - 4 3 , PP.76-109;

ANS/SD-79/16,PP.76-109 , 1

A V A I L A B I L I T Y - N T I S EBASCO

8799 Date February 1979 I I1110 223000 721200 719A00 Measured Distribution of Neutrons Inside Containment of

a PWR. Butler, H.M. ; Ohnesorge, W.F.; Auxier, J.A. ORNL/RSIC-43,PP.110-113;

ANS/SD—79/16.PP. 110-113


8800 Date February 1979 111110 422140 721200 719A00 A Survey of Neutrons Inside the Containment of a Pressur-

ized Water Reactor. Hankins, D.E.; Griffith, R.V. ORNL/RSIC-43 ,PP. l 14-126;

ANS/SD-79/16,PP.114-126 A V A I L A B I L I T Y - N T I S L A L L

Ducts, Mazes, Voids, and S t r eaming -Gamma-Ray - Calculation


6391 Date Dec. 1977 719A00 721100 722100 Shielding Against, Neutron Streaming in Pressurized Water

Reactors. Devillers, C ; Payen, J.P. COMF--77Q401, PP.223-229; ATOMKERNENERGIE,



6395 Date Dec. 1977 722100 853100 Calculation of Duct and Annular Gap Problems With

ESi 'OQ-DOT and Analytical Expressions. Zumach, W. CQNF-770401, PP.253-261 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


o /, 6444 Date Dec. 1977

63/1000 722100 A Simple Albedo Method for Calculating Effects of Sin-

gle-Legged Ducts. Celnik, J. ,CONF-770401, PP.688-693 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 BURNS

6465 Date Dec. 1977 329000 721100 722100 795090 795187 Intercomparison of Monte Carlo Calculations and Measure-

ments of the Neutron and Gamma-Ray Streaming in Multibend Ducts.

315

Vogt, D.G. CONF-770401, PP.857-864 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6672 Date December 1977 112B00 112720 322000 328000 722100 795084 810000 Computer Program SCAP-BR for Gamma-Ray Stream-

ing Through Mult i -Legged Ducts. Byoun, T.Y.; Babel, P.J.; Dajani, A.T. CONF-771109-88 A V A I L A B I L I T Y - D E P . , NTIS BURNS

7072 Date January 1977 112720 322000 722100 Gamma Ray Streaming Through Annular Cylindrical Duct. Murthy, K.P.N.; Vaidyanathan, R.; Singh, R.S. 'NBS SPEC. PUB. 461, PP. 132-135 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

W A S H I N G T O N , D.C. 20402 f x-I ~>IA 3

\ \ \J 7109 Date July 1976

112B00 329000 722100 810000 Passage of Gamma-Radiation from Point Sources with an


Zolotukhin, V.G.; Yefimenko, B.A.; Klimanov^ V.A.; Kochanov, V.A.; Mashkovich, V.P.; Orlov, N.Yu.

E R D A - T R - 1 2 5 , PP. 100-105 „ A V A I L A B I L I T Y - N T I S RUSSIA

8791 Date February 1979 010000 111110 223000 719A00 721100 722100 Radiation Streaming in Power Reactors. Lahti, G.P.; Lee, R.R.; Courtney, J.C. (Eds.) O R N L / R S I C - 4 3 ; A N S / S D - 7 9 / 1 6 A V A I L A B I L I T Y - N T I S $9.25 O R A N L

8793 Date February 1979 111110 32AOOO 329000 223000 719A00 721100 722100


siderations. , /"/-"x-Simmons, G.L. ORNL/RSIC-43,PP.22-27;


8794 Date February 1979 111110 223000 32AOOO 329000 719A00 721100 722100




8795 Date February 1979 111110 223000 32A000 721100 722100 795198 719AOO Reactor Cavity Radiation Streaming. Cardito, J.M.; Eastman, E.A.B.; Allen, P.R.; Wainio, K.M. ORNL/RSIC-43,PP.43-53;

ANS/SD-79/16,PP.43-53 A V A I L A B I L I T Y - N T I S STONE

8796 i . . 'Dale February 1979 111110 223000 32A000 521130 522130 551110 552210


Cavity Shield System. Celnik, J. O R N L / R S I C - 4 3 , PP.54-67;

ANS/SD-79/16,PP.54-67 , A V A I L A B I L I T Y - N T I S

BURNS

" }

• h , U (J V

8792 Date February 1979 010000 111110 223000 32AOOO 521110 522110 610000


LWRs. Rahn, F.; Ti l l , H. ORNL/RSIC-43,PP.1-21 ; ANS/SD-79/16,PP.1 - 2 1 A V A I L A B I L I T Y - N T I S EPRI

8797 Date February 1979 111110 329000 721100 722100 793000 7I9A00 610000


Harmonics Expansion of Albedo Data. Albert, T.E.; Simmons, G.L. ORNL/RSIC-43,PP.68 - 75;

ANS/SD-79 /16 , PP.68-75 A V A I L A B I L I T Y - N T I S SCA

316

8798 Date February 1979 111110/223000 329000 721100 721200 722100 620000



ANS/SD-79/16,PP.76-109 A V A I L A B I L I T Y - N T I S EBASCO

S t r u c t u r e Shielding - Vehicle


8263 Date August 1978 111130 111400 32AOOO 329000 731100 795262 M113A1 Armored Personnel C a r r i e r ^ Initial Radiation

Protection Factors. Stueker, S.; Rainis, A.E.; Schwenk, R.M. A R B R L - T R - 0 2 0 9 7 A V A I L A B I L I T Y - D E F E N S E D O C U M E N T A T I O N

CENTER, C A M E R O N STATION, A L E X A N D R I A , V I R G I N I A 22314

A R M Y

9561 Date August 1979 111400 112130 32A000 329000 73,1100 793000 795262 Nuclear Vulnerability Analysis of the X M - 1 Tank in an

Init ial Nuclear Radiation Environment. Kinch, J.W.; Rainis, A.E. A R B R L - T R - 0 2 1 8 3 A V A I L A B I L I T Y - D E F E N S E D O C U M E N T A T I O N

CENTER, C A M E R O N STATION, A L E X A N D R I A , VA 22314

A R M Y

Rainis, A.E.; Kinch, J.W. A R B R L - M R - 0 2 9 3 4 A V A I L A B I L I T Y - D E F E N S E D O C U M E N T A T I O N


A R M Y

S t r u c t u r e Shielding - Buildings, Bunkers , and She l te r s



Materials. Swedjemark, G.A. SSI -1977-004 A V A I L A B I L I T Y - N T I S SWEDEN

8046 Date May 1978 112760 329000 731200 795299

•/ Calculation of Exposure Rates from Gamma Sources in Walls of Dwelling Rooms.

Koblinger, L. H E A L T H PHYS., 34(5), 459-463 H U N G A R


Plant. Kukhtevich, V.I.; Goryac'nev, I.V.; Trykov, L.A. BOOK ( I N RUSSIAN) A V A I L A B I L I T Y - A T O M I Z D A T , MOSCOW RUSSIA

9562 Date August 1979 111400 112130 329000 795203 731100 793000 810000 Radiation Shielding Properties of Selected Materials. <> Rainis, A.E.; Kinch, J.W.; Bowers, G.A. A R B R L - T R - 0 2 1 8 7 A V A I L A B I L I T Y - D E F E N S E D O C U M E N T A T I O N


A R M Y



Kocher, D.C. O R N L / T M - 6 5 2 6 A V A I L A B I L I T Y - N T I S $6.00 O A R N L

9563 Date July 1979 111400 112800 329000 32A000 551110 552110 552210


Tank and APRD Reactor Scenario.

9018 Date Apri l 1978 112930 632110 731200 Protective Action Evaluation. Part 1. Effectiveness of Shel-

tering as a Protective Action Against Nuclear Accidents Involving Gaseous Releases.

317

Anno, G.H.; Dore, M.A. E P A - 5 2 0 / I - 7 8 - 0 0 1 A A V A I L A B I L I T Y - NTIS ENPA

9539 Date October 24, 1979 112920 522120 731200 Fallout Model for System Studies. Harvey, T.F.; Serduke, F.J.D. UCRL-52,858 A V A I L A B I L I T Y - N T I S L A L L

9738 Date M i d - A p r i l 1980 222000 631000 731200 Effects of Indoor Residence on Ridiation Doses from Rou-

tine Releases of Radionuclides to the Atmosphere. Kocher, D.C. NUCL. TECHNOLOGY, 48(2), 171-179 O A R N L

Structure Shielding - Ships and Compartmented Structures




Natume, H.; Nishizaki, T.; Okumura, Y.; Miyasaka, S.; Asaoka, T.; Taj i , Y.; Ise, T.; Koyama, K.; Tsutsui, T.; Takeuchi, M.; Fuse, T.; Miura, T.; Yamaji, A.



Shield Construction and Fabrication


7126 Date July 1976 111110 740000 853200 853800 The Use of Barium-Serpentine Cement in Reactor Shields

of Atomic Power Plants. Voskresenskiy, Ye.V.; Yegorov, Yu.A.; Zaalishvili, G.G.;

Kutateladze, K.S.; Lekishvili, R.A.; Pankrat'yev, Yu.V.; Piskunov, V.L

E R D A - T R - 1 2 5 , PP. 260- 272 A V A I L A B I L I T Y - N T I S RUSSIA

Accelerator Shielding (including neutron generators)


8020 Date December 1977 422120 521220 750000 Measurement of Stray Neutron Doses Around KEK

PS-Faci l i ty (1). Miyajima, M.; Hirayama, H.; Hozumi, K.; Miura, S.;

Katoh, K. K E K - 7 7 - 1 7 A V A I L A B I L I T Y - N A T I O N A L LABORATORY FOR

H I G H ENERGY PHYSICS, O H O - M A C H I , T S U K U B A - G U N , I B A R A K I - K E N , 300-32, JAPAN

JAPAN

8811 Date October 1978 111220 329000 750000 795203 810000 Transport of Accelerator Produced Neutrons in a Concrete

Room. McCall, R.C.; Jenkins, T.M.; Shore, R.A. SLAC-PUB-2214 ; CONF-781113-19 A V A I L A B I L I T Y - D E P . , NT IS STLAC

8983 Date March 1979 113100 513120 750000 853100 Attenuation of Primary and Leakage Radiation in Concrete

for X - R a y s from a 10 MV Linear Accelerator. Tochilin, E.; LaRiviere, P.D. H E A L T H PHYS., 36(3), 387-392 V A R I A N

6804 Date September 5, 1970 111110 710000 740000 853100 853300 853400 853700 N Reactor Shielding. Davis, H.S. D U N - S A - 1 5 1 A V A I L A B I L I T Y - N T I S DOUGLA Vt

8986 Date May 1979 111220 750000 Leakage Neutrons Produced by 10 MeV Medical Accelera-

tors. McGinley, P.H.; Fenn, J.O.; White, T.A.,Jr. H E A L T H PHYS., 36(5), 635-637 U - G A

318

9028 Date August 1979 112710 329000 32AOOO 510000 750000 717000 793000


Induced Residual Activation Dose Rates. Barish, J.; Gabriel, T.A.; Alsmiller, R.G,Jr. ORNL-5561 A V A I L A B I L I T Y - N T I S $6.00 O A R N L

9052 Date December 1978 410000 750000 760000 A Simple Method of Energy Determination for Electron

Accelerators Used in Medicine. Liesem, H.; Pohlit, W. STI /PU B - 471 (VOL.2),PP.291 - 300;

CONF-771209-P2,PP.291 -300; A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C


9062 Date February 15, 1979 111220 329000 750000 853100 Neutron and Photon Measurements Through Concrete from

a 15 GeV Electron Beam on a Target - Comparison with Models and Calculations.

Jenkins, T.M. NUCL . INSTRUM. METHODS, 159(2,3), 265-288 STLAC

9195 Date September 1977 111220 710000 750000 PEP Radiation Shielding Tests in SLAC A Beam. Ash, W.; DeStaebler, H.; Harris, J.; Jenkins, T.; Murray, J. S L A C - T N - 7 7 - 5 ; PEP-252 A V A I L A B I L I T Y - D E P . , NTIS STLAC


by Electron -Transport Calculations. Peek, J.M. S A N D - 7 9 - 0 7 7 2 A V A I L A B I L I T Y - D E P . , NTIS, PC A 0 6 / M F A01 S A N D I A

A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 H A N F O R

Medical Facilities


6690 Date February 1978 /

111220 122110 32AOOO 421000 521130 551110 760000 1 „ 810000 795042

Nuclear Data Development and Shieid Design for Neutrons Below 60 MeV.

Wilson, W.B. L A - 7 1 5 9 - T A V A I L A B I L I T Y - NT IS LOASL


Radiotherapy. Wells, A.H.' L A - 7 2 8 8 - T A V A I L A B I L I T Y - N T I S $13.25 LOASL

8472 Date November 1978 113100 760000 Simplified Shielding for Diagnostic X - R a y Rooms. (Notes) Rummerfield, P.S. H E A L T H PHYS., 35(5), 718-719 APRPS

8854 Date September 1978 010000 122100 122200 220000 312000 32A000 760000


Dose and Simulation of Tissue Response in Neutron Therapy. ' <•

Pfister, G.; Hehn, G.; Mattes, M.; Friedlein, H.P. CONF-780921, PP.621-627 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,


9986 Date August 1980 010000 111110 111220 329000 713000 750000 810000 Monte Carlo Applications at Hanford Engineering Develop-

ment Laboratory. Carter, L.L.; Morford, R.J. O R N L / R S I C - 4 4 , PP.7-30

8855 Date September 1978 010000 122100 210000 760000 845000 Basic Nuclear Data for Dosimetry in Radiotherapy and

Radiobiology. Ricourt, A.; Chemtob, M.; Nguyen, V.D.; Parmentier, N . CQNF-780921, PP.628-635

319

A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L , 75775 PARIS CEDEX 16, F R A N C E

FRANCE

8857 Date September 1978 010000 122100 210000 760000 845000 Nuclear Data for Radiotherapy with Neutrons. Cross, W.G. CONF-780921, PP.648-666 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, FRANCE C A N A D A

8858 Date September 1978 010000 122100 210000 760000 845000 Recent Trends in Nuclear Reaction Data Needs for Nuclear

Medicine. Stocklin, G.; Qaim, S.M. CONF-780921, PP.667-687 A V A I L A B I L I T Y - O E C D , 2, ,RUE A N D R E - P A S C A L ,


8984 Date May 1979 113100 423300 513120 760000 885000 Use of Gypsum Wallboard for Diagnostic X - R a y Protec-

tive Barriers. Glaze, S.A.; Schneiders, N.J.; Bushong, S.C. H E A L T H PHYS., 36(5), 587-593 U - T X

8985 Date May 1979 113100 423300 513120 760000 885000 Attenuation Characteristics of Gypsum Wallboard. Christensen, R.C.; Sayeg, J.A. H E A L T H PHYS., 36(5), 595-600 U - K Y

9051 Date December 1978 113100 410000 760000 Ionization-Chamber-Dependent Factors for Calibration

of Megavoltage X - R a y and Electron Beam Therapy Machines.

Almond, P.R.; Mendez, A.; Behmard, M . STI/PUB-471(VOL.2),PP.271-289;

CONF - 771209 -P2.PP.271-289; A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C

ENERGY AGENCY, V I E N N A ( A U S T R I A ) U - T X

9052 Date December 1978 410000 750000 760000 A Simple Method of Energy Determination for Electron

Accelerators Used in Medicine. '• \ Liesem, H.; Pohlit, W. \ \ ST I /PUB-471 (VOL.2),PP.291-300; iV\

C O N F - 771209-P2,PP.291 - 300; \ \ A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C


9285 Date 1978 111220 760000 845000 Transport Calculations, Analytical Representations of

Absorbed Dose and Determination of Isoeffect Curves for Therapy with Fast Neutrons.

Bohm, J.K.; Eissa, H.M.; Hehn, G.; Pfister, G.; Stiller, P. EUR-5848,PP.145-163; CONF-770597,PP.145-163 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-

TIONS OF T H E EUROPEAN C O M M U N I T I E S , BOITE POSTALE 1003 - L U X E M B O U R G ISBN 92 -825 -0256-2

G E R M A N

9287 Date 1978 111220 760000 Comparison of High Energy Neutron Sources for Radiation

Therapy. Grant, W.H.; Almond, P.R.; Otte, V.A.; Anderson, M.D.;

Smathers, J.B. EUR-5848,PP.303-314;.CONF-770597,PP.303-314 A V A I L A B I L I T Y - O F F I C E FOR OFFIC IAL PUBLICA-

T IONS OF T H E EUROPEAN C O M M U N I T I E S , BOITE POSTALE 1003 - L U X E M B O U R G ISBN 92 -825 -0256 -2

U - T X ;

929 0 Date 1978 111220 220000 421140 421200 760000 842000 845000 Determination of Neutron and Gamma Spectra in a Mixed

(n, gamma)-Field. Schmidt, R.; Magiera, E. EUR - 5848,PP.443 - 454; C O N F - 770597,PP.443 - 454 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-

TIONS OF T H E EUROPEAN COMMUNIT IES , BOITE POSTALE 1003 - LUXEMBOURG ISBN 92 -825 -0256 -2

G E R M A N

929 1 Date 1978 111220 220000 760000 Radiation Quality Studies in Mixed Neutron-Gamma

Fields. Menzel, H.G.; Waker, A.J.; Grillmaier, R.; Bihy, L.; Hart-

mann, G.

320

EUR-5848,PP.481-497; CONF-770597,PP.481-497 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-

T IONS OF T H E EUROPEAN COMMUNITIES, BOITE POSTALE 1003 - LUXEMBOURG ISBN 92 -825 -0256 -2

G E R M A N

9822 Date May 1980 760000 Development Studies Regarding the Construction of Epi-

thermal-Enriched Neutron Field for Medical Purposes at the University of Tokyo YAYOI Fast Reactor.

An, S.; Furuhashi, A.; Oka, Y.; Akiyama, M.; Kuga, H.; Tanaka, H.

NUCL. TECHNOLOGY, 48(3), 204-215 JAPAN

Irradiation Facilities


6809 Date 1978 010000 111110 410000 122200 511120 421140 770000

430000 Benchmark Neutron Fields for Reactor Dosimetry. Grundl, J.; Eisenhauer, C. IAEA-208, VOL.I, 'PP.53-104 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE



9047 Date December 1978 112760 410000 770000 A Technique to Compensate for Geometry-Induced Errors

in a Photon Irradiator Calibration. Mulhern, O.R.; Hooker, C.D. STI/PUB-471(VOL,2),PP.201 -205;

CONF-771209-P2, PP.201 -205; A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C

ENERGY AGENCY, V I E N N A (AUSTRIA) BANW

Data Library Collection Used





6537 Date September 1977 717000 793000 795253 Feasibility Study of L iF -BeF /sub 2/ amd Chloride Salts

as Blanket Coolants for Fusion Power Reactors. Imamura, Y. PPPL-1380 A V A I L A B I L I T Y - D E P . , NTIS U - N J


8565 Date 1977 111210 32AOOO 329000 511110 512210 830000 853100


Facility. Peng, W.H.; Celnik, J. CONF-771029,VOL.11, PP.1704-1706 A V A I L A B I L I T Y - I E E E SERVICE CENTER, SINGLE


BURNS

6746 Date September 1977 111110 112110 112400 112500 32A000 511110 551110


Damage Studies. Gritzner, M.L.; Simmons, G.L.; Albert,T.E.; Straker, E.A. EPRI -NP-152 , F I N A L REPORT A V A I L A B I L I T Y - S C I E N C E APPLICATIONS INC.,


321

6772 Date Apr i l 1978 111210 329000 793000 795203 717000 810000 Three Dimensional Neutronics Analysis of the Mir-


Ragheb, M.M.H.; Klein, A.C.; Maynard, C.W. U W F D M - 2 3 9 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,


U - W I

7069 Date January 1977 111110 32A000 423140 511110 511120 793000 795254



WASHINGTON, D.C. 20402 N A V Y

6935 Date June 1978 111210 710000 717000 793000 795254 853100 Shielding Calculations for the Intense Neutron Source Facil-

ity. Final Report. Battat, M.E.; Henninger, R.J.; Macdonald, J.L.; Dudziak,

D.J. L A - 7 3 3 2 - M S A V A I L A B I L I T Y - N T I S $4.00 LOASL

7090 Date May 1977 111210 311000 329000 531000 532000 793000 717000



Santoro, R.T.; Tang, J.S.; Alsmiller, R.G.,Jr.; Barnes, J.M. O R N L / T M - 5 8 7 4 A V A I L A B I L I T Y - N T I S $4.00 O A R N L

<'j 7027 Date September 1976

111110 111210 32A000 521130 717100 810000 793000 795254

Fusion-Fission Neutronics Calculations for the Laser Sole-noid.

Woodruff, G.L.; Quimby, D.C. CONF-760935-P2, PP. 787-798 ' A V A I L A B I L I T Y - NTIS M A S N

8023 Date June 1978 111110 122110 511110 551110 713000 793000 794000

122310 E N D F / B - I V , L I B - I V , and the CSEWG Benchmarks. Kidman, R.B. L A - 7 3 5 5 - M S A V A I L A B I L I T Y - L O S A L A M O S SCIENTIFIC LAB.,


7033 Date September 1976 111210 32A000 521230 422130 717000 717100 870003



8033 Date August 1978 111110 230000 325000 551110 713000 887000 793000

794000 Preliminary Neutronic Siiidy of Actinide Transmutation in

a Fast Reactor. Williams, M.L.; McAdoo, J.W.; Flanagan, G.F. O R N L / T M - 6 3 0 9 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

7035 Date September 1976 111110 111210 521130 522130 717100 32A000 810000

793000 795254 Natural-Uranium Light-Water Breeding Hybrid Reac-

tors. Greenspan, E.; Schneider, A.; Filai, D.; Levine, P. CONF-760935-P3, PP. 1061-1073 A V A I L A B I L I T Y - N T I S ISRAEL

9

8034 '. Date August 1978 111110 220000 32AOOO 551110 552210 820000 861000


with Experimental Data. Santoro, R.T.; Alsmiller, R.G.,Jr.; Barnes, J.M. O R N L / T M - 6401/R1 $ A V A I L A B I L I T Y - N T I S $4.00 O A R N L

8035 Date August 1978 111220 122110 32A000 511110 853900 853700 861000


Energies to 60 MeV. Alsmiller, R.G,Jr. ORNL /TM-6486 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8115 Date February 1978 111110 122110 793000 810000 Multigroup and Few-Group Cross Sections for

E N D F / B - I V Fission Products; theTOAFEW Collaps-ing Code and Data File of 154-Group Fission-Product Cross Sections.

Wilson, W.B.; England, T.R.; LaBauve, R.J. L A - 7 1 7 4 - M S AVAILABIL ITY-DEP. , NTIS LOASL

8403 Date March 1978 122110 122210 220000 531000 532000 793000 794000



Gohar, Y.; Abdou, M.A. ANL /FPP /TM-106 A V A I L A B I L I T Y - N T I S $9.25 ARGONN

GAC - A N L TNS Scoping Studies. Volume V. Support Engineering, Trit ium and Neutronics.

Project Staff - Argonne National Lab. GA-A14614,VOL.V; ANL/FPP/77-6,VOL.V A V A I L A B I L I T Y - N T I S $8.00 GEAC

8517 Date February 1979 020000 111210 122310 312000 32A000 551110 552110


Streaming Experiment with a Two-Dimensional Model. i


ORNL /TM-6588 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8518 Date'January 1979 111210 122310 32A000 521130 551110 717000 793000



Seki, Y.; Santoro, R.T.; Oblow, E.M.; Lucius, J.L. ORNL /TM-6667 A V A I L A B I L I T Y - N T I S $4.00 OARNL

8435 Date January 1979 111110 112930 122110 329000 32AOOO 325000 551110


ruptive Accidents. Tomlinson, E.T. ORNL/CSD-35 A V A I L A B I L I T Y - N T I S $5.25 OARNL

8481 Date January 1979 230000 793000 794000 717000 Preliminary Design and Neutronic Analysis of a Laser

Fusion Driven Actinide Waste Burning Hybrid Reactor. Berwald, D.H.; Duderstadt, J.J. NUCL. TECHNOLOGY, 42(1), 34-50 U - M I

8496 Date January 1978 111210 329000 32A000 551110 552110 793000 717000$''

810000 x.

!>

O ... v q, -•-. *.;<s-yi.il" !? 323 'ft

8565 //. Date 1977 111210 32A000 3290007511110 512210 830000 853100


Facility. 'Peng, W.H.; Celnik, J. CONF-771029,VOL.11, PP.1704-1706 A V A I L A B I L I T Y - I E E E SERVICE CENTER, SINGLE


BURNS

8567 Date 1977 111210 223000 521130 522130 717000 795217 795254



U-TX A

ti

8577 Date November 1978 111110 32A000 1223)0 312000 551110 551200 793000


8734 Date March 1979 112760 220000 222000 870090 870094 793000 Doses for Various Pathways to Man Based on Uni t Concen-


Hi l l , G.S. O R N L / O E P A - 7 A V A I L A B I L I T Y - N T I S O A R N L

8591 Date 1977 111210 210000 421140 430000 717000 521130 795254



Odette, G.R. EUR - 5667E/F.PT.I, PP.84-97; CONF-750935,PT.I,

PP.84-97 f A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L P U B L I C A -

T IONS OF T H E EUROPEAN C O M M U N I T I E S , V BOITE POSTAL; 1003 - L U X E M B O U R G

U - C A (i


Research Reactor. Allen, E.J.; Kerr, H.T. EUR-5667E/F,PT. I , PP.4I4-423;

CONF-750935,PT.I , PP.414-423 A V A I L A B I L I T Y - O F F I C E FOR OFF IC IAL PUBLICA-

T IONS OF T H E EUROPEAN C O M M U N I T I E S , BOITE POSTAL, 1003 - L U X E M B O U R G

O A R N L

8662 Date February 1979 111110 32A000 312000 421130 511110 870041 794000


Cross Sections. Ingersoll, D.T.; Wehring, B.W. O R N L / R S I C - 4 2 , PP. 179-189 A V A I L A B I L I T Y - N T I S O A R N L

8710 Date 1978 010000 111110 32A000 329000 312000 551110^552210

713000 719BOO 793000 794000 795254 795320 810000 Methods for U.S. Shielding Calculations: Applications lo

FFTF and CRBR Designs. Engle, W.W.,Jr.; Mynatt, F.R.; Disney, R.K. CONF-781117-3 ,, A V A I L A B I L I T Y - D E P . , NTIS O A R N L

8793 Date February 1979 111110 32A000 329000 223000 719AOO 721100 722100


siderations. Simmons, G.L. ORNL/RSIC-43.PP.22-27;

ANS/SD-79/16,PP:22-27 A V A I L A B I L I T Y - N T I S , SCA

8797 Date February 1979 f i l l 10 329000 721100 722100 793000 719A00 610000

861000 853100 An Improved Streaming Analysis Technique:, Spherical

Harmonics Expansion of Albedo Data. Albert, T.E.; Simmons, G.L. ORNL/RSIC-43,PP.68-75;

ANS/SD-79/16,PP.68-75 A V A I L A B I L I T Y - N T I S •• SCA ~

8807 Date March 1979 111210 32A000 521130 522130 717100 793000 794000



M.J. O R N L / T M - 6 5 6 0 A V A I L A B I L I T Y - N T I S S4.50 O A R N L

8816 Date October 1978 111210 32A000 521130 717100 793000 794000 795254


tant Fuel Assembly from the Fusion-Fission Fuel Factory, S O L A S E - H .

Youssef, M.Z.; Conn, R;W.; Moses, G.A. U W F D M - 2 6 3 A V A I L A B I L I T Y - N U C L E A R ENGINEERING


324

U - W I

8819 Date March 1979 111110 32A000 521130 793000 795254 870090 870092 Analysis of a Water Moderated Critical Assembly with

, A N I S N - V I T A M I N C. Green, L. WFPS.TME-79-015 A V A I L A B I L I T Y - F U S I O N POWER SYSTEMS

DEPARTMENT, WESTINGHOUSE ELECTRIC CORPORATION, PJO. BOX 10864, PITTSBURGH, PENNSYLVANIA \\

WEE

8854 Date September 1978 010000 122100 122200 220000 312000 32A000 760000


Dose and Simulation of Tissue Response in Neutron Therapy. ,)

Pfister, G.; Hehn, G.; Mattes, M.; Friedlein, H.P. CONF-780921, PP.621-627 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL,

75775 PARIS CEDEX 16, FRANCE GERMAN

SAI - 121 -132 -4 -79 AVA ILAB IL ITY -SC IENCE APPLICATIONS, INC.,


SAI

8946 Date May 1978 111210 32A000 521130 522130 717100 793000 795254


tion Tokamak Hybrid Reactor. Chapin, D.L.; Chi, J.W.H.; Kelly, J.L. , CONF-780508,VOL.l, PP.230-238 AVAILABIL ITY-DEP. , NTIS WEE

8955 Date May 1978 111210 123000 210000 531000 532000 793000 794000


M A C K - I V . Abdou, M.A.; Gohar, Y. CONF-780508,VOL.l, PP.402-410 AVAILABIL ITY-DEP. , NTIS ARGONN

8885. .,. Date March 1979 111500 32AOOO 329000 551110,552210 853100 861000

795203 793000 C) The SAI/EPRI Albedo Information Library. Simmons, G.L. EPRI-NP-1017 ^ AVA ILAB IL ITY -SC IENCE APPLICATIONS, INC.,


SCA


Human Dosimetry Applications. Kaul, D.; Chen, S.; Jarka, R. SAI-121 - 132-1 AVA ILAB IL ITY -SC IENCE APPLIATIONS, INC.,


SCA


sure to Mixed LET Radiation. Kaul, D.

8962 Date April 1979 111 110 111600 210000 521230 719AOO 795254 861000



Simmons, G.L. EPRI-NP-1056 AVA ILAB IL ITY -SC IENCE APPLICATIONS,


SCA ,„ 11

902 8 Date August 1979 112710 329000 32AOOO 510000 750000 717000 793000


Induced Residual Activation Dose Rates. Barish, J.; Gabriel, T.A.; Alsmiller, R.G.,Jr. ORNL-5561 A V A I L A B I L I T Y - N T I S $6.00 OARNL

902 9 Date August 1979 111110 210000 717000 793000 810000 Calculated Irradiation Response of Materials Using Fission

Reactor (HFIR, ORR, and EBR- I I ) Neutron Spectra.

325

Gabriel, T.A.; Bishop, B.L.; Wiffen, F.W. •ORNL/TM-6361 A V A I L A B I L I T Y - N T I S S4.50 OARNL

9030. . . .' Date October 1978 111210 210000 32A000 52^130 717000 861000 862000


Reactor Neutronic Performance. Barnes, J.M.; Bishop, B.L.; Santoro, R.T.; Gabriel, T.A. ORNL/TM-6543 A V A I L A B I L I T Y - N T I S $4.00 OARNL


Electron - Beam - Fusion Microexplosi ves. Ragheb, M.M.H.; Moses, G.; Maynard, C.W. UWFDM-295 \ A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-


U - W I

9107 Date June 1979 111110 020000 32A000 325000 521130 795134 795266

713000 793000 794000 SPECTRA-IV, Benchmark Spectra Based on LIB-1V. Kidman, R.B. LA-7861 - M S A V A I L A B I L I T Y - N T I S LOASL

9146 Date September 1979 111210 32AOOO 717000 793000 795254 Neutronic Performance of Fusion Reactor Blankets with

Different Coolants and Structural Arrangements. Chao, J.; Mikic, B.B.; Todreas, N.E. NUCL. TECHNOLOGY, 45(2), 113-120 U - M A

9191 Date July 1979 111210 32AOOO 329000 793000 794000 717100 810000 Workshop Summaries for the Third US/USSR Symposium

on Fusion - Fission Reactors. Jassby, D.L. PPPL-1550 A V A I L A B I L I T Y - N T I S U 7 N J .-.T. -

326

919 2 Date May 10, 1977 111110 111210 112110 32AOOO 511110 512110 512210



Straker, E.A.; Gritzner, M.L.; Harris, L.,Jr.; Schanzler, L. S A I - 7 7 - 6 5 7 - L J A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, I N C ,


SCA

919 3 Date April 27, 1978 111110 111210 421130 430000 312000 32A000 522130

793000,795254 830000 NE-213 Detector Perturbations to Measured and Calcu-


Scott, W.H.,Jr.; Gritzner, M.L.; Albert, T.E.; Hagan, W.K.; Schanzler, L.



SCA


Library (ENDL-78) . Howerton, R.J. UCRL-50400, VOL.15, PT.E A V A I L A B I L I T Y - N T I S L A L L

u 9306 Date July 1979 111210 329000 521130 717000 793000 794000 795254


' Anisotropic Neutron Transport Problem and the Nitran System for Fusion Neutronics Applications. Part I.

Takahashi, A.; et al. KFK-2832/1 AVAILABIL ITY-KERNFORSCHUNGSZENTRUM


GERMAN


Reactor (FMSR). Burns, T.J.; White, J.R.

- II n o

O R N L / T M - 6 8 5 4 A V A I L A B I L I T Y - N T I S O A R N L

9326 Date 1978 111210 32A000 521130 522130 717000 793000 795254


Design Study, December 1978. Chi, J.W.H. (Ed.) W F P S - T M E - 1 0 6 A V A I L A B I L I T Y - F U S I O N POWER SYSTEMS

DEPT., WESTINGHOUSE"' ELECTRIC CORP., PENN.

WEE

9342 Date September 1977 111210 32AOOO 521130 522130 793000 795254 717000 Fusion Blankets for Catalyzed D - D and D - * * 3 H e Reac-

tors. Fillo, J.A.; Powell, J.R. E P R I - E R - 5 3 6 - S R , PP.57-67 A V A I L A B I L I T Y - B R O O K H A V E N N A T I O N A L LAB-


9438 Date October 1979 111210v329000 521130 717000 793000 794000 795254





9441 Date September 1979 112710 122100 610000 717000 793000 810000 G A M M O N Activation Library. Battat, M.E.; LaBauve, R.J.; Muir, D.W.i L A - 8 0 4 0 - M S . 6 '>, A V A I L A B I L I T Y - D E P . , NTIS, PC A03 /MF A01 LOASL

^ 9448 Date August 1979 ^ 111110 122310 32A000 521130 793000 794000 719A00



Jenquin, U.P.; Thompson, J.K.; Trapp, T.J.; Kottwitz, D.A.

NUREG/CR-0965; PNL-3071 AVA ILAB IL ITY-DEP. , NTIS, PC A05/MF A01 PANL

9532 , Date February 1979 111500 112B00 220000 32A000 551110 552110 552210


Function. Trubey, D.K.; Knight, J.R.; Bartine, D.E.; Pace, J.V.,III O R N L / T M - 6 6 3 4 A V A I L A B I L I T Y - N T I S $4.50 OARNL

9544 Date June 1979 111210 32AOOO 521130 717100 793000 795254 810000

870094 ° Paramctric Calculations of 239-Pu Breeding in Hybrid

Blankets With and Without Trit ium Breeding. Henderson, D.L.; Moses, G.A. UWFDM-334 A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-


U - W I

9561 Date August 1979 111400 112130 32A000 329000 731100 793000 795262 Nuclear Vulnerability Analysis of the X M - 1 Tank in an

Initial Nuclear Radiation Environment. Kinch, J.W.; Rainis, A.E. ARBRL-TR-02183 a A V A I L A B I L I T Y - D E F E N S E DOCUMENTATION


A R M Y

9562 Date August 1579 111400 112130 329000 795203 731100 793000 810000 Radiation Shielding Properties of Selected Materials. Rainis, A.E.; Kinch, J.W.; Bowers, G.A. ARBRL-TR-02187 A V A I L A B I L I T Y - D E F E N S E DOCUMENTATION


A R M Y

9563 Date July 1979 111400 112800 329000 32A000 551110 552110 552210


Tank and APRD Reactor Scenario. °

327

Rainis, A.E.; Kinch, J.W. A R B R L - M R - 0 2 9 3 4 A V A I L A B I L I T Y - D E F E N S E D O C U M E N T A T I O N

CENTER, C A M E R O N STATION, A L E X A N D R I A , V A 22314

A R M Y

,1V 9724 Date^January 1980 111500 329000 521110 853100 795203 793000 Neutron Spectra from Monoenergetic Source Neutrons


Hagan, W.K.; Simmons, G.L. NUCL. SCI. ENG., 73(1), 35-41 SCA

9765 Date December 1978 111210 32A000 795254 793000 521130 522130 717000

810000 870003 Thermal-Hydraulic and Neutronic Considerations for

Designing a Lithium-Cooled Tokamak Blanket. Mikic, B.; Todreas, N. COO-2431 -2 A V A I L A B I L I T Y - D E P . , NTIS, PC A 0 6 / M F A01 ° U - M A

9845 Date March 1980 112120 532000 719A00 793000 ^ T M I - 2 Decay Power: LASL Fission-Product and Acti-


England, T.R.; Wilson, W.B. LA-8041 - MS, REVISED A V A I L A B I L I T Y - N T I S « LOASL

9856 ." Date May 1980 111210 329000 424000 510000 795203 793000 810000 Calculation of Neutron Die-Away Times in a

Large-Vehicle Portal Monitor. Lillie, R.A.; Santoro, R.T.; Alsmiller, R.G:;Jr. O R N L / T M - 7 2 9 9 A V A I L A B I L I T Y - N T I S , PC A 0 3 / M F A01 O A R N L « "

9869 ->. Date September 1979 111210 32AOOO 521130 522130 717100 793000 795254 Blanket Design Study for a Commercial Tokamak Hybrid

Reactor (CTHR). .. Chapin, D.L.; Green, L.; Lee, A.Y.; Culbert, M.E.; Kelly,

J.L. W F P S - T M E - 7 9 - 0 2 1

A V A I L A B I L I T Y - F U S I O N POWER SYSTEMS DEPT., WESTINGHOUSE ELECTRIC CORPORA-T ION, PITTSBURGH, PA '

WEE

" 9897 Date January , 1980 111210 32A000 521130 717100 793000 795254 810000 Evaluation of DD and DT Fusion Fuel Cycles for Different

Fusion-Fission Energy Systems. Gohar, Y. A N L / F P P / T M - 1 3 2 „ "

<S) AVAILABILITY-NTIS, PC A03/MF A01 A R G O N N

9933 ^ Date May 1980 -111110 122110 12ff2i0 711100 793000 794000 810000 FCXSEC: Multigroup Cross-Section Libraries for

Nuclear Fuel Cycle Shielding Calculations. Ford, W.E.,III; Webster, C.C.; Diggs, B.R.; Pevey, R.E.;

Croff, A.G. O R N L / T M - 7 0 3 8 ; E N D F - 2 8 7 0


o 9979. Date May 1980 112120 122210 793000 810000 PEFPYD - A Library of Aggregate Fission-Product

Decay Data Derived from E N D F / B - I V . LaBauve, R.J.; George, D.C. L A - 8 3 6 5 - M S A V A I L A B I L I T Y - N T I S $4.00 LOASL

9991 Date August 1980 111110 122110 329000 711100 793000 794000 810000 KENO Calculations of Light ,Water Fuel Lattices. Hebert, M.J.; Handschuh, J.A.; Pilat, E.E.; Harris, D.R.;

Mayer, J.A. 0

O R N L / R S I C - 4 4 , PP.107-120 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 Y A A E C

Peripheral Shielding Routines Used


6463 Date Dec. 1977 122310 870041 870098 430000 794000 , Integral Tests of Niobium Cross Sections Through Simulta

c neous Measurements of Neutron and Gamma-Ray Leakage Spectra.

328 a




placement per Atom Cross-Sections to Different Secondary Neutron Energy and Angular Distributions and " In -Group" Weighting Schemes.

Gabriel, T.A.; Bishop, B.L. O R N L / T M - 6 1 0 8 A V A I L A B I L I T Y - N T I S $4.50 O A R N L



Arcipiani, B.; Palmiotti, G.; Salvatores, M. N U C L . SCL ENG., 65(3), 540-544 I T A L Y

6696 Date Apr i l 1978 111110 112120 221000 532000 422200 430000 794000






DancofT Factor of Spheres, Cylinders, and Slabs. Knight, J.R. O R N L / N U R E G / C S D / T M - 2 A V A I L A B I L I T Y - N T I S $6.00 O A R N L


Sections. Kidman, R.B.; MacFarlane, R.E.; Becker, M . L A - 7 L 9 L - M S

A V A I L A B I L I T Y - N T I S $8.00 LOASL

6880 Date July 1978 122310 870011 794000 Interactive Graphics Interpretation of Calculation Measure-


Parvez, A.; Becker, M. NUCL. SCL ENG., 67(1), 130-136 U - N Y

7009 Date September 1976 111210 32A000 721100 717000 794000 795254 795222





Neutronic Characteristics of a Fusion Reactor. Ide, T.; Seki, Y ; Iida, H. CONF-760935-P2, PP. 395-406 A V A I L A B I L I T Y - N T I S „ JAPAN

7133 Date October 1977 111220 421140 430000 794000 Least-Squares Dosimetry Unfolding: The Program Stay'sl. Perey, F.G. O R N L / T M - 6 0 6 2 ; ENDF-254 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8023 Date June 1978 111110 122110 511110 551110 713000'793000 794000

122310 E N D F / B - I V , L IB -1V, and the CSEWG Benchmarks. Kidman, R.B. L A - 7 3 5 5 - M S A V A I L A B I L I T Y - L O S A L A M O S SCIENTIFIC LAB.,


329

8033 Date August 1978 111110 230000 325000 551110 713000 887000 793000

794000 Preliminary Neutronic Study of Actinide Transmutation in

a Fast Reactor. Williams, M.L.; McAdoo, J.W.; Flanagan, G.F. O R N L / T M - 6 3 0 9 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8086 Date January 15, 1978 430000 794000 Effect of the Light Output Efficiency of Charged Particles

on an Unfolded Neutron Spectrum by an NE213 Organic Scintillator.

Sasamoto, N.; Tanaka, S. NUCL . INSTRUM. METHODS, 148(2), 395-397 ' JAPAN

8193 Date 1978 111110 122310 312000 32A000 521130 713000 794000 Uncertainties in the Breeding Ratio of a Large LMFBR. Marable, J.H.; Weisbin, C.R. CONF-780401 - 1 6 A V A I L A B I L I T Y - D E P . , N T I S O A R N L

8254 Date November 1978 122310 430000 794000 Development and Testing of Neutron Dosimetry Techniques

for Accelerator-Based Irradiation Facilities. Greenwood, L.R.; Heinrich, R.R.; Kennerley, R.J.; Medrzy-

chowski, R. NUCL. TECHNOLOGY, 41(1), 109-128 A R G O N N

8392 Date September 1, 1978 329000 422140 430000 794000 Absolute Neutron Flux Measurements Using an NE-110

Scintillation Counter. Renner, C.; Hi l l , N.W.; Morgan, G.L.; Rush, K.; Harvey,

J.A. NUCL. INSTRUM. METHODS, 154(3), 525-533 O A R N L

8401 Date July 1978 121100 121200 122110 122210 220000 531000 532000



Abdou, M.A.; Gohar, Y.; Wright, R.Q. A N L / F P P - 7 7 - 5 ,„

A V A I L A B I L I T Y - N T I S £6.00 A R G O N N

8403 Date March 1978 122110 122210 220000 531000 532000 793000 794000



Gohar, Y.; Abdou, M.A. A N L / F P P / T M - 1 0 6 A V A I L A B I L I T Y - N T I S $9.25 A R G O N N

8435 Date January 1979 111110 112930 122110 329000 32AOOO 325000 551110


ruptive Accidents. Tomlinson, E.T. O R N L / C S D - 3 5 A V A I L A B I L I T Y - N T I S $5.25 O A R N L

8481 Date January 1979 230000 793000 794000 717000 Preliminary Design and Neutronic Analysis of a Laser

Fusion Driven Actinide Waste Burring Hybrid Reactor. Berwald, D.H.; Duderstadt, J.J. NUCL . TECHNOLOGY, 42(1), 34-50 U - M I

8515 Date January 1979 111110 122110 32AOOO 521130 522130 794000 122210 Sample Problems for the Novice User of the A M P X - I I

System. Ford, W.E , I I I ; Roussin, R.W.; Petrie, L.M.; Diggs, B.R.;

Comolander, H.E. O R N L / C S D / T M - 7 2 ( A M P X - 7 ) A V A I L A B I L I T Y - N T I S $9.25 O A R N L


795276 717000 721100 793000 794000 861000 853100 Cross Section Sensitivity Analysis of a Proposed jNeutron




330

8518 Date January 1979 111210 122310 32AOOO 521130 551110 717000 793000



Seki, Y.; Santoro, R.T.; Oblow, E.M.; Lucius, J.L. O R N L / T M - 6 6 6 7 A V A I L A B I L I T Y - N T I S $4.00 O A R N L

8577 Date November 1978 111110 32AOOO 122310 312000 551110 551200 793000


8601 Date 1977 111110 421140 430000 794000 The Experimental Data Processing Program RADAK. McCracken, A.K.; Grimstone, M.J. EUR-5667E/F,PT. I , PP.358-374;



E N G L A N


ysis. Marable, J.H.; Weisbin, C.R. O R N L / R S I C - 4 2 , PP.25-48 A V A I L A B I L I T Y - N T I S O A R N L



NBS- ISNF . Broadhead, B.L.; Marable, J.H. O R N L / R S I C - 4 2 , PP.161-178 A V A I L A B I L I T Y - N T I S U - T N

8662 Date February 1979 11I I10 32AOOO 312000 421130 511110 870041 794000

793000 795254 795204

Sensitivity Analysis Applied to an Integral Test of Niobium Cross Sections.

Ingersoll, D.T.; Wehring, B.W. O R N L / R S I C - 4 2 , PP.179-189 A V A I L A B I L I T Y - N T I S O A R N L

8710 Date 1978 010000 111110 32A000 329000 312000 551110 552210

713000 719BOO 793000 794000 795254 795320 810000 Methods for U.S. Shielding Calculations: Applications to


8737 Date December 1978 430000 794000 WINDOWS: A Program for the Analysis of Spectral Data

Foil Activation Measurements. Stallmann, F.W.; Eastham, J.F.; Kam, F.B.K. O R N L / T M - 6 6 5 6 A V A I L A B I L I T Y - D E P . , NTIS O A R N L

8801 Date February 1979 111110 32A000 329000 721100 719A00 794000 795203


Containment. Hopkins, W.C. ORNL/RSIC-43,PP.127-136;

ANS/SD-79/16,PP.127-136 A V A I L A B I L I T Y - N T I S BECHTE

8807 Date March 1979 111210 32AOOO 521130 522130 717100 793000 794000


biotic Systems for Catalyzed DD and DT Reactors. Ragheb, M.M.H. ; Santoro, R.T.; Barnes, J.M.; Saltmarsh,


8816 Date October 1978 111210 32A000 521130 717100 793000 794000 795254


tant Fuel Assembly from the Fusion-Fission Fuel Factory, SOLASE-H .

331

Youssef, M.Z.; Conn, R.W.; Moses, G.A. UWFDM-263 A V A I L A B I L I T Y - N U C L E A R ENGINEERING


U - W I


sure to Mixed LET Radiation. Kaul, D. SAI -121 - 1 3 2 - 4 - 7 9 A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, INC.,'

1701 EAST WOODFIELD RD., SUITE 819, SCHAUMBURG, ILL . 60195

8955 Date May 1978 111210 123000 210000 531000 532000 793000 794000


M A C K - I V . Abdou, M.A.; Gohar, Y. CONF-780508,VOL. 1, PP.402-410 A V A I L A B I L I T Y - D E P . , NTIS ARGONN

9093 Date 1979 122110 32A000 794000 870079 Range Calculations Using Multigroup Transport Methods. Hoffman, T.J.; Robinson, M.T.; Dodds, H.L,Jr . CONF-790125-57 A V A I L A B I L I T Y - D E P . , NTIS O A R N L

9107 Date June 1979 1,11110 020000 32A000 32.5000 521130 795134 795266

713000 793000 794000 SPECTRA- IV , Benchmark Spectra Based on L I B - I V . Kidman, R.B. L A - 7 8 6 I - M S A V A I L A B I L I T Y - N T I S LOASL

9191 Date July 1979 111210 32A000 329000 793000 794000 717100 810000 Workshop Summaries for the Third US/USSR Symposium

on Fusion-Fission Reactors. Jassby, D.L. PPPL-1550 A V A I L A B I L I T Y - N T I S U - N J

9306 Date July 1979 111210 329000 521130 717000 793000 794000 795254



Takahashi, A.; et al. KFK-2832/1 A V A I L A B I L I T Y - K E R N F O R S C H U N G S Z E N T R U M


G E R M A N


Rcactor (FMSR). Burns, T.J.; White, J.R. O R N L / T M - 6 8 5 4 A V A I L A B I L I T Y - N T I S OARNL

9438 Date October 1979 111210 329000 521130 717000 793000 794000 795254



Takahashi, A.; Rusch, D. KFK-2832 / I I A V A l LAB IL ITY -KERNFORSCHUNGSZENTRUM



LAPHNGAS, M A C K - I V , and NJOY. Barrett, R.J.; Ford, W.E.,III; Gohar, Y.; Bohn, T.S.; Mac-

Farlane, R.E.; Boicourt, R.M. LA -8100 -MS; ENDF-288 A V A I L A B I L I T Y - N T I S LOASL

o 9448 Date August 1979

111110 122310 32A000 521130 793000 794000 719A00 861000 870094 '•>'

Integral Data Evaluation of Stainless Steel, 239-Pu, 240-Pu, and H /sub 2/ O for Homogeneous Plutonium Systems.

Jenquin, U.P.; Thompson, J.K.; Trapp, T.J.; Kottwitz, D.A. NUREG/CR-0965; PNL-3071 A V A I L A B I L I T Y - D E P , NTIS, PC A05 /MF A01 PANL

332

9527 Date September 1978 32A100 794000 A Method of Generating Multigroup Transfer Matrices

Using an Analytic Angular Integration Free of Trunca-tion Error.

Bucholz, J.A. N U R E G / C R - 0 2 9 5 A V A I L A B I L I T Y - N T I S $4.50 O A R N L



RESEARCH F O U N D A T I O N ECN, P.O. BOX 1, 1755 ZG PETTEN (NH) , T H E N E T H E R L A N D S

N E T H E R

9991 Date August 1980 111110 122110 329000 711100 793000 794000 810000 KENO Calculations of Light Water Fuel Lattices. Hebert, M.J.; Handschuh, J.A.; Pilat, E.E.; Harris, D.R.;

Mayer, J.A. O R N L / R S I C - 4 4 , PP.107-120 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 Y A A E C

General Survey of Shielding Materials


6205 Date October 1975 111700 112940 32A000 329000 521130 522130 712000

810000 795217 795254 795291 Shielding Analysis for the Sealed Storage Cask Concept. Zimmerman, M.G. BNWL-1953 A V A I L A B I L I T Y - N T I S BANW

9729 Date January 1980 430000 794000 Optimized Smoothing in Neutron Spectrum Unfolding by

the FERDOR Method. (Tech. Note) Johnson, R.H.; Wehring, B.W.; Doming, J.J. N U C L . SCI. ENG., 73(1), 93-97 U - I L

9763 Date 1979 111110 330000 719B00 794000 An Interface-Currents Integral Transport Model for

Treating Doubly Heterogeneous, Multisystem Geome-tries.

Westfall, R.M.; Bjerke, M.A. CONF-790402,VOL.11, PP.7-71 - - 7 - 8 3 A V A I L A B I L I T Y - H C - - A N S V I R G I N I A SECTION,

P.O. BOX 1260, L Y N C H B U R G , VA. 24505; M F — NTIS

O A R N L



Shirley, G.W. GA-A14635 A V A I L A B I L I T Y - N T I S S6.00 GEAC



Milosevicj, M.; Kocicj, A.; Altiparmarkov, D. I N I S - M F - 3 2 8 5 ( I N SERBIAN) A V A I L A B I L I T Y - I N S T I T U T Z A N U K L E A R N E

N A U K E BORIS KIDRIC, BELGRADE (YUGOSLA-V IA )

YUGOSL

9933. Date May 1980 111110 122110 122210 711100 793000 794000 810000 FCXSEC: Multigroup Cross-Section Libraries for

Nuclear Fuel Cycle Shielding Calculations. Ford, W . E , I I I ; Webster, C.C.; Diggs, B.R.; Pevey, R.E.;

Croff, A.G. O R N L / T M - 7 0 3 8 ; ENDF-287 A V A I L A B I L I T Y - N T I S O A R N L


717000 793000 795254 810000 861000 870003 Nuclear Performance Calculations for the E L M O Bumpy

Torus Reactor (EBTR) Reference Design. Santoro, R.T.; Barnes, J.M. O R N L / T M - 6 0 8 5 A V A I L A B I L I T Y - N T I S $4.50

333

OARNL

6499 Date 1976 111110 121100 122110 810000 Twenty-Seven Group Cross "Section Set Derived from

E N D F / B Library. Garg, S.B. B A R C - 8 9 2 A V A I L A B I L I T Y - D E P . , N T I S (U.S. SALES O N L Y ) I N D I A

6501 Date December 1977 010000 121100 810000 An Index to the Literature on Microscopic Neutron Data. I A E A C I N D A 76 /77-SUPPL.3 A V A I L A B I L I T Y - I A E A , V I E N N A I A E A

' %

6510. . : Date 1976 020000 111110 111210 111220 122100 122200 810000

845000 Basic Physical Data for Neutron Dosimetry. Broerse, J.J. (Ed.) EUR-5629 A V A I L A B I L I T Y - I N I S N E T H E R

6522 Date January 1978 111210 122110 122310 32AOOO 521130 717000 795042


Neutronics Data. (Thesis) Reupke, W.A. L A ; - 7 0 6 7 - T A V A I L A B I L I T Y - N T I S L O A S L

6593 Date 1978 111210 121100 810000 Analysis of Neutron Emission Spectra from 14 MeV Neu-

tron Reactions. Pearlstein, S. B N L - N C S - 2 4 0 6 6 A V A I L A B I L I T Y - N A T I O N A L N U C L E A R D A T A

C E N T E R , B R O O K H A V E N N A T I O N A L L A B O R A -T O R Y , U P T O N , N E W Y O R K 11973

B R O O K H

Van At ta, C.M. CONF-770107 , PP.9-29 A V A I L A B I L I T Y - N T I S L A L L

6600 Date 1977 010000 111220 717500 810000 Linear Accelerator Breeder for Energy Security. Steinberg, M . CONF-770107, PP.41-68

. A V A I L A B I L I T Y - N T I S B R O O K H

iv 6601 Date 1977

010000 111220 717500 810000 High Current Linear Accelerators and Nuclear Power. Tunnicliffe, P.R. CONF-770107, PP.69-84 A V A I L A B I L I T Y - N T I S C A N A D A v \ .

6602 Date 1977 010000 111220 717500 810000 Analysis of Accelerator Breeder Concepts wi th L M F B R ,

GCFR, and Molten Sa l t -Type Blankets. Mynatt , F.R. CONF-770107, PP.85-106 A V A I L A B I L I T Y - N T I S O A R N L


ment. A Technical Assessment. Scott, J.L. (Ch.) D O E / E T - 0 0 1 5 A V A I L A B I L I T Y - N T I S S6.50 DOE

6599 010000 111220 717500 810000 A Brief History of the M T A Project.

6609 Date December 1977 111110 210000 311000 32A000 551110 795276 719A00


of an L W R . Final Report (Research Project 827-2) . Livesay, R.B.; Wells, M.B. E P R I - N P - 6 1 7

Date 1977 A V A I L A B I L I T Y - R A D I A T I O N R E S E A R C H ASSOCI-ATES, INC.

R A R A

334

6612 Date December 1977 111110 010000 719B00 713000 810000 Shielding and Control Materials for the Gas-Cooled Fast/

Breeder Reactor. Simnad, M.T. G A - A - 1 4 4 7 8 A V A I L A B I L I T Y - N T I S $14.50 GEAC

6620 Date March 1978 112B00 121200 329000 810000 A New Method of Sampling the Klein-Nishina Probability

Distribution for A l l Incident Photon Energies Above 1 keV. (A Revised Complete Account).

Everett, .C.J.; Cashwell, E.D. ' J


<i 6623 Date 1977

111210 210000 32A000 795266 717000 810000 521130 Neutron Spectra Characteristics for the Intense Neutron

Source, INS. Battat, M. ; Dierckx, CL; Emigh, C.R.

, < ! L A - U R - 7 7 - 1054; C O N F - 7 7 0 5 2 3 - 2 A V A I L A B I L I T Y - D E P . , NT IS LOASL

6627 Date March 1978 122310 312000 521130 719A00 870092 870013 870001


for the T R X - 2 Thermal Lattice. Tomlinson, E.T.; Lucius, J.L.; Drischler, J.D. ORNL-5336 ; E N D F - 2 5 3 A V A I L A B I L I T Y - N T I S $8.00 O A R N L


Theory Neutronics Results for Perturbation Analyses. Vondy, D.R.; Fowler, T.B. O R N L - 5 3 7 6 A V A I L A B I L I T Y - N T I S $6.00 O A R N L

O A R N L

6657 Date November' 1977 111110 521130 551110 329000 795203 870090 870092

870093 810000 Monte Carlo Calculations of Time-Dependent Neptuni-



C O M M I S S I O N , RESEARCH E S T A B L I S H M E N T , LUCAS HEIGHTS

A U S T R A


mination. Boot, S.J. A E R E - R - 8 6 5 4 A V A I L A B I L I T Y - H . M . S . O . PRICE POUND1.50; NT IS



Fast-Reactor Structural Materials. Smith, A.; McKnight, R.; Smith, D. A N L / N D M - 4 1 A V A I L A B I L I T Y - N T I S A R G O N N


Standard Fast Reactor with the O S K A R - 7 5 System of Constants. 0

Bobkov, Yu.G.; Usachev, P.N. A N L - T R A N S - 1 0 8 6 ; FE I -659 ( I N RUSSIAN) A V A I L A B I L I T Y - N T I S RUSSIA

6630 Date Apri l 1978 010000 122100 810000 Status Report to the DOE Nuclear Data Committee. Perey, F.G.; Gentry, J.C. O R N L / T M - 6 3 3 8 A V A I L A B I L I T Y - N T I S $4.50

6667 Date 1977 111110 421140 430000 810000 Foil Activation Dosimetry at Energies Below 1 MeV. Stallmann, F.W.; Kam, F.B.K. CONF-771036 -5 A V A I L A B I L I T Y - D E P . , NT IS U - T N

335

6672 Date December 1977 112B00 112720 322000 328000 722100 795084 810000 Computer Program SCAP-BR for Gamma-Ray Stream-

ing Through Mult i-Legged Ducts. Byoun, T.Y.; Babel, P.J.; Dajani, A.T. CONF-771109-88 A V A I L A B I L I T Y - D E P . , NTIS BURNS

6697 Date March 1978 111110 121100 6100i)0 632200 810000 794000 SUPERDAN: Computer Programs for Calculating the

Dancoff Factor of Spheres, Cylinders, and Slabs. Knight, J.R. O R N L / N U R E G / C S D / T M - 2 A V A I L A B I L I T Y - N T I S 56.00 O A R N L (i o

6675 Date December 1977 111500 122100 810000 Tables of R C N - 2 Fission-Product Cross Sections, Evalu-

ation, Volume 2 (13 Nuclides). Gruppelaar, H. ' ECN-33 A V A I L A B I L I T Y - NETHERLANDS ENER G Y


NETHER

6676 Date February 1978 111110 122110 122310 325000 312000 521130 8.10000 Adjusted Neutron Spectra of STEK Cores for Reactivity



RESEARCH FOUNDATION (ECN), 3 WESTERDUINWEG, PETTEN (NH) , T H E NETH-ERLANDS

NETHER

6690 Date February 1978 111220 122110 32A000 421000 521130 551110 760000



6691 Date March 1978 111210 122110 521130 522130 717000 793000 810000 Riggatron Nucleonics: One-Dimensional Analysis. Wienke, B.R.; Dudziak, D.J.; Bosler, G.E. L A - 7 1 8 3 - M S A V A I L A B I L I T Y - N T I S LOASL Hj


Materials. u Swedjemark, G.A. SSI-1977-004 A V A I L A B I L I T Y - N T I S SWEDEN

o 6757 Date March 1977 122100 810000 Evaluations for the German Nuclear Data Library

K E D A K - 3 . Pt. l . Non-fissile Materials. Goel, B. (Comp.) KFK-2386 / I I A V A I L A B I L I T Y - I N S T . FUER NEUTRONENPHY-

SIK U N D REAKTORTEKNIK ; KERNFORSCHUNGSZENTRUM KARLSRUHE (GERMANY, F.R.)

G E R M A N


Sections. Kidman, R.B.; MacFarlane, R.E.; Becker, M. L A - 7 L 9 L - M S A V A I L A B I L I T Y - N T I S $8.00 LOASL

6768 Date October 1977 010000 111210 210000 717000 810000. Progress in Materials Research for Fusion Reactors. Kulcinski, G.L. UWFDM-228 " " A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,


U - W I

6769 Date March 1978 010000 111210 111220 210000 717000 810000 Intense Sources of Fast Neutrons. Barschall, H.H.

%

U W F D M - 2 3 1 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,


U - W I

6771'.' Date March 1978 111210 210000 717000 810000 First Wall and Divertor Plate Material Selection in Fusion

Reactors. Conn, R.W. UWFDM-237 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,


U - W I

6772 Date April 1978 111210 329000 793000 795203 717000 810000 Three Dimensional Neutronics Analysis of the Mir-


Ragheb, M.M.H.; Klein, A.C.; Maynard, C.W. UWFDM-239 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,


U - W I

6773 ° Date April 1978 010000 111210 717100 810000 Notes on Fusion Hybrid Reactors. Conn, R.W.; Moses, G.A.; Abdel-Khalik, S.I. UWFDM-240 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,


U - W I

6808 Date 1978 010000 111110 122200 210000 421140 430000 511120


Papers. Summary Report. Vlasov, M.F. (Ed.) IAEA-208, VOL.I, PP. l -49 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE IAEA

6815 Date 1978 010000 111110 122310 511120 810000 870092 870098

Review of Microscopic Integral Cross Section Data in Fun-damental Reactor Dosimetry Benchmark Neutron Fields.


IAEA-208, VOL.I, PP.233-263 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE HANFOR

6816 Date 1978 111110 122310 421140 511120 810000 870092 870098 Ratios of Measured and Calculated Reaction Rates for

Some Known Spectra. Zijp, W.L.; Nolthenius, H.J.; Baard, J.H. IAEA-208. VOL.I, PP.265-300 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE NETHER

f'v.-i i'Kj)

6824 Date 1978 010000 111110 421140 430000 810000 Foil Activation Detectors - Some Remarks on the Choice


McCracken, A.K.; Packwood, A. IAEA-208, VOL.I, PP.431-442 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE ENGLAN

6838 Date 1978 111110 410000 421140 511120 810000 Activation Foil Data for NISUS, MOL-sigma sigma and n 235-U Fission Spectrum. Hannan, A.H.M.A.; Williams, J.G. IAEA-208, VOL.11, PP.209-225 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE ENGLAN

6840 Date 1978 111110 421140 511120 810000 Spectrum Averaged Cross-Section Measurements in the

Fast Neutron Field of a Uranium Fission Plate. Najzer, M.; Rant, J. IAEA-208, VOL.11, PP.247-260 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE YUGOSL

337

6851 Date May 1978 010000 122200 810000 Compilations and Evaluations of Data on the Interaction of

Electromagnetic Radiation with Matter. Lorenz, A. (Comp.) I N D C ( N D S ) - 9 4 / L N A V A I L A B I L I T Y - I A E A NUCLEAR DATA SECTION,

KARNTNER RING 11, A-1010 V I E N N A IAEA

6859 Date June 1978 122200 810000 X - R a y Fluorescence Cross Sections for K and L X-Rays

of the Elements. Krause, M.O.; Nestor, C,W.,Jr.; Sparks, C.J.,Jr.; Ricci, E. ORNL-5399 A V A I L A B I L I T Y - N T I S $8.00 OARNL

A V A I L A B I L I T Y - S T I C H T I N G ENERGIEONDER-ZOEK CENTRUM NEDERLAND (ECN), VOORTZETTING V A N DE STICHTING REAC-TOR CENTRUM (RCN), WESTERDUINWEG 3, PETTEN (NH), THE NETHERLANDS

NETHER

6936 Date June 1978 122200 810000 e

Total Photon Absorption Cross Section Measurements, The-oretical Analysis and Evaluations for*Energies Above 10 MeV. ;

Gimm, H.A.; Hubbell, J.H. " NBS TN-968

AVAILAB IL ITY-SUPT. OF DOC., U.S. GOVERN-MENT PRINTING OFFICE, WASHINGTON, D.C. 20402 $2.40 o

NABS

6861 Date May 1978 111220 121100 123000 421150 810000 SIOB: A FORTRAN Code for Least-Squares Shape Fit-

ting Several Neutron Transmission Measurements Using the Breit-Wigner Multilevel Formula,

de Saussure, G.; Olsen, D.K.; Perez, R.B. ORNL/TM-6286 ; ENDF-261 A V A I L A B I L I T Y - N T I S $6.00 OARNL



6889. Date June 1978 010000 122100 810000 An Index to the Literature on Microscopic Neutron Data. IAEA CINDA 78 - SUPPL.4 TO CINDA 76/77 A V A I L A B I L I T Y - I A E A , AUSTRIA IAEA

6899 Date October 1977 111110 122110 421140 430000 521230 719AOO 795112

795233 810000 Neutron Metrology in the L.F.R. Neutron Flux Density 0 Spectrum in the Inner Graphite Reflector of the L.F.R.

Zsolnay, E.M. E C N - 7 7 - 134 (RESTRICTED DISTRIBUTION)

6937 Date June 1978 121200 810000 Comments on the Analysis of Total Photoabsorption Mea-

surements in the Energy Range 10 - 150 MeV. Maximon, L.C.; Gimm, H.A. NBSIR 78-1456 A V A I L A B I L I T Y - N A T I O N A L BUREAU OF STAN-

DARDS, DEPT. OF COMMERCE, WASHINGTON, D.C. 20234 $4.50

NABS

694 3 Date June 1978 111110 325000 551110 713000 810000 Test of the Diffusion Theory Difference Equations in Slab

Geometry (Computer Code VANCER). Vondy, D.R.; Fowler, T.B. ORNL-5381 A V A I L A B I L I T Y - N T I S $4.50 OARNL »

a

694 4 Date May 1978 111110,112120 210000 421200 719B00 810000 Distribution of Fission Products in Peach Bottom HTGR

Fuel Element F03-01. Dyer, F.F.; Wichner, R.P.; Martin, W.J.; Fairchild, L.L.

„ ORNL/TM-5996 A V A I L A B I L I T Y - N T I S $10.75 OARNL

6951 Date March 23, 1978 112200 810000 870092 Beta-Induced External Bremsstrahlung from Spent-Fuel

Fission Products. Stamatelatos, M.C1

0 338

S A I - 7 8 - 6 0 0 - L J A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, P.O.

BOX 2351, 1200 PROSPECT STREET, L A JOLLA, C A L I F O R N I A 92037

SCA

Condit, W.C,Jr.; Carlson, G.A.; Devoto, R.S.; Doggett, J.; Neef, W.

CQNF-760935-P1, PP. 107-117 A V A I L A B I L I T Y - N T I S L A L L

7000 Date September 1976 111210 717000 810000 Tokamak Experimental Power Reactor. Stacey, W.M,Jr . ; Abdou, M.A.; Bertoncini, P.J.; et al. CONF-760935-PI , PP. 21-45 A V A I L A B I L I T Y - N T I S A R G O N N

7001 Date September 1976 111210 7 1 7 0 0 0 8 1 0 0 0 0 General Atomic Company Experimental Power Reactor

Conceptual Design. Baker, C.C. CONF-760935-P1, PP. 47-58 A V A I L A B I L I T Y - N T I S

7002 Date September 1976 111210 717000)(810000 Results and Conclusions from O R N L Tokamak Experimen-

tal Power Reactor Conceptual Studies. Roberts, M. CONF-760935-PI , PP. 59-71 A V A I L A B I L I T Y - N T I S O A R N L

7003 Date September 1976 111210 717000 810000 TETR - A Tokamak Engineering Test Reactor to Qualify

Materials and Blanket Components for Early DT Fusion Reactors.

Kulcinski, G.L.; Conn, R.W.; Maynard, C.W.; et al. CONF-760935-P I , PP. 73-93 A V A I L A B I L I T Y - N T I S U - W I

7004 Date September 1976 111210 717000 810000 Tokamak Engineering Technology Facility. Stacey, W.M.,Jr.; Abdou, M.A.; Bolta, C.C.; et al. CONF-760935-P I , PP. 95-105 A V A I L A B I L I T Y - N T I S A R G O N N

7006 Date September 1976 111220 717000 810000 Studies of Catalyzed-D and D - * * 3 H e Fusion Reactor

System. Miley, G.H.; Southworth, F.H.; Choi, C.K.; Gerdin, G.A. , CONF-760935-P1, PP. 119-133 A V A I L A B I L I T Y - N T I S U - I L

7009 Date September 1976 111210 32A000 721100 717000 794000 795254 795222



7010 Date September 1976 111210 717000 810000 The Impact of Neutron Wall Loading on the Cost of a Toka-

mak Fusion Power System. Defreece, D.A.; Fuller, G.M.; Waganer, L.M. CONF-760935-P2, PP. 421-432 A V A I L A B I L I T Y - N T I S M C D O N N

7011 Date September 1976 010000 111210,717000 810000 What is Past is Prologue: Future Directions in Tokamak

Power Reactor Design Research. Conn, R.W. CONF-760935-P2, PP. 539-553 A V A I L A B I L I T Y - N T I S U - W I

7005 Date September 1976 111210 717000 810000 The Field Reversed Mirror as a Power Reactor.

7012 Date September 1976 010000 111210 717000 810000 Mirror Machine Reactors. Carlson, G.A.; Moir, R.W. 0

CONF-760935-P2, PP. 555-573 A V A I L A B I L I T Y - N T I S L A L L

339

701 3 Date September 1976 010000 111210 717000 810000 A Technology Assessment of Laser Fusion Power Produc-

tion. Booth, L.A.; Frank, T.G. CONF-760935-P2, PP. 575-589 A V A I L A B I L I T Y - N T I S LOASL

VJ. 701 4 Date September 1976

010000 111210 717000 810000 Technology Problems in Theta Pinch Reactors. Thomassen, K.I. CONF-760935-P2, PP. 591-599 A V A I L A B I L I T Y - N T I S LOASL

7015 Date September 1976 111210 717000 810000 Conceptual Design of the JAERI Demonstration Fusion

Reactor. Sako, K.; Tone, T.; Seki, Y.; et al. CONF-760935-P2, PP. 607-618 A V A I L A B I L I T Y - N T I S JAPAN

7016 Date September 1976 010000 111210 717000 810000 The Elmo Bumpy Torus Reactor. McAlees, D.G.; Uckan, N.A.; Bettis, E.S.; et al. CONF-760935-P2, PP. 619-628 A V A I L A B I L I T Y - N T I S O A R N L

7020 Date September 1976 111210 111110 329000 521130 522130 717000 810000 Neutronic Study of a Laser Fusion Hybrid Reactor Design. Hansen, L.F.; Maniscalco, J.A. CONF-760935-P2, PP. 677-688; UCRL-78069 A V A I L A B I L I T Y - N T I S L A L L

7021 Date September 1976 010000 111110 111210 717000 810000 Mirror Hybrids - A Status Report. Lee, J.D.; Bender, D.J.; Moir, R.W.; Schultz, K.R. CONF-760935-P2, PP. 689-710 A V A I L A B I L I T Y - N T I S GEAC

7022 Date September 1976 111110 111210 32A000 521130 717000 810000 870090


ket. Leonard, B.R,Jr.; Jenquin, U.P. < CONF-760935-P2, PP. 711-722 A V A I L A B I L I T Y - N T I S BANW

7024 Date September 1976 111110 111210 717100 810000 Some Systems Economic Considerations of Pure Fusion

Breeders of Fissile Nuclear Fuel. Bussard, R.W. CONF-760935-P2, PP. 741-755 A V A I L A B I L I T Y - N T I S ENGR

7017 Date September 1976 111210,717000 810000 Design Considerations for a Noncircular Tokamak Demon-

stration Plant. Kearney, D.; Bourque, R.; Chen, W.; et al. CONF-760935-P2, PP. 629-640 A V A I L A B I L I T Y - N T I S GEAC

7019 Date September 1976 010000 111110 111210 717000 810000 A Conceptual Design Study for a Laser Fusion Hybrid. Maniscalco, J.A. CONF-760935-P2, PP. 657-675 A V A I L A B I L I T Y - N T I S L A L L

7026 Date September 1976 111210 111110 717500 810000 Breeding of Fissile Fuel with Linear Fusion Sources. Oliver, D.; Cooper, B. CONF-760935-P2, PP. 775-786 A V A I L A B I L I T Y - N T I S PHIC

7027 Date September 1976 111110 111210 32A000 521130 717100 810000 793000

795254 Fusion-Fission Neutronics Calculations for the Laser Sole-

noid. ( I Woodruff, G.L.; Quimby, D.C. CONF-760935-P2, PP. 787-798 „ A V A I L A B I L I T Y - N T I S MASN

340 a

7028 Date September 1976 010000 111210 210000 32A000 329000 531000 532000


Reactors. Dudziak, D. i . CONF-760935-P3, PP. 819-832; L A - U R - 7 6 - 2 0 8 6 A V A I L A B I L I T Y - N T I S LOASL

7029 Date September 1976 111210 32A000 551110 552110 721100 717000 810000 Neutronic and Photonic Analysis of U W M A K - I I I Blanket

and Shield in Noncircular Toroidal Geometry. Gohar, Y.; Maynard, C.W.; Cheng, E.T. CONF-760935-P3, PP. 833-844 A V A T T A D I I I T V • M I - J O / v • n i i ^ n L t i i ^ i i a — i i t o

U - W I


tions in Tokamaks. Abdou, M.A.; Milton, L.J.; Jung, J.C.; Gelbard, E M . CONF-760935-P3, PP. 845-860, A V A I L A B I L I T Y - N T I S A R G O N N

7032 Date September 1976 111210 112120 230000 32A000 795217 795254 717000


kets Containing Sr -90 and 1-129. Parish, T.A.; Davidson, J.W.; Draper, E.L.,Jr. CONF-760935-P3, PP. 873-882 A V A I L A B I L I T Y - N T I S U - T X

7035 Date September^ 1976 111110 111210 521130 522130 717100 32A000 810000

793000 795254 Natural -Uranium Light-Water Breeding Hybrid Reac-

tors. Greenspan, E.; Schneider, A.; Fiiai, D.; Levine, P. CONF-760935-P3, PP. 1061-1073 A V A I L A B I L I T Y - N T I S ISRAEL

7042 Date September 1976 010000 111210 112760 223000 210000 521130 522130


Reactors.

Vogelsang, W.F. CONF-760935-P4, PP. 1303-1318; U W F D M - 1 7 8 A V A I L A B I L I T Y - NTIS U - W I

7043 Date September 1976 010000 111210 717000 810000 An Assessment of Blanket and Shield Technology. Twining, B.G.; Powell, J.R. CONF-760935-P4, PP. 1433-1446 A V A I L A B I L I T Y - N T I S BROOKH

7044 Date September 1976 111210 210000 717000 810000 Radiation Damage Analysis as Applied to Fusion Reactor


7050 Date September 1977 111210 122110 122210 32A000 312000 521130 522130

717000 810000 Cross-^Section Sensitivity Analyses for a Tokamak Experi-

mental Power Rcactor. Simmons, E.L.; Gerstl, S.A.W.; Dudziak, D.J. L A - 6 9 4 2 - M S A V A I L A B I L I T Y - N T I S $5.00 LOASL

7052 Date January 1977 112B00 122210 810000 Present Status of Photon Cross Section Data 100 eV to 100

GeV. Hubbell, J.H. NBS SPEC. PUB. 461, PP. 3 -16 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

WASHINGTON, D.C. 20402 NABS

7053 Date January 1977 112B00 121200 810000 Semiempirical Formulation of Coherent Scattering of

Gamma Rays. Roy, S.C.; Ghose, A.M. NBS SPEC. PUB. 461, PP. 17-19 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


341 it

7054 Date January 1977 112B00 121200 810000 Experimental Photoionization Cross Section of Gamma Ray

Photons for Low, Medium and High Z Atoms. Sinha (Goswami), B.; Chaudhuri, N. NBS SPEC. PUB. 461, PP. 20 -22 A V A I L A B I L I T Y - S U P T . OF D O C U M E N T S , GPO,


7055 Date January 1977 010000 121100 121200 810000 Radiation Physics and Nuclear Technology. Iyengar, P.K. NBS SPEC. PUB. 461, PP. 32 -40 A V A I L A B I L I T Y - S U P T . OF D O C U M E N T S , GPO,


7056 Date January 1977 112B00 121200 810000 Variation of Total to K - S h e l l Photoelectric Cross Section

Ratios with Atomic Number and Photon Energy. Gowda, R.; Sanjeevaiah, B'.

/ r ^NBS SPEC. PUB. 461, PP. 41 -43 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

W A S H I N G T O N , D.C. 20402 I N D I A °

7057 Date January 1977 111210 121100 810000 Optical Model Analysis of Non-Elast ic Interaction of 14.2

MeV Neutrons. ^ Pal, B.; Chatterjee, A.; Ghose, A .M . NBS SPEC. PUB. 461, PP. 44 -46 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


705 9 Date January 1977 121200 810000 Measurement of Angular Distribution of Incoherently Scat-

tered Gamma Rays from Atoms. Sinha (Goswami), B.; Chaudhuri, N . NBS SPEC. PUB. 461, PP. 55-56 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

W A S H I N G T O N , D.C. 20402*$ABSTRACT I N D I A

'J

706 0 Date January 1977 112200 810000 Intermediate Energy Approximation of B - H Formula for

the Bremsstrahlung Cross Sections.

Gopala, K.; Sanjeevaiah, B. NBS SPEC. PUB. 461, PP. 60-63 A V A I L A B I L I T Y - S U P T . OF D O C U M E N T S , GPO,


7067 Date January 1977 111500 121100 329000 810000 A Random Sampling Technique for Choosing Scattering



NBS SPEC. PUB. 461, PP. 100-105 A V A I L A B I L I T Y - S U P T . OF D O C U M E N T S , GPO,


7068 Date January 1977 010000 112B00 310000 522110 522210 610000 810000 Backscattering of Gamma Rays. Hyodo, T. „ NBS SPEC. PUB. 461, PP. 110-118 A V A I L A B I L I T Y - S U P T . OF D O C U M E N T S , GPO,

W A S H I N G T O N , D.C. 20402 J A P A N »

o 7071 v . Date January 1977

112BOO 329000 421200 522110 522210 810000 Backscattering of Gamma Rays by Barriers from Various

Media. Pozdneyev, D.B. u NBS SPEC. PUB. 461, PP. 129-131 A V A I L A B I L I T Y - S U P T . OF D O C U M E N T S , GPO,

W A S H I N G T O N , D.C. 20402 RUSSIA

7074 Date January 1977 010000 111110 32AOOO 325000 32F000 521l1l0 713000

810000" Neutron Transport Studies in Fast Reactor Shields. Vaidyanatjian, R.; Murthy, K.P.N.; Singh, R.S. NBS SPEC. PUB. 461, PP. 163-165 A V A I L A B I L I T Y ^ S U P T . OF D O C U M E N T S , GPO,

^ V A S H I N G T O ^ , D.C. 20402 => I N D I A

7076 Date January 1977 112BOO 632120 810000 Gamma Ray Buildup Factors for Finite Media. John, K.; Gopinath, D.V. NBS SPEC. PUB. 461, PP. 174-176 A V A I L A B I L I T Y - S U P T . OF D O C U M E N T S , GPO,

W A S H I N G T O N , D.C. 20402

342

a

INDIA

7085 Date January 1977 111110 329000 511110 521110 795171 795017 810000 Neutron Dose Evaluation Using Calculated Neutron Spec-


WASHINGTON, D.C. 20402 H U N G A R

7090 Date May 1977 111210 311000 329000 531000 532000 793000 717000



Santoro, R.T.; Tang, J.S.; Alsmiller, R.G,Jr.; Barnes, J.M. O R N L / T M - 5 8 7 4 A V A I L A B I L I T Y - N T I S $4.00 O A R N L

7100 Date July 1976 111110 122110 32A000 511110 810000 Using the Method of Subgroups to Allow for the Resonance

Structure of Cross-Sections in Computations of the Passage of Neutrons Through Plane Layers of Shielding.

Germogenova, T.A.; Isayev, N.V.; Nikolayev, M.N.; Khokhlov, V.F.


7104 Date July 1976 112B00 312000 552110 810000 Using Perturbation Theory for Problems Concerning Scat-

tered Gamma-Radiation. Petrov, E.Ye.; Shemetenko, B.P. E R D A - T R - 1 2 5 , PP. 54-72 A\RA TT AT r-k » r u i - r u RUSSIA

•=> 7105 Date July . 1976 111110 531000 532000 810000 Calculating the Temperature Field in Biological Shielding

by the Method of Electrothermal Analogy. Demeshev, R.S.; Rekshnya, N.F. E R D A - T R - 1 2 5 , PP. 73-78 A V A I L A B I L I T Y - N T I S RUSSIA

7106 Date July 1976 111110 32BOOO 521130 522130 620000 810000 Optimum Multilayer Shadow Shielding for a Reactor. Sakovich, V.A.; Sakharov, V.M. E R D A - T R - 1 2 5 , PP. 79-87 A V A I L A B I L I T Y - 1 9 7 6 RUSSIA

7109 ; .<>. Date July 1976 112B00 329000 722100 810000 Passage of Gamma-Radiation from Point Sources with an


Zolotukhin, V.G.; Yefimenko, B.A.; Klimanov, V.A.; Kochanov, V.A.; Mashkovich, V.P.; Orlov, N.Yu.


7111 Date July 1976 111110 421130 421200 521230 522230 710000 719AOO


the Novo-Voronezhskaya AES's Second Unit. Glushchenko, A.I.; Orlov, Yu.V.; Satarin, V.Ye. E R D A - T R - 1 2 5 , PP. 119-126 A V A I L A B I L I T Y - N T I S RUSSIA


Screens with Various Thicknesses. Yegorov, Yu.A.; Zharkov, V.P.; Oriov, Yu.V. E R D A - T R - 1 2 5 , PP. 157-168 0


7121 Date July 1976 111110 121100 122110 810000 Analysis of Complete Neutron-Matter Interaction Cross

Sections [n Nuclear Reactor. Yegorov, Yu.A.; Pankrat'yev, Yu.V.; Tolstykh, V.D. E R D A - T R - 1 2 5 , PP. 207-216 A V A I L A B I L I T Y - N T I S RUSSIA


with He**3-Spectrometer in Shield Materials. Yegorov, Yu.A.; Zharkov, V.P.; Orlov, Yu.V. E R D A - T R - 1 2 5 , PP. 225-230

343



Spectrometer by Monte Carlo Method. Yegorov, Yu.A.; Zharkov, V.P.; Orlov, Yu.V. E R D A - T R - 1 2 5 , PP. 231-239 A V A I L A B I L I T Y - N T I S RUSSIA

7129 Date March 1977 111130 111400 122110 122210 32A000 511110 512210

830000 853100 810000 Production and Testing of the DNA Few-Group Coupled

Neutron-Gamma Cross-Section Library. Bartine, D.E.; Knight, J.R.; Pace, J.V..III; Roussin, R. O R N L / T M - 4 8 4 0 A V A I L A B I L I T Y - D E P . , NTIS $5.50 O A R N L

7130 Date March 1977 111210 32A000 521130 522130 531000 532000 717000


Experimentation Power Reactor. Santoro, R.T.; Baker, V.C.; Barnes, J.M. O R N L / T M - 5 4 6 6 A V A I L A B I L I T Y - N T I S $4.50 O A R N L ,, „

8036 Date June 1978 111210 230000 717000 810000 Fusion Fuel Cycle Solid Radioactive Wastes. Gore, B.F.; Kaser, J.D.; Kabele, T.J. -PNL-2719 A V A I L A B I L I T Y - N T I S B A N W o


Laser Fusion Reactors. Kulcinski, G.L. U W F D M - 2 5 0 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,

NUCLEAR ENGINEERING DEPT., UN IVERSITY OF WISCONSIN, M A D I S O N , WISCONSIN 53706

U - W I

8114 Date August 1978 111110 122110 713000 810000 Preparation of Nuclear Data for Detailed Calculation of the

Neutron Spectrum in Fast Systems. Vozyakov, V.V.; Voropaev, A.I.; Abdullaev, Kh.Sh.; Voro-

tyntsev, M.F.; Van'kov, A.A.; Krivtsov, A.S.; Fivovaruv, V.A.

INDC(CCP) - 124/LV A V A I L A B I L I T Y - I A E A NUCLEAR D A T A SECTION,

K A R N T N E R R ING 11, A -1010 V I E N N A IAEA

7131 Date March 1977 020000 111110 122310 312000 32AOOO 810000 Compilation of Sensitivity Profiles for Several CSEWG Fast

Reactor Benchmarks. Marable, J.H.; Lucius, J.L.; Weisbin, C.R. ORNL-5262; ENDF-234 A V A I L A B I L I T Y - E R D A , TIC, P.O. BOX 62, O A K

RIDGE, T E N N . 37830 O A R N L

8115 Date February 1978 " 111110 122110 793000 810000 Multigroup and Few-Group Cross Sections for

E N D F / B - I V Fission Products; theTOAFEW Collaps-ing Code and Data File of 154-Group Fission-Product Cross Sections.

Wilson, W.B.; England, T.R.; LaBauve, R.J. L A - 7 1 7 4 - M S A V A I L A B I L I T Y - D E P . , NTIS LOASL

13025 Date July 1978 112930 "220000 222000 717000 810000 Application of Probabilistic Consequence Analysis to the




8127 Date July 4, 1978 111110 121100 810000 Program Linear (Version 78-1) ; Linearize Data in the

Evaluated Nuclear Data File/Version B(ENDF/B) Format.

Cullen, D.E. UCRL-50400, VOL.17, PT.A, REV.l A V A I L A B I L I T Y - N T I S L A L L

344

8128 Date July 4, 1978 111110 121100 810000 Program S I G M A 1 (Version 7 8 - 1 ) : Doppler Broaden Eval-

uated Cross Sections in the Evaluated Nuclear Data File/Version B ( E N D F / B ) Format.

Cullen, D.E. U C R L - 5 0 4 0 0 , VOL.17, PT.B, REV. l A V A I L A B I L I T Y - N T I S L A L L

8201 Date March 1975 111110 122110 713000 810000 Nuclear Data and Mult igroup Methods in Fast Reactor Cal-

culations. Gur, Y. I A - 1312; THESIS A V A I L A B I L I T Y - I S R A E L A T O M I C ENERGY C O M -

M I S S I O N I S R A E L


Thermonuclear Radiation (Part I). Hunter, T.O.; Kulcinski, G.L. U W F D M - 1 9 6 A V A I L A B I L I T Y - F U S I O N RESEARCH P R O G R A M ,

N U C L E A R E N G I N E E R I N G DEPT., U N I V E R S I T Y OF W I S C O N S I N , M A D I S O N , W I S C O N S I N 53706

U - W I

8130 Date October 1977 111110 111210 111220 121100 121200 531000 532000


nii.'ioar Radiation. Part I I . Transient Energy Deposition, Temperatures, and Displacement Rate.

Hunter, T.O.; Kulcinski, G.L. U W F D M - 2 1 7 A V A I L A B I L I T Y - F U S I O N RESEARCH P R O G R A M ,

N U C L E A R E N G I N E E R I N G DEPT., U N I V E R S I T Y OF W I S C O N S I N , M A D I S O N , W I S C O N S I N 53706

U - W I

8186 Date 1976 111110 210000 421140 810000 Damage Model and Neutron Spectrometry Applied in Reac-

tor Steel Irradiation Programmes. Weise, L. A E D - C G N F - 7 6 - 5 5 6 - 0 0 8 ( I N GEP.MA.N) A V A I L A B I L I T Y - I N I S ' -G E R M A N


Blanket. Perry, R.T.; McKinnon, M.A . ; Teofilo, V.L.: Aase, D.T. B N W L - S A - 6 4 2 0 ; C O N F - 7 7 1 0 2 9 - 2 2 1 A V A I L A B I L I T Y - D E P . , N T I S B A N W

8211 Date August 1978 123000 810000 The Nuclear Structure References (NSR) File. Ewbank, W.B. O R N L - 5 3 9 7 A V A I L A B I L I T Y - N T I S O A R N L

8214 Date October 1978 111210 32A000 329000 531000 532000 551110 552120


for the TFTR Neutral Beam Injectors. Santoro, R.T.; Li l l ie, R.A.; Alsmiller, R.G.,Jr.; Barnes, J.M. O R N L / T M - 6 3 5 4 ; C O N F - 7 8 0 6 2 2 - 2 9 A V A I L A B I L I T Y - N T I S $5.25 O A R N L

8222 Date May 17, 1978 122100 122200 810000 The L L L Evaluated Nuclear Data Library (ENDL) :

Descriptions of Individual Evaluations for Z = 0 - 9 8 . Howerton, R.J.; MacGregor, M .H . UCRL-50400 , VOL.15, PT.D, REV. l A V A I L A B I L I T Y - N T I S L A L L

8223 Date May 18, 1978 1 1 1 1 1 0 1 2 1 1 0 0 1 2 2 1 1 0 8 1 0 0 0 0 Bondarenko Self-Shielded Cross Sections and Mult iband

Parameters Derived from the I . L L Evaluat-ed -Nuc lea r -Da ta Library ( E N D L ) .

Cullen, D.E. UCRL-50400 , VOL.20 A V A I L A B I L I T Y - N T I S L A L L



Ragheb, M.M.H. ; Gohar, Y.M. ; Maynard, C .w .

345

UWFDM-192 A V A I L A B I L I T Y - F U S I O N T E C H N O L O G Y PRO-

GRAM, N U C L E A R E N G I N E E R I N G DEPT., UN IVERSITY OF WISCONSIN, M A D I S O N , WIS-CONSIN 53706

U - W I


nal-Source-Driven Multiplying Systems. Ragheb, M.M.H. ; Maynard, C.W. U W F D M - 2 6 5 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,

N U C L E A R E N G I N E E R I N G DEPT., UN IVERSITY OF WISCONSIN, MADISON, WISCONSIN 53706

U - W I )i

8274 Date August 1978 010000 123000 112120 810000 Status of Neutron Reaction Cross Sections of Fission Prod-

ucts in the Energy Range of Resolved and Unresolved Resonances.

Fort, E. IAEA-213 , PP. 139-218 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) FRANCE

8275 Date August 1978 010000 122310 112120 810000 Impact of Integral Measurements on the Capture

Cross-Section Evaluations of Individual Fission Prod-uct Isotopes.

Gruppelaar, H.; Dekker, J.W.M. IAEA-213 , PP.219-277 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) NETHER

8276 Dale August 1978 010000 111210 122310 810000 Status of Fast Neutron Reaction Cross Section of Fission

Products. Ii j ima, S. IAEA-213 , PP.279-350 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) JAPAN

8278 Date 1978 111210 32A000 329000 521130 522130 717000 810000 Scoping Nucieonic Studies for the Riggatron Fusion Reactor

Concept. Wienke, B.R.; Dudziak, D.J.; Bosler, G.E. L A - U R - 7 8 - 9 6 4 ; CONF-780508-5

A V A I L A B I L I T Y - D E P . , N T I S LOASL

8356 Date October 1977 717000 810000 Reactor Dosimetry Studies at the Coupled Fast Reactivity

Measurements Facility (CFRMF). Rogers, J.W.; Harker, Y.D.; Millsap, D.A.; Stepan, I.E. NUREG/CP-0004,VOL.3, PP.1237- 1249 A V A I L A B I L I T Y - N T I S U - W I

8373 Date January 1978 111110 111210 32A000 521130 717000 795254 810000 TCT Hybrid Preconceptual Blanket Design Studies. Aase, D.T.; Bampton, M.C.C.; Doherty, T.J.; Leonard, B.R.;



WEST LAB. BANW

8401 Date July 1978 121100 121200 122110 122210 220000 531000 532000



Abdou, M.A.; Gohar, Y.; Wright, R.Q. A N L / F P P - 7 7 - 5 A V A I L A B I L I T Y - N T I S $6.00 A R G O N N

8403 Date March 1978 122110 122210 220000 531000 532000 793000 794000



Gohar, Y.; Abdou, M.A. A N L / F P P / T M -106 A V A I L A B I L I T Y - N T I S $9.25 A R G O N N

8421 Date August 1978 111110 122310 521130 810000 Integral Determination of RP Neutron Cross Sections. Bustraan, M. IAEA-213 , VOL.11, PP.627-675 A V A I L A B I L I T Y - I A E A ( M F O N L Y ) NETHER

346


(Using the Baker Model). Voropaev, A.I.; Van'kov, A.A.; Tsybulya, A.M. I N D C ( C C P ) - 125/LV A V A I L A B I L I T Y - I A E A NUCLEAR DATA SECTION,

K A R N T N E R R I N G 11, A-1010 V I E N N A U - W I

8494 Date October 1, 1978 010000 121100 810000 An Index to the Literature on Microscopic Neutron Data. IAEA C I N D A 78 - SUPPL. 5 TO C I N D A 76/77 A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C

ENERGY AGENCY, V I E N N A IAEA

8459 Date October 1978 111210 112760 112930 220000 223000 521130 531000


mak Fusion Power Plant. Willenberg, H.J.; Bickford, W.E. PNL-2823 A V A I L A B I L I T Y - N T I S P A N L

8465 Date June 1978 111210 210000 717000 861000 870003 810000 Materials Considerations for Inertially-Confined Fusion

Reactors (ICFR). Hovingh, J. UCRL-81206 A V A I L A B I L I T Y - L A W R E N C E L I V E R M O R E LABO-

RATORY L A L L

8467 Date November 1978 111110 111210 329000 717100 795203 810000 Three-Dimensional Neutronics Analysis of the Solase-H

Laser Fusion Fissile-Enrichment-Fuel-Factory. Ragheb, M.M.H. ; Youssef, M.Z.; Abdcl-Khal ik , S.I.;

Maynard, C.W. U W F D M - 2 6 6 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,

XTT I P I r A n rvi^iMrnnrxir nrnT r txnurnrtTt; m j ^ L L A I ^ L-l^VJU"! L-L-lVll^VJ 1JCr 1 U1N1 Y CIVOt 1 I OF WISCONSIN, M A D I S O N , WISCONSIN 53706

U - W I


etry to 44 MeV, Greenwood, L.R. A N L / F P P / T M - 1 1 5 A V A I L A B I L I T Y - N T I S $4.50 A R G O N N

8495 Date 1977 111210 210000 717000 810000 Radiation Considerations for Superconducting Fusion Mag-

nets. Abdou, M.A. CONF-770649-6 A V A I L A B I L I T Y - N T I S A R G O N N

8496 Date January 1978 111210 329000 32A000 551110 552110 793000 717000


Engineering, Tri t ium and Neutronics. Project Staff - Argonne National Lab. G A - A14 614.VOL.V; A N L/FPP/77 - 6, VOL. V A V A I L A B I L I T Y - N T I S $8.00 GEAC

8509 Date July 1978 111110 312000 32A000 521130 795042 810000 Sensitivity Studies of One-Dimensional Neutronics Calcu-

lations for Prompt Burst Excursion (PBE) Experiments in the Annular Core Pulse Rcactor (ACPR).

Varela, D.W.; Williams, D.C. NUREG/CR-0262 ; SAND78-0143 A V A I L A B I L I T Y - N T I S S A N D I A

8514 Date February 1979 122110 122210 810000

r x i n r /r» \ r l - l i u i ' I u - r

* «..u: m u i u g i u u p Cross-Section Library for LMFBR Core and Shield, LWR Shield, Dosimetry, and Fusion Blanket Technolo-gy-

Weisbin, C.R.; Roussin, R.W.; Wagschal, J.J.; White, J.E.; Wright, R.Q.

ORNL-5505 ; ENDF-274 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8563 Date 1977 111210 32A000 521130 717000 795254 810000 A Practical Blanket Design for a Toroidal Fusion Reactor.

347

Bettis, E.S.; Barnes, J.M.; Huxford, T.J.; Liu, K.C.; Santoro, R.T.; Watts, H.L. ^

CONF-771029,VOL.11, PP.1453-1458 ' A V A I L A B I L I T Y - I E E E SERVICE CENTER, S INGLE


O A R N L

8566 Date 1977 111210 32AOOO 521130 717000 810000 795254 Design of the Blanket and Shield for a High-F ie ld Com-

pact Tokamak Reactor (HFCTR). Cook, D.L.; Lidsky, L.M.; Herring, S.; Stephany, W. CONF-771029,VOL.11, PP.1713-1717 A V A I L A B I L I T Y - I E E E SERVICE CENTER, S INGLE


U - M A

8567 Date 1977 111210 223000 521130 522130 717000 795217 795254

793000 810000 Structure Activation in an Experimental Power Reactor. Smith, R.D.; Parish, I".A. CONF-771029,VOL.11, PP.1718-1722 A V A I L A B I L I T Y - I E E E SERVICE CENTER, S INGLE


U - T X

85"6 Date November 1978 020000 010000 122100 122310 713000 810000 Nuclear Data Needs for Fast Breeder Reactor Shielding. Oblow, E.M.; Perey, F.G. CONF-781117-5 A V A I L A B I L I T Y - D E P . , NT IS O A R N L

8585 Date 1977 010000 111110 210000 421140 430000 713000 717000



McElroy, W.N.; Bennett, R.A.; Johnson, D.L. . EUR-5667E/F,PT. I , PP.1-26; CONF-750935,PT.I,

PP. 1 -26 A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L PUBLICA-

T IONS OF T H E EUROPEAN C O M M U N I T I E S , BOITE POSTALol003 - L U X E M B O U R G

WEE

8586 Date 19,77 010000 111110 210000 421140 713000 719A00 810000 Dosimetry Methods for Structural Material Irradiation in

the European Countries. Farinelli, U. EUR-5667E/F,PT. I , PP.27-40; CONF-750935,PT.I,



I T A L Y

8589 Date 1977 111110 210000 421140 32A000 551110 810000 Neutron Energy Spectrum Determination for Irradiation

Damage Study of Reactor Structural Materials. Takeuchi, K.; Miura, T.; Yamaji, A. EUR-5667E/F.PT.I , PP.63-73; CONF-750935,PT.I,



JAPAN

8591 Date 1977 111210 210000 421140 430000 717000.521130 795254



Odette, G.R. EUR-5667E/F,PT.I , PP.84-97; CONF-750935,PT.I,

PP.84-97 A V A I L A B I L I T Y - O F F I C E FOR OFF IC IAL PUBLICA-

TIONS ..OF T H E EUROPEAN C O M M U N I T I E S , BOITE POSTAL 1003 - L U X E M B O U R G

U - C A


P.esearch P.e?.ctor, Allen, E.J.; Kerr, H.T. EUR-5667E/F,PT. I , PP.414-423;



O A R N L

8612 Date 1977 111110 423240 531000 532000 810000 Dosimetry Methods for Structural Materials: Nuclear Heat-

ing.

348

Boyd, A.W. EUR-5667E/F.PT.I , PP.591-598;



C A N A D A

„ 8618 Date 1977 111110 210000 422110 423250 532000 713000 810000 Dosimetry Work in Connection with Irradiations in the High


de; Fabry, A.; Leenders, L.; Maene, N.; Menil, R. EUR-5667E/F,PT.I , PP.700-737;



FRANCE

862 0 Date 1977 111110 210000 422110 810000 870041 Application de la Reaction 9 3 - N b (n,n') 93m-Nb a la

Dosimetric des Irradiations de Materiaux. Lloret, R. EUR-5667E/F,PT.I , PP.747-756(IN FRENCH);



FRANCE

862 1 Date 1977 111110 210000 422110 810000 870041 Utilization of the Reaction 93 - Nb (n,n') 93m - Nb for Fast

Neutron Fluence Measurement. Hegedus, F. EUR-5667E/F,PT.I , 0 PP.757-762;



SWITZ


in the 10 M W Research Reactor HIFAR. Hilditch, R.J.; Lowenthal, G.C. EUR-5667E/F,PT. I , PP.791-807;

CONF-750935,PT.I, PP.791 -807 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-

T IONS OF T H E EUROPEAN COMMUNITIES, BOITE POSTAL 1003 - LUXEMBOURG

AUSTRA

8627 Date 1977 111110 210000 810000 Radiation-Induced Defect Production in Structural Mate-

rials at Reactor Temperatures. Beeler, J.R.,Jr.; Brudnoy, D.M.; Beeler, M.F. EUR-5667E/F,PT.I I , PP.1-23; CONF-750935,PT.II,

PP. 1-23 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


U - N C

8628 Date 1977 111110 210000 422110 551120 810000 795254 795209 Dosimetric Relative a des Irradiations d'Acier dans le Reac-

teur Melusine. Devillers, C.; Perdreau, R. EUR-5667E/F,PT.I I , PP.69-80(IN FRENCH);



FRANCE

8629 ''. . Date 1977 , 111110 122100 210000 810000 421140 Differential Neutron Data for Reactor Dosimetry. Paulsen, A.; Magurno, B.A. EUR-5667E/F,PT.I I , PP.93-111;



BELGIU

8631 Date 1977 111110 421140 810000 870098 Measurements of Integral Cross Sections in the Californi-

um—252 Fission Neutron Spectrum. Alberts, W.G.; Gunther, E.; Matzke, M.; Rassl, G. EUR-5667E/F,PT.I I , PP.131 -141;

CONF-750935,PT.II, PP.131 -141 A V A I L A B I L I T Y - O F F I C E FOR OFFIC IAL PUBLICA-

TIONS OF THE EUROPEAN COMMUNITIES, BOITE POSTAL 1003

G E R M A N LUXEMBOURG <'

8635 Date 1977 020000 111110 421140 551120 795209 810000 The Tapiro'Fast Source Reactor as a Benchmark to Test

Activation Detector Cross Sections.

349-

Martini, M.; Belli, M.; Sirito, M.F. EUR-5667E/F, PT.II,,. PP.259-276;

CONF-750935,PT:II, PP.259-276 A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-


I T A L Y

8636 Date 1977 111110 020000 32A000 421140 511120 713000 810000 Fast Neutron Spectrum and Dosimetry Studies in the Cou-

pled Fast Reactivity Measurements Facility. Rogers, J.W.; Harker, Y.D.; Millsap, D.A. EUR-5667E/F,PT.I I , PP.277-295;


TIONS OF THE EUROPEAN COMMUNITIES, BOITE FOSTAL 1003 - LUXEMBOURG

AEROJE

8651 Date February 1979 111110 122310 312000 325000 521130 810000 The Use of Cross-Section Sensitivities in the Analysis of,

Fast Reactor Integral Parameters. Collins, P.J.; Lineberry, M.J. 0 ,RNL/RSIC-42 , PP.13-23 A V A I L A B I L I T Y - N T I S A R G O N N

W \ 8653 Date'February 1979 111110 122310 32A000 521130 713000 810000 312000 Controlled Cross-Section Adjustment by Integral Data. Salmi, U.; Wagschal, J.J.; Ya'ari, A.; Yeivin, Y. ORNL /RS IC -42 , PP.49-59 A V A I L A B I L I T Y - N T I S ISRAEL

r8654 Date February 1979 111110 329000 312000 430000 551110 795203 810000 Sensitivity Analysis Applied to the Calculation of Detec-

tor-Response Kernels. Scott, W.H.,Jr.; McDaniel, P.J.; Renken, J.H.; Wright, S.A. ORNL /RS IC-42 , PP.61-74 A V A I L A B I L I T Y - N T I S SCA

8655 Date February 1979 111110 122310 719A00 810000 Sensitivity of Water Reactor Fuel Cycle Parameters and

Costs to Nuclear Data. Becker, M.; Harris, D.R.; Quan, B.; Ryskamp, J.M. ORNL /RS IC -42 , PP.75-87 ( i

A V A I L A B I L I T Y - N T I S

U - N Y

8658 Date February 1979 111110 122310 210000 421140 430000 521130 810000

870098 Testing of ENDF /B Cross-Section Data in the Californi-

um-252 Neutron Benchmark Field. Mannhart, W. ORNL /RS IC-42 , PP.119-133 A V A I L A B I L I T Y - N T I S G E R M A N


with Complete Covariance Capability. Schmittroth, F.° ORNL /RS IC-42 , PP.145-159 A V A I L A B I L I T Y - N T I S HANFOR

8661 Date February 1979 111110 122310 32A000 312000 210000 521130 810000

795254 794000 Sensitivity and Uncertainly Analysis Applied to the

NBS- ISNF. Broadhead, B.L.; Marable, J.H. ORNL/RSIC-42 , PP.161-178 A V A I L A B I L I T Y - N T I S U - T N o

866 3 Date February 1979 111210 122310 32AOOO 312000 521130 551110 717000


Fusion Reactor Design. Wu, T.; Maynard, C.W. ORNL/RSIC-42 , PP.191 -217; U W F D M - 2 9 0 A V A I L A B I L I T Y - N T I S U - W I

is 866 4 Date February 1979

111110 122310 32AOOO 312000 717000 810000 Uncertainty Analysis for Secondary Energy Distributions. Gerstl, S.A.W. ORNL /RS IC-42 , 219-229 A V A I L A B I L I T Y - N T I S LOASL o

8669 Dale February 1979 010000 020000 122310 810000 Expectations for E N D F / B - V Covariance Files: Coverage,

Strength and Limitations.

o 350

Perey, F.G. E N G L A N O R N L / R S I C - 4 2 , PP.311-318 A V A I L A B I L I T Y - N T I S O A R N L

8671 Date February 1979 111110 122310 719A00 810000 u , <•> Sensitivity of L W R Fuel Cycle Costs to Uncertainties in

Detailed Thermal Cross Sections. Ryskamp, J.M.; Becker, M.; Harris, D.R. O R N L / R S I C - 4 2 , PP.329-342 A V A I L A B I L I T Y - N T I S U - N Y

k , 8674 Date February 1979

111110 122310 32A000 312000 521130 713000 719A00 795204 795254 861000 810000

The Use of Error Files in Uncertainty Analysis and Data Adjustment.

Chestnutt, M.M. ; MCracken, A .K. O R N L / R S I C - 4 2 , PP.363-373 A V A I L A B I L I T Y - N T I S E N G L A N

8709 Date 1978 020000 111110 32AOOO 329000 551120 552220 713000

795254 795320 795203 810000 U.S. Integral and Benchmark Experiments. Maienschein, F.C. C O N F - 7 8 1 1 1 7 - 2 A V A I L A B I L I T Y - D E P . , NT IS O A R N L

8710 o Date 1978 010000 111110 32AOOO 329000 312000 551110 552210

713000 719B00 793000 794000 795254 795320 810000 Methods for U.S. Shielding Calculations: Applications to;

FFTF and CRBR Designs. Engle, W.W,J r . ; Mynatt , F.R.; Disney, R.K. C O N F - 7 8 1 1 1 7 - 3 A V A I L A B I L I T Y - D E P . , NT IS O A R N L ,

8681 Date October 31, 1978 122100 122200 810000 The L L L Evaluated-Nuclear-Data Library (ENDL) :

Graphs of Cross Sections from the Library. Howerton, R.J.; Cullen, D.E.; MacGregor, M.H. ; Perkins,

S.T.; Plechaty, E.F. UCRL-50400 , VOL. 15,PT.B,REV. 1 A V A I L A B I L I T Y - N T I S L A L L

8727 Daie 1977 111210 329000 717000 795203 810000 Three-Dimensional Analysis of the Effects of Penetrations

on Radiation Shielding of a Tokamak Fusion Reactor. Ide, T. J A E R I - M - 7 3 6 0 A V A I L A B I L I T Y - J A P A N A T O M I C ENERGY

RESEARCH INST ITUTE, T O K A I , J A P A N J A P A N

8682 Date October 31, 1978 122110 810000 Tabular and Graphical Presentation of 175 Neu-

t ron-Group Constants Derived from the L L L Evaluated-Nuclear-Data Library (ENDL) .

Plechaty, E.F.; Cullen, D.E.; Howerton, R.J.; Kimlinger, J.R..

UCRL-50400 , VOL.16,REV.2 ° A V A 1 L A B I L 1 T Y - N T I S

L A L L 0

o

8695 Date June 1978 111110 210000 421140 521230 713000 810000 The Zero-Power Basis of Fast Reactor Dosimetry. Sanders, J.E. A E E W - R - 1183 A V A I L A B I L I T Y - U K A E A , A T O M I C ENERGY--

E S T A B L I S H M E N T , W I N F R I T H , DORCHESTER, DORSET, GREAT B R I T A I N

8729 Date September 1978 111110 329000 810000 The Application of Artif icial Intelligence Techniques to the

Acceleration of Monte Carlo Transport Calculations. Macdonald, J.L.; Cashwell, E.D. L A - 7 4 7 5 A IF A TT A N I T M T I P r\ t n i i^nuiu i i i — m i to LOASL

0 8770 Date January 1979 P 1 1 1 U 0 122110 521 130 713000 810000

Comparison of Some Mult igroup Nuclear Data Sets on Existing Fast Neutron Assemblies.

Cuculeanu, V.; Mocioiu, D.; Constantinescu, D. I N D C ( R U M ) - 9 / G V

- - - A V A I L A B I L I T Y - I A E A N U C L E A R D A T A SECTION, K A R N T N E R R I N G 11, A - 1010 V I E N N A

R O M A N I

351-

8772 Date January 1979 122100 122200 810000 Summary Documentation of LASL Nuclear Data Evalua-

tions for E N D F / B - V . Young, P.G. L A - 7 6 6 3 - M S A V A I L A B I L I T Y - L O S A L A M O S SCIENTIFIC LABO-

RATORY, P.O. BOX 1663, LOS ALAMOS, NEW MEXICO 87545

LOASL

8801." Date February 1979 111110 32A000 329000 721100 719A00 794000 795203


Containment. Hopkins, W.C. . ORNL/RSIC - 43,PP. 127 -136;

ANS/SD -79/16,PP. 127 -136 A V A I L A B I L I T Y - N T I S BECHTE

8785 Date Apr i l 1979 112760 220000 795337 810000 845000 Dose-Rate Conversion Factors for External Exposure to

Photon and Electron Radiation' from Radionuclides Occurring in Routine Releases from Nuclear Fuel Cycle Facilities.

Kocher, D.C. NUREG/CR-0494; O R N L / N U R E G / T M - 2 8 3 A V A I L A B I L I T Y - N T I S O A R N L

8790 Date Apri l 1979 010000 111210 717100 810000 An Optimization of the Fission-Fusion Hybrid Concept. Saltmarsh, M.J.; Grimes, W.R.; Santoro, R.T. O R N L / P P A - 7 9 / 3 A V A I L A B I L I T Y - O A K RIDGE N A T I O N A L LABO-

RATORY, OAK RIDGE, TENNESSEE O A R N L

8802 Date February 1979 " 111110 32AOOO 551110 719A00 710000 721100 810000 A Low Pressure Drop Reactor Cavity Shield System. Klotz, R.J.; Cavanaugh, G.P.; Kassawara, R.P.;



8803 Date February 1979 111110 329000 710000 719A00 721100 795207 810000 Radiation Streaming and Reactor Cavity Shield Design at

TVA PWR Plants. Francis, C.C.; Galbreth, T.M.; Zobel, W. ORNL/RSIC-43 , PP.149-162;

ANS/SD-79/16,PP. 149-162 A V A I L A B I L I T Y - N T I S TVA

8794 Date February 1979 111110 223000 32A000 329000 719A00 721100 722100

795276 810000 Applications of Monte Carlo and Discrete Ordinales Tech-



8796 Date February 1979 111110 223000 32A000 521130 522130 551110 552210


Cavity Shield System. Celnik, J. ORNL/RSIC-43.PP.54-67;


880 4 Date February 1979 111110 329000 719AOO 721100 810000 Radiation Shielding for BWR Shield Wall Penetrations. Gillett, T.C.; Warkentin, J.K. ORNL/RSIC-43,PP. 163-177;

ANS/SD - 79/16,PP. 163 - 177 A V A I L A B I L I T Y - N T I S BRAUN

o

880 5 !fDate February 1979 111110 795144 710000 721100 719A00 810000 Shield Design Against Neutron Streaming in the Vicinity of

a BWR Pressure Vessel. <r

Seifferth, L.; Przibram, E.; Hock, R. ORNL/RSIC-43,PP.178-192;

ANS/SD-79/16,PP.178-192 A V A I L A B I L I T Y - N T I S G E R M A N

8807 Date March 1979 111210 32A000 521130 522130 717100 793000 794000

795254 810000 O

352-

Nuclear Performance of Molten Salt Fusion-Fission Sym-biotic Systems for Catalyzed D D and DT Reactors.

Ragheb, M . M . H . ; Santoro, R.T.; Barnes, J.M.; Saltmarsh, M.J.


8808 Date Apr i l 1979 111220 122100 810000 Status of E N D F / B - V Neutron Emission Spectra Induced

by 14 -MeV Neutrons. Hetrick, D.M.; Larson, D.C.; Fu, C.Y. O R N L / T M - 6 6 3 7 ; E N D F - 2 8 0 A V A I L A B I L I T Y - N T I S S4.50 O A R N L

Hep, J.; Valenta, V.; Veverka, O. ZJE -199 A V A I L A B I L I T Y - S K O D A WORKS, N U C L E A R

POWER C O N S T R U C T I O N DEPARTMENT, I N F O R M A T I O N CENTRE, P L Z E N - CZECHO-S L O V A K I A

C Z E C H O


nets. Abdou, M.A. J. N U C L . MATER. , 72(1-2) , 147-167 " A R G O N N

8811 Date October 1978 111220 329000 750000 795203 810000 Transport of Accelerator Produced Neutrons in a Concrete

Room. McCall, R.C.; Jenkins, T.M.; Shore, R.A. S L A C - P U B - 2 2 1 4 ; C O N F - 7 8 U 1 3 - 1 9 A V A I L A B I L I T Y - D E P . , N T I S STLAC

8837. . Date September 1978 010000 122100 810000 ° Nuclear Data for Reactor Design, Operation and Safety. Rowlands, J.L. CONF-780921, PP.7-27 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,


8812 Date December 7, 1978 122200 810000 Tables and Graphs of Photon-Interaction Cross Sections

from 0.1 keV to 100 MeV Derived from the L L L Evalu-a ted-Nuc lear -Data Library.

Plechaty, E.F.; Cullen, D.E.; Howerton, R.J. UCRL-50400 , VOL.6, REV.2 A V A I L A B I L I T Y - N T I S L A L L


810000 „ Neutronics Optimization Studies for a Proliferation Resis-

tant Fuel Assembly from the Fusion-Fission Fuel Factory, SOLASF. -H .

Youssef, M.Z. ; Conn, R.W.; Moses, G.A. U W F D M - 2 6 3 A V A I L A B I L I T Y - N U C L E A R E N G I N E E R I N G

D E P A R T M E N T , U N I V E R S I T Y OF WISCONSIN , M A D I S O N 53706

U - W I



883 8 Date September 1978 010000 122100 122200 810000 Nuclear Data for Reactor Shielding. Butler, J. CONF-780921, PP.28-60 A V A I L A B I L I T Y - O E C D , 2, R U E ANDRE-?, ! , -7CAL, I

75775 PARIS CEDEX 16, F R A N C E . / f ^ ' , E N G L A N a 4 o ' 0 o fi

883 9 Date September 1978 010000 122100 810000 Non-Prol i ferat ion and Nuclear Data. Sowerby, M.G. <-CONF-780921, PP.61-75 ^ A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,


8841 Date September 1978 010000 122100 122310 810000 Correlated Uncertainties in Integral Data. McCracken, A.K. CONF-780921, PP.116-135 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,


o

353

8842 Date September 1978 010000 122200 112400 112500 112600 810000 Photon Production in Neutron Induced Reactions, van Heerden, I.J. CONF-780921, PP.160-180 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, F R A N C E SAFRIC

8860 Date September 1978 111210 551110 71710d 870092 810000 Neutronic Studies of a 2 3 3 - U Fusion Breeder. Hansen, L.F.; Maniscalco, J.A. CONF-780921, PP.772-777 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, F R A N C E L A L L

8844 Date'September 1978 010000 122200 112710 810000 The U K Chemical Nuclear Data Files: An Evaluated Set of

Radioactive Decay Data for Reactor Applications. Davies, B.S.J.; Crouch, E.A.C.; James, M.F.; Nichols, A.L. ;

Parkinson, J.R.; Tobias, A.; Vallis, D.G. CONF-780921, PP.209-214 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,


8845 Date September 1978 010000 112710 122200 810000 Bibliotheque de Donnees Nucleaires non Neutroniques des

Isotopes Radioactifs, Produits de Fission et Noyaux Lourds. (

Blachot, J.; Fiche, Ch. i : CONF-780921, PP.215-222 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,



Nuclear Data Aspects. „ Kusters, H.; Lalovic, M. ; Wiese, W.H.


75775 PARIS CEDEX 16: FRANCF^ G E R M A N


Logging. Sanders, L.G. CONF-780921, PP.642-647 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,


8861 Date September 1978 010000 122310 521230 717100 810000 Neutron Data for the Hybr id Reactor Calculation. Markovskii, D.V.; Shatalov, G . E . ^ CONF-780921, PP.783-791 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

t75775 PARIS CEDEX 16, F R A N C E RUSSIA

886 4 Date September 1978 010000 122100 810000 Nuclear Data for Safeguards. Fuketa, T. CONF-780921, PP.922-940 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, F R A N C E JAPAN

O 886 5 Date September 1978^1

122310 713000 810000 Consequences des Incertitudes sur les Donnees de Base dans

les Calculs de Protection. Estiot, J.C.; Rado, V.; Salvatores, M.;-Trapp, J.P. CONF-780921, PP.9,93-998 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, F R A N C E FRANCE

886 6 Date September 1978 111110 422110 551120 719BOO 810000 Fast Neutron Dose in High-Temperature Gas-Cooled


Neef, R.D.; Druke, V.; Khamis, H.; Litzow, W. CONF-780921, PP. 1022-1027 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,


s 886 7 Date September 1978

111210 122310 32AOOO 521130 795254 717100 810000 870092

Reproduction of the Weale Experiment Results with Modi-fied E N D F / B - I V U - 2 3 8 Data.

354

o

Segev, M . ; Krumbein, A. CONF-780921 , PP.1028-1032 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, F R A N C E „ !

I S R A E L , ...

8888 Date June 1977 ,-,111110 121100 210000 810000 1 Diirriage Correlation in Theory and Practice.

pSraji; D.G.; Odette, G.R.; Simons, R.L.; Mansur, L.K. ^ K i u j j L - S A - 1144-A ; CONF-770641 - 9

\ y A l L A B I L I T Y - N T I S

8868 Date .September 1978, 111210 810000 Analysis,,of Neutrons Emitted from. 14 MeV Neutron;

Induced Reactions. , Pearlstein, S. s ' r ' ' CONF-780921 , PP.1059-1065 A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, F R A N C E BROOK H i ' ^

8894,

r V f i i l i ' M 1 0 3 2 9 0 0 0 717000 810000,,

Date February 1979

- /"i -. ^ ' i ^^V j ' . ^ncep tua l Design of the Fast-Linear Reactor ( F L R )

* Fusion Power. '' J i f o i ' i i ^ vW. ; Krakowski, R^A.; Mi l ler, R.L.

L A - 7 6 8 6 - M S A V A I L A B I L I T Y - N T I S L O A S L

8869 . . Date September 1978 010000 122100 717000 810000 O ." Nuclear Data for Fusion Reactors. ,, Jarvis, O.N. CONF-780921, PP.1073- 1087 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, F R A N C E E N G L A N t

„ 8906 Date October 17, 1978 121100 122100 810000 ^ -A C T L : Evaluated Neutron Activation Cross Sectiori'v

Library - - Evaluation Techniques and Reaction Index. Gardner, M.A. ; Howerton, R.J. UCRL-50400 , VOL.18 A V A I L A B I L I T Y - N T I S L A L L

«

8870 . Date September 1978 121100 410000 810000 Recent Advances in the Study of Some Neutron Threshold

Reactions. Qaim, S.M. .r CONF-780921 , PP.1088-1107 A V A l L A B I L I T Y - O E C D ^ 2, R U E ' A N D R E - P A S C A L ,


8875 Date 1979 111210 210000 717000 810000 852000 Radiation Damage in Diagnostic Windows for the TFTR. Primak, W. CONF-79ni?S_!2Q A V A I L A B I L I T Y - D E P . , NT IS A R G O N N

8908 Date May 26, 1978 111210 329000 717000 717100 810000 Nuclear Design of t h e ' L L L - G A U/sub 3 /S i Blanket. Lee, J.D. UCRL-80588 ; C O N F - 7 8 0 5 0 8 - 2 7 A V A I L A B I L I T Y - D E P . , NT IS L A L L „•. l?

8909 Date January 1979 111210 210000 717000 810000 Tokamak Reactors and Structural Materials. r

Conn, R.W. & U W F D M - 2 8 8 A V A I L A B I L I T Y - N U C L E A R E N G I N E E R I N G

D E P A R T M E N T , U N I V E R S I T Y , O b W I S C O N S I N , M A D I S O N , W I 53706 -

U - W I o

8876 Date 1979 010000 111210 210000 717000 810000 Effects of Irradiation on the Normal Metal of a Composite


Klabunde, C.E.; Coltman, R.R.,Jr.; Wil l iams, J.M. C O N F - 7 9 0 1 2 5 - 2 5 ' A V A I L A B I L I T Y - D E P . , N T I S O A R N L

8911 Date 1978 112710 122200 421140 810000 Gamma-Ray Spectra of. Neutron-I r radiated Activation

Detectors. Hogel, J. Z J E - 2 3 0 A V A I L A B I L I T Y - S K O D A * WORKS, N U C L E A R

POWER C O N S T R U C T I O N D E P A R T , I N F O R M A -T I O N CENTRE, P L Z E N - C Z E C H O S L O V A K I A

355- Q

CZECHO

8932 Date January 1979 010000 111210 121100 210000 521130 717000 795217


Structural Materials. Jarvis, O.N. AERE-R-9298 „ AVAILABIL ITY-H .M.S .O . .J^' ENGLAN v : - ; • / ' " ' ' ' ,

Zwilsky, K.M.; Cohen, M.M.; Finfgeld, C.R.; Reuther, T.C. CONF-780508,VOL.1, PP.549-553 'AVAILABIL ITY-DEP. , NTIS DOE

8946 Date May 1978 111210 32A000 521130 522130 717100 793000 .795254


tion Tokamak Hybrid Reactor. 0

Chapin, D.L.; Chi, J.W:H.; Kelly, J.L. ^ CONF-780508,VOL.1, PP.230-238 A V A l LABI L ITY - DEP., NTIS WEE " ;

8947 Date May 1978 111210 32AOOO 551110 552110 795276 717000 810000 A BWTR (Boiling Water Tokamak Reactor) Blanket Study. Sze, D.K.; Maynard, C.W.; Sviatoslavsky, I.N.; Cheng, " E.T.; Wang, C.C.; Wrazel, J. CONF-780508,VOL.1, PP.239-248 AVA ILAB IL ITY -DEP. , NTIS U - W I

8948 Date May 1978 111210 32A000 521130 717000 795042 810000 Nucleonic Aspects of the 'L INUS' Imploding Blanket.

vDudziak, D.J. CONF-780508,VOL.1, PP.254-261 AVA ILAB IL ITY-DEP. , NTIS LOASL i:>

8955 Date. May 1978 111210 123000 210000 531000 532000 793000 794000

810000 Computations of Nuclear Response Functions with C ' M A C K - I V .

Abdou, M.A.; Gohar, Y. ' 0

CONF-780508,VOL.1, PP.402-410, A V A I L A B I L I T Y - D E P , NTIS ARGONN

8956 . ; . . . . . Date May 1978 010000 U1210 210000 717000 810000_ Materials Program for Magnetic Fusion Energy.

8957 Date May 1978 111210 210000 810000 The Damage/Analysis and Fundamental Studies Program.

r '.Doran, D.G.;%i't',rar, ,H„ IV; Goland,"A.N.; Greenwood, ! L.R.; Heinrich, R.R.; Nolfi, F.V.; Odette, G.R.; Parkin, k.. D.M.; Reuther, T.C.; Robinson, M.T.; Smidt, F.A.; ?/ Spraquc, J.A.; Vandervoort, R.R.; Wilkes, P, CONF-780508,VOL.1, PP.575-587 A V A I L A B I L I T Y - D E P , NTIS HANFOR

8900 Date May 1978 111210 717000 810000 " N U M A K " An Attractive Medium Field, Medium Size,'

-> Conceptual Tokamak Reactor. Conn, R.W.; Kulcinski, G.L.; Maynard, C.W. CONF-780508,VOL.2, PP.1049-1059 A V A I L A B I L I T Y - N T I S ' <• 0 U - W I

8971 Date January 23, 1979 112720 422200 424000 719A00 810000 Neutron Shielding Requirements for the Loft^Densitome-

ters.'J

, Wheeler, F.J.; McCracken, R.T. ° L T R - 141-97 A V A I L A B I L I T Y - D E P , NTIS IDNEL w

8975 " , Date June 1979 111110 122110 122310 810000 :s ' Specifications for Adjusted Cross Section and Covariance


Weisbin, C.R1;; Marable, J.H.; Collings, P.J.; Cowan, C.L.; Peelle, R.W.; Salvatores. M.

ORNLr-5517 A V A I L A B I L I T Y - N T I S $5.25 OARNL

9006 Date June 1978 111110 325000 551110 719AOO 810000 A Nodal Method for Solving Transient Fewgroup Neutron

Diffusion Equations. Shober, R.A. A N L - 7 8 - 5 1 A V A I L A B I L I T Y - N T I S $6.00 « ARGONN

o

356 o

9029 " Date August 1979 111110 210000 717000 793000 810000 Calculated Irradiation Response of Materials Using Fission

Reactor (HFIR, ORR, and E B R - I I ) Neutron Spectra. Gabriel, T.A.; Bishop, B.L.; Widen, F.W. O R N L / T M - 6 3 6 1 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

9057 Date July 1979 111210 329000 521130 717000 7I7I00 793000 810000 Pellet and Pellet-Blanket Neutronics and Photonics for

Electron - Beam - Fusion Microexplosives. Ragheb, M.M.H.; Moses, G.; Maynard, C.W. U W F D M - 2 9 5 A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-


U - W I v

9069 Date Mid-December 1978 111210 210000 32A000 521130 810000 861000 717000

795323 Minimizing Radioactivity and Other Features of Elemental

and Isotopic Tailoring of Materials for Fusion Reactors. Conn, R.W.; Okula, K.; Johnson, A.W.

D NUCL. TECHNOLOGY, 41(3), 389-400; UWFDM-305

U - W I

9095 Date September 1976 111110 325000 551110 810000, Exact and Approximate Interior Corner Problem in Neutron

Diffusion by Integral Transform Methods. Bareiss, E.H.; Chang, K.S.J.; Constatinescu, D.A. COO-2280-28 A V A I L A B I L I T Y - N T I S U - I L

9110 Date August 1979 111110 32A000 329000 551110 552210 719B00 795320

795203 810000 Analysis of the ORNlT/TSF GCFR Grid-Plate Shield


Q •> 9123 Date July 1979

111210 32AOOO 329000 521130 522130 717000 795203 795255 795279 810000

ft

Preliminary Studies for the PDX Tokamak Radiation Shield Design.

Grimesey, R.A.; Nigg, D.W.; Scott, A.J.; Wheeler, F.J. TREE-1369 A V A I L A B I L I T Y - D E P . , NTIS $8.00 EDGERT

9124 Date June 1979 111600 810000 Atlas of Photoneutron Cross Sections Obtained with Mon-

oenergetic Photons. Supplement. Berman, B.L. UCRL-78482-SUPPLEMENT (PREPRINT) A V A I L A B I L I T Y - L A W R E N C E LIVERMORE LABO-

RATORY, UNIVERSITY OF CALIFORNIA, LIVF'. \MORE, CALIFORNIA 94550

LAL I

9126 Date 1979 112B00 121200 810000 Energy and Angular Distribution of Secondary Particles in

the Detection Media After the Interaction of Ionizing Radiation. Part One.

Okta, L.; Petr, I. U V V V R - 6 A V A I L A B I L I T Y - I N S T I T U T E FOR RESEARCH,

PRODUCTION A N D USES OF RADIOISOTOPES, PRAGUE 7, PRISTAVNI 24, CZECHOSLOVAKIA

CZECHO

9127 Date May 1979 1,11210 329000 717100 795203 810000 SOLASE-H - A Laser Fusion Hybrid Study. Conn, R.W.; Abdel-Khalik, S.I.; Moses, G.A.; Cooper,

G.W.; Howard, J.E.; Kulcinski, G.L.; Larsen, E.; May-nard, C.W.; Ragheb, M.M.H.; Sviatoslavsky, I.N.; Vogelsang, W.F.; Wolfer, W.G.; Ortman, M.; Smatlak, D.L.; Watson, R.; Youssef, M.Z.


GRAM, NUCLEAR ENGINEERING DEPT., UNIVERSITY„OF WISCONSIN, MADISON WI 53706

U - W I



dent Neutron Transport, Beranek, F.; et al. UWFDM-304 A V A I L A B I L I T Y - N U C L E A R ENGINEERING

DEPARTMENT, UNIVERSITY OF WISCONSIN, MADISON, WI

."> >j 357-

U - W I G E R M A N

9191 Date July 1979 111210 32A000 329000 793000 794000 717100 810000 Workshop Summaries for the Third US/USSR Symposium

on Fusion-Fission Reactors. Jassby, D.L. PPPL-1550 A V A I L A B I L I T Y - N T I S U - N J

922 9 Date August 13, 1979 111110 111220 329000 511110 521130 793000 810000 Data Testing Results for the L L L Evaluated Nuclear Data

Library ( E N D L - 7 8 ) . Howerton, R.J. UCRL-50400, VOL.15, PT.E A V A I L A B I L I T Y - N T I S L A L L j j

m 923 0 Date March 17, 1979

121100 810000 ^ Program S I G M A L (Version 79-1) : Doppler-Broaden

Evaluated Cross Sections in the Livermore-Evaluated Nuclear Data Library ( E N D L ) Format.

Cullen,°D.E. UCRL-50400, VOL.21, PT.C A V A I L A B I L I T Y - N T I S L A L L


Nuclear Data Aspects. Kusters, H.; et al. KFK-2833 A V A I L A B I L I T Y - K E R N F O R S C H U N G S Z E N T R U M

K A R L S R U H E , G M B H , K A R L S R U H E (F.R. GER-M A N Y )

G E R M A N 0

9310 Date August 1979 111210 32AOOO 521130 522130"717000 810000 The Reversed-Field Pinch Reactor (RFPR) Concept. Hagenson, R.L.; Krakowski, R.A.; Cort, G.E. L A - 7 9 7 3 - M S O A V A I L A B I L I T Y - N T I S L O A S L

//

9314 Date August 1979 111110 325000 551110 713000 793000 794000 810000 Preliminary Neutronic Analysis ora Fast Mixed-Spectrum

Reactor (FMSR). o

Burns, T.J.; White, J.R. 1

O R N L / T M - 6 8 5 4 ' A V A I L A B I L I T Y - N T I S O A R N L

9281 Date 1978 111500 121100 220000 810000 Influence of Nuclear Data on Calculations of Neutron

Energy Deposition. Caswell, R.S.; Coyne, J.J. EUR-5848,PP.29-43; CONF-770597,PP.29-43 A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L PUBLICA-

T IONS OF T H E EUROPEAN C O M M U N I T I E S , BOITE POSTALE 1003 - L U X E M B O U R G ISBN 9 2 - 8 2 5 - 0 2 5 6 - 2

NABS

9326 Date 1978 111210 32A000 521130 522130 717000 793000 795254

810000 Demonstration Tokamak Hybrid Reactor ( D T H R ) Blanket

Design Study, December 1978. Chi, J.'W.H. (Ed.)' W F P S - T M E - 106 A V A I L A B I L I T Y - F U S I O N POWER SYSTEMS

DEPT.,-, WESTINGHOUSE ELECTRIC CORP., PENN.

WEE

9306 Date July 1979 111210 329000 521130 717000 793000 794000 795254



Takahashi, A.; et al. K F K - 2 8 3 2 / 1 A V A I L A B I L I T Y - K E R N F O R S C H U N G S Z E N S E R U M

K A R L S R U H E GMBH, K A R L S R U H E (F.R. GER-M A N Y )




DIENSTSTELLE DER B U N D E S W E H R FUR A B C - S C H U T Z , D 3042 M U N S T E R , G E R M A N Y

G E R M A N

358-

9366 Date March 1979 122100 810000 Graphs of Neutron Cross Section Data for Fusion Reactor

Development. Asami, T.; Tanaka, S. J A E R I - M - 8 1 3 6 A V A I L A B I L I T Y - D I V I S I O N OF T E C H N I C A L

I N F O R M A T I O N , J A P A N A T O M I C ENERGY R E S E A R C H I N S T I T U T E , T O K A I - M U R A , N A K A - G U N , I B A R A K I - K E N , J A P A N

J A P A N

9383 Date 1977 111110 712000 713000 810000 Radiation Shield Design for L M F B R Spent-Fuel Shipping

Casks. Dupree, S.A. S A N D - 7 7 - 0 9 7 1 C ; C O N F - 7 7 1 1 0 9 - 6 8 A V A I L A B I L I T Y - N T I S S A N D I A

9386 Date August 1979 010000 111210 210000 717000 810000 A Crit ical Assessment of the Effects of Pulsed Irradiation on

Materials. Ghoniem, N.M. ; Kulcinski, G.L. U W F D M - 3 1 1 A V A I L A B I L I T Y - F U S I O N E N G I N E E R I N G PRO-

G R A M , N U C L E A R E N G I N E E R I N G DEPT., U N I V E R S I T Y OF W I S C O N S I N , M A D I S O N , W I 53706 'v-'

U - W I

9389. t Date October 1979 010000 111210 717100 810000 869999 A Brief Summary of Different Tr i t ium Sources for a Tr i t i -

umless Hybrid Reactor. Moses, G.A. U W F D M - 3 1 7 A V A I L A B I L I T Y - F U S I O N E N G I N E E R I N G PRO-

G R A M , N U C L E A R E N G I N E E R I N G DEPT., U N I V E R S I T Y OF WISCONSIN , M A D I S O N , W I 53706

U - W I

9421 Date 1977 111210 620000 710000 717000 810000 Neutral Beam System for an Ignition Tokamak. Fasolo, J.: Fuja, R.; Jung, J.; Moenich, J.; Norem, J.; Praeg,

W.; Stevens, H. C O N F - 7 7 1 0 2 9 - 1 7 7 " A V A I L A B I L I T Y - N T I S , PC AR2/MF, A01 A R G O N N ' i

9422 Date 1977 111210 620000 710000 717000 810000 Mechanical Design and Analysis for an EPR First

Wal l /Blanket/Shield System. Stevens, H.C.; Misra, B.; Youngdahl, C.K. C O N F - 7 7 1 0 2 9 - 1 9 4 A V A I L A B I L I T Y - N T I S , PC A 0 2 / M F A01 A R G O N N

9427 Date August 1979 111210 111220 210000 717000 810000 Fusion Technology Development. Coffman, F.E.(Dir.) D O E / E T - O l 16/1 A V A I L A B I L I T Y - U . S . DOE, OFFICE OF F U S I O N

ENERGY, D I V I S I O N OF D E V E L O P M E N T A N D T E C H N O L O G Y , W A S H I N G T O N , D.C. 20545

DOE

9432 Date October 1979 010000 122100 810000 v .. „

, W R E N D A 79/80. Wor ld Request List for Nuclear Data. Mui r , D.W. I N D C ( S E C ) - 7 3 / U R S F A V A I L A B I L I T Y - I A E A N U C L E A R D A T A SECTION,


9438 Date October 1979 111210 329000 521130 717000 793000 794000 795254


Anisotropic Neutron Transport Problem and the Nitran System for Fusion Neutronics Application. Part I I .


K A R L S R U H E ( G E R M A N Y , F.R.) G E R M A N

9441. . . ". Date September 1979 112710 122100 610000 717000 793000 810000 G A M M O N Activation Library. Battat, M.E.; LaBauve, R.J.; Mui r , D.W. L A - 8 0 4 0 - M S A V A I L A B I L I T Y - D E P . , NT IS , PC A 0 3 / M F A01 L O A S L


L A P H N G A S , M A C K - I V , and NJOY. Barrett, R.J.; Ford, W.E., I I I ; Gohar, Y.; Bohn, T.S.; Mac-

Farlane, R.E.; Boicourt, R.M.

c? 359

O

L A - 8 1 0 0 - M S ; E N D F - 2 8 8 A V A I L A B I L I T Y - N T I S L O A S L

9443 Date 1977 111220 210000 717000 810000 Jet Target Intense Neutron Source. Meier, K.L. L A - U R - 7 7 - 2 3 9 8 ; CONF-771029 -38 A V A I L A B I L I T Y - N T I S PC A 0 2 / M F A01 L O A S L

»

9483 Date 1979 -010000 111210 717000 717100 810000 Mirror Fusion Reactor Design. Neef, W.S.,Jr.; Carlson, G.A. CONF-790125, PT.A, PP.17-28; J. N U C L E A R


I N G C O M P A N Y - A M S T E R D A M L A L L

9484 Date 1979 010000 111210 717100 810000 Materials Implications of Fusion-Fission Reactor Designs. Schultz, K.R. CONF-790125, PT.A, PP.29-36; J. N U C L E A R


ING C O M P A N Y - A M S T E R D A M GEAC


Neutron Energy Effects. Goland, A .N . CONF-790125, PT.A, PP.453-461; J. N U C L E A R

M A T E R . , 85 A N D 86, A V A I L A B I L I T Y - N O R T H - H O L L A N D PUBL ISH-

I N G C O M P A N Y - A M S T E R D A M B R O O K H

9490. . . JJ. Date 1979 111220 122100 521230 717000 810000 Integral Tests of Nuclear Activation Cross Sections for

Be(d,n) Sources, E /sub d / = 1 4 - - 4 0 MeV. Greenwood, L.R.; Heinrich, R.R. CONF-790125, PT.A, PP.473-477; J. N U C L E A R


I N G C O M P A N Y - A M S T E R D A M A R G O N N

9491 Date 1979 111220 122100 121100 210000 717000 810000 Helium Accumulation Fluence Dosimetry for Fusion Reac-

tor Materials Irradiations. Kneff, D.W.; Farrar, H., IV CONF-790125, PT.A, PP.479-483; J. N U C L E A R


I N G C O M P A N Y - A M S T E R D A M ROI


Inertial Confinement Fusion Systems. Maniscalco, J.A.; Berwald, D.H.; Meier, W.R. CONF-790125, PT.A, PP.37-46; J. N U C L E A R


I N G C O M P A N Y - A M S T E R D A M L A L L


Their Implications. ° SchifTgens, J.O.; Simons, R.L.; Mann, F.M.; Carter, L.L. C01S1F-790125, PT.A, PP.491-495; J. N U C L E A R


I N G C O M P A N Y - A M S T E R D A M H A N F O R

9486 Date 1979 010000 111210 111220 210000 717000 810000 Irradiation Sources for Fusion Materials Development. Holmes, J.J.; Straalsund, J.L. CONF-790125, PT.A, PP.447-451; J. N U C L E A R

MATER. , 85 A N D 86, 0

A V A I L A B I L I T Y - N O R T H - H O L L A N D PUBLISH-I N G C O M P A N Y - A M S T E R D A M

H A N F O R

9497. . . . . '<> Date 1979 111210 210000 717000 810000 Predicting the Effects of Radiation upon the Constitution of

Fusion Reactor Materials. Gittus, J.H.; Miodownik, A.P. CONF-790125, < PT.A, PP.621-625; J. N U C L E A R

MATER. , 85 A N D 86, A V A I L A B I L I T V - N O R T H - H O L L A N D PUBLISH, .

I N G COMPAIN V A M S T E R D A M E N G L A N

360-

9541 Date August 1979 111210 717100 810000 Implementation Considerations of Coupling Dedicated Fis-

sile and Fusile Productions Fusion and Fusion Reactors. Ragheb, M . M . H . U W F D M - 3 0 9 A V A I L A B I L I T Y - F U S I O N E N G I N E E R I N G PRO-

G R A M , D E P A R T M E N T O F N U C L E A R E N G I N E E R I N G , U N I V . OF W I S C O N S I N , M A D I -SON, W I 53706

U - W I

9542 Date September 1979 111210 32AOOO 717000 521130 522130 810000 First Wa l l and Cavity Design Studies for a Light Ion Beam

Driven Fusion Reactor. Moses, G.A.; Abde l -Kha l i k , S.I.; Drake, D.; Engelstad,

R.L.; Kulcinski, G.L.; Lewis, R.; Lovell, E.; McCarvil le, T.; Peranich, L.; Peterson, R.R.; Ragheb, M.M.H. ; Spencer, R.

U W F D M - 3 2 0 A V A I L A B I L I T Y - F U S I O N E N G I N E E R I N G PRO-

G R A M , D E P A R T M E N T OF N U C L E A R E N G I N E E R I N G , U N I V . OF W I S C O N S I N , M A D I -SON, W I 53706

U - W I

9543 P Date October 1979 111210 717000 810000 ' O First Wal l Protection in ICF Reactors by Inert Cavity Gases. Moses, G.A.; Peterson, R.R. U W F D M - 3 2 3

v A V A I L A B I L I T Y - F U S I O N E N G I N E E R I N G PRO-~ G R A M , D E P A R T M E N T OF N U C L E A R

E N G I N E E R I N G , U N I V . OF W I S C O N S I N , M A D I -SON, W I 53706

U - W I

9544 Date June 1979 111210 32A000 521130 717100 793000 795254 810000

870094 v. Parametric Calculations of 239-Pu Breeding in Hybrid

Blankets Wi th and Without Tr i t ium Breeding. Henderson, D.L.; Moses, G.A. U W F D M - 3 3 4

' A V A I L A B I L I T Y - F U S I O N E N G I N E E R I N G PRO-G R A M , D E P A R T M E N T OF N U C L E A R E N G I N E E R I N G , U N I V . OF W I S C O N S I N , M A D I -SON, W I 53706

U - W I

9546 Date December 1979 010000 111210 717100 810000 Summary^of the Fusion-Fission Hybr id Fuel Cycle Analy-

sis (Trit iumless Hybrids?).

Moses, G.A. (Comp.) U W F D M - 3 3 7 A V A I L A B I L I T Y - F U S I O N E N G I N E E R I N G PRO-

G R A M , D E P A R T M E N T O F N U C L E A R E N G I N E E R I N G , U N I V . OF W I S C O N S I N , M A D I -SON, W I 53706

U - W I

9563 Date July 1979 111400 112800 329000 32A000 551110 552110 552210


Tank and A P R D Reactor Scenario. Rainis, A.E.; Kinch, J.W. A R B R L - M R - 0 2 9 3 4 A V A I L A B I L I T Y - D E F E N S E D O C U M E N T A T I O N

CENTER, C A M E R O N S T A T I O N , A L E X A N D R I A , V A 22314

A R M Y

9569. . . Date October 1979 010000 121100 810000 A n Index to the Literature on Microscopic Neutron Data. I A E A C I N D A 79 S U P P L E M E N T A V A l LA B I L I T Y - I N T E R N A T I O N A L A T O M IC

E N E R G Y A G E N C Y , V I E N N A I A E A



RESEARCH F O U N D A T I O N ECN, P.O. BOX 1, 1755 ZG P E T T E N ( N H ) , T H E N E T H E R L A N D S

N E T H E R

9575 Date August 1979 122100 123000 421150 810000 Nuclear Data Guide for Reactor Neutron Metrology. Part " 2: Fission Reactions. (1979 Edit ion) &

Zi jp, W.L.; Baard, J.H. c E C N - 7 1 A V A I L A B I L I T Y - N E T H E R L A N D S E N E R G Y

RESEARCH F O U N D A T I O N ECN, P.O. BOX 1, 1755 ZG P E T T E N ( N H ) , T H E N E T H E R L A N D S

N E T H E R

361-



RESEARCH FOUNDATION ECN, P.O. BOX 1, 1755 Z G PETTEN (NH) , THE NETHERLANDS

NETHER

9705 Date July 1979 122100 810000 Status of the Nuclear Data Library K E D A K - 3 . Goel, B.; Krieg, B. KFK-2386 / I A V A I L A B I L I T Y - K E R N F O R S C H U N G S Z E N T R U M

KARLSRUHE (F.R. GERMANY) , INSTITUT FUER NEUTRONENPHYSIK U N D REAKTOR-T E C H N I K

G E R M A N

9765 Date December 1978 111210 32A000 795254 793000 521,130 522130 717000

' 810000 870003 Thermal-Hydraulic and Neutronic Considerations for

Designing a Lithium-Cooled Tokamak Blanket. Mikic, B.; Todreas, N. COO-2431-2 A V A I L A B I L I T Y - D E P . , NTIS, PC A06 /MF A01 U - M A

9780 Date December 1979 010000 111210 122100 717000 810000

; Nuclear Data Requirements of the Magnetic Fusion Power Program of the United States of America. (Introductory Paper No. 1)

Head, C.R. IAEA-TECDOC-223 , PP. 1 - 7 A V A I L A B I L I T Y - M F O N L Y - IN IS MICROFICHE


DOE

0 9781 Date December 1979 010000 111210 122100 717000 810000 Nuclear Data Requirements for Fusion Reactor Design -

Neutronics Design, Blanket Neutronics and Tritium Breeding. (Review Paper No .A l )

Constantine, G. IAEA-TECDOC-223 , PP.11-29

A V A I L A B I L I T Y - M F O N L Y - INIS MICROFICHE CLEARINGHOUSE, IAEA, WAGRAMER-STRASSE 5, P.O. BOX 100, A-1400 V I E N N A , AUSTRIA

ENGLAN

9782 ; Date.December 1979 010000 111210 210000 717000 810000 Review of Nuclear Heating in Fusion Reactors. (Review

Paper No.A2) Seki, Y. IAEA-TECDOC-223 , PP.31-45 A V A I L A B I L I T Y - M F O N L Y - INIS MICROFICHE


JAPAN

978 3 Date December 1979 010000 111210 717000 810000 Nuclear Data Requirements for Transmutation and Activa-

tion of Reactor Wall and Structural Materials. (Review Paper No.A3)

Jarvis, O.N. IAEA-TECDOC-223 , PP.47-74 c

A V A I L A B I L I T Y - M F O N L Y - INIS MICROFICHE „ CLEARINGHOUSE, IAEA, WAGRAMER-STRASSE 5, P.O. BOX 100, A-1400 V IENNA, AUSTRIA

ENGLAN »

978 4 Date December 1979 010000 111210 122100 210000 717000 810000 Nuclear Data Needs for Radiation Damage Studies Rele-


Qaim, S.M. IAEA-TECDOC-223 , PP.75-89 A V A I L A B I L I T Y - M F ONLY - INIS MICROFICHE

CLEARINGHOUSE, IAEA, WAGRAMER-STRASSE 5, P.O. BjOX 100, A -1400 V IENNA, AUSTRIA

GERMAN


(Review Paper No.A5) Abdou, M.A. IAEA-TECDOC-223 , PP.91 - 110 A V A I L A B I L I T Y - M F ONLY - INIS MICROFICHE

CLEARINGHOUSE, IAEA, WAGRAMER-STRASSE 5, P.O. BOX 100,_A-1400 V I E N N A , AUSTRIA

362-

U - G A

9786 Date December 1979 010000 111210 717100 810000 122100 Neutron Data for Hybr id Reactor Calculations. (Review

P.aper N0 .A6) Markovskii, D.V.; Shatalov, G.E. I A E A - T E C D O C - 2 2 3 , PP.111-118 A V A I L A B I L I T Y - M F O N L Y - IN IS M I C R O F I C H E


RUSSIA

o9787 Date December 1979 010000 111210 312000 32A000 717000 810000 Cross-Section Sensitivity and Uncertainty Analysis for

Fusion Reactors - A Review. (Review Paper No .B I ) Dudziak, D.J. I A E A - T E C D O C - 2 2 3 , PP.121-138 A V A I L A B I L I T Y - M F O N L Y - IN IS M I C R O F I C H E


L O A S L

(i 9788 Date December 1979

010000 111210 122100 123000 717000 810000 Theoretical Approach to Nuclear Data Required for Fusion

Reactor Calculations. (Review Paper No.B2) Seeliger, D . , u

I A E A - T E C D O C - 2 2 3 , PP.139-152 A V A I L A B I L I T Y - M F ' O N L Y - IN IS M I C R O F I C H E

C L E A R I N G H O U S E , IAEA , W A G R A M E R -STRASSE 5, P.O. BOX 100 , 'A -1400 V I E N N A , A U S T R I A

. G E R M A N

978 9 Date December 1979 " 010000 111210 122100 122200 717000 717100 810000

Evaluated Files of Nuclear Cross Sections for Fusion Reac-tor Calculations. (Review Paper No.B3)

Bhat, M.R. I A E A - T E C D O C - 2 2 3 , PP.153-183 A V A I L A B I L I T Y - M F j O N L Y - IN IS M I C R O F I C H E


BROOKH

979 0 r V . . Date December 1979 010000 122100 717000 810000 Neutron Reaction Data in the MeV Range. (Review Paper

No.B4)

Liskien, H. I A E A - T E C D O C - 2 2 3 , PP.185-197 A V A I L A B I L I T Y - M F O N L Y - IN IS M I C R O F I C H E


BELGIU

9791 Date December 1979 010000 111210 122100 717000 810000 ' Q Status of 1 4 - M e V Neutron Cross Section Data. (Review

Paper N0.B6) Csikai, J. H I A E A - T E C D O C - 2 2 3 , PP.199-222 A Y A I L A B I L I T Y - M F O N L Y - IN IS M I C R O F I C H E


H U N G A R

9827 Date July 19 79 020000 122100 122200 810000 ° E N D F / B Summary Documentation. Kinsey, R. (Comp.) BNL-NCS-17541 (ED.3 ) ; ENDF-201(ED.3) A V A I L A B I L I T Y - D E P . , NT IS , PC A 2 2 / M F A01 BROOKH

9832 <>. . . Date May 1979 112120 122100 810000 Tables of R C N - 2 Fission-Product Cross Section Evalua-

tion. Volume 3. (Nd and Pm Isotopes). Gruppelaar, H. E C N - 6 5 A V A I L A B I L I T Y - D E P . , NT IS (U.S. SALES O N L Y ) ,

PC A 0 8 / M F A01 NETHER

9840 Date March 1980 111210 312000 32AOOO 521130 717000 795254 795204

810000 Sensitivity Analysis of Neutronics Calculations in the Pre-

liminary Design of J A E R I Experimental Fusion Reactor. (Revised)

Yamauchi, M.; Seki, Y.; Iida, H. J A E R I - M - 8 7 3 9 A V A I L A B I L I T Y - D I V I S I O N OF T E C H N I C A L

I N F O R M A T I O N , J A P A N A T O M I C ENERGY RESEARCH INSTITUTE, T O K A I - M U R A , N A K A - G U N , I B A R A K I - K E N , J A P A N

JAPAN „ 0

0

363 <D

0,

9855 Date May 1980 111110 312000 32A000 551110 552210 795204 795254


Gas-Cooled Fast Reactor (GCFR). Slater, C.O.; Tomlinson, E.T.; Williams, L.R. O R N L / T M - 7 2 4 6 A V A I L A B I L I T Y - N T I S , PC A 0 5 / M F A01 O A R N L

9856 Date May 1980 111210 329000 424000 510000 795203 793000 810000 Calculation of Neutron Die-Away Times in

Large-Vehicle Portal Monitor. Liliie, R.A.; Santoro, R.T.; Alsmiller, R.G.,Jr. O R N L / T M - 7 2 9 9 A V A I L A B I L I T Y - N T I S , PC A 0 3 / M F AO! O A R N L

9862 Date Apri l 1978 121200 122210 32A000 810000 Definition of Two Band Parameters for Use in Photon Trans-

port Calculations. Cullen, D.E. UC1D-17774 A V A I L A B I L I T Y - N T I S , PC A 0 2 / M F A01 L A L L

9866 Date September 1979 111210 717100 81000C.:» '', Minerals Resource Implications of a Tokamak Fusion Reac-

tor Economy. • ^ Cameron, E.; Conn, R.W.; Kulcinski, G.L.; Sviatoslavsky, I. U W F D M - 3 1 3 A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-

GRAM, NUCLEAR ENGINEERING DEPT., UNIV . OF WISCONSIN, MADISON, W I 53706

U - W I

9897 Date January 1980 111210 32AOOO 521130 717100 793000 795254 810000 Evaluation of DD and DT Fusion Fuel Cycles for Different

Fusion-Fission Energy Systems. Gohar, Y. A N L / F P P / T M - 1 3 2 A V A I L A B I L I T Y - N T I S , PC A 0 3 / M F A01 ARGONN

9900 Date 1978 111110 112120 322000 712000 795142 810000 Calculation of Gamma-Rays and Fast Neutrons Fluxes

with the Program MERCURE-4 . u

Baur, A.; Dupont, C.; Totth, B.

CEA-CONF-4493 ; CONF-7811158-1 A V A I L A B I L I T Y - N T I S (U.S. SALES ONLY) , PC

A 0 3 / M F A01 FRANCE

9933 Date May 1980 111110 122110 122210 711100 793000 794000 810000 FCXSEC: Multigroup Cross-Section Libraries for-

Nuclear Fuel Cycle Shielding Calculations. Ford, W.E.,111; Webster, C.C.; Diggs, B.R.; Pevey, R.E.;

Croff, A.G. O R N L / T M - 7038; ENDF-287 A V A I L A B I L I T Y - N T I S O A R N L

9937 Date March 1980 111210 717100 810000 Nuclear Development Needs for Fusion - Fission Hybrid

Reactors. Jassby, D.L. PPPL-1647 A V A I L A B I L I T Y - N T I S $4.00 U - N J

9978 Date May 1980 010000 329000 32A000 521130 810000 The Status of Monte Carlo at Los Alamos. Thompson, W.L.; Cashwell, E.D.; Godfrey, T.N.K.; .Sch-

randt, R.G.; Deutsch, O.L.; Booth, T.E. c

L A - 8 3 5 3 - M S ; ORNL/RSIC-44 , PP.231-246 A V A I L A B I L I T Y - N T I S $5.25 LOASL °

9979 .< Date May 1980 112120 122210 793000 810000 PEFPYD - A Library of Aggregate Fission-Product

Decay Data Derived from E N D F / B - I V . LaBauve, R.J.; George, D.C. LA-8365 - M S A V A I L A B I L I T Y - N T I S $4.00 LOASL

9986 Date August 1980 010000 111 110 111220 329000 713000 750000 810000 Monte Carlo Applications at Hanford Engineering Develop-

ment Laboratory. Carter, L.L.; Morford, R.J. ORNL/RSIC-44 , PP.7-30 » A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 HANFOR <; „

<S>

364-

9988 Date August 1980 010000 312000 329000 521130 81000U Monte Carlo Perturbation Theory in Neutron Transport

Calculations. Hall, M.C.G. O R N L / R S I C - 4 4 , PP.47-62 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 E N G L A N

10066 Date May 1980 122100 810000 Graphs of the Cross Sections in the Recommended Monte

Carlo Cross-Section Library at the Los Alamos Scien-tific Laboratory.

Soran, P.D.; Seamon, R.E. L A - 8 3 7 4 - M S A V A I L A B I L I T Y - N T I S $13.25 L O A S L

9991 Date August 1980 111110 122110 329000 711100 793000 794000 810000 K E N O Calculations of Light Water Fuel Lattices. Hebert, M.J.; Handschuh, J.A.; Pilat, E.E.; Harris, D.R.;

Mayer, J.A. O R N L / R S I C - 4 4 , PP.107-120 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 Y A A E C ° o

9997 Date August 1980 020000 329000 521130 795187 810000 T R X and UO/sub 2/ Benchmark Crit icality Calculations

with S A M - C E . Beer, M.; Troubetzkoy, E.S.; Lichtenstein, H.; Rose, P.F. O R N L / R S I C - 4 4 , PP.157-167 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 M A A G


Problems. Goldstein, M.; Greenspan, E. O R N L / R S I C - 4 4 , PP.169-187 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 ° O A R N L

10010 Date August 1980 111110 329000 711100 810000 Applicabil ity of Monte Carlo Code K E N O - I V . Yamakoshi, H. O R N L / R S I C - 4 4 , PP.345-349 A V A I L A B I L I T Y - N T I S , PC A ' l 6 / M F A01 J A P A N

10067 Date June 1980 122100 810000 0 Graphs of the Cross Sections in the AlternatecMonte Carlo

Cross Section Library at the Los Alamos Scientific Lab-oratory.

Seamon, R.E.; Soran, P.D. L A - 8 3 9 4 - M S A V A I L A B I L I T Y - N T I S $4.00 L O A S L


ited on the Ground. Beck, H.L. E M L - 3 7 8 A V A I L A B I L I T Y - D O E , N E W YORK, N.Y., ENVI -

R O N M E N T A L M E A S U R E M E N T S L A B O R A T O R Y

DOE

10146 Date August 1980 111210 122310 32A100 521130 717000 810000 SENSIT: A Cross-Section and Design Sensitivity and


Water


' r 10011 . . . Date July 1980 112120 112760 532000 795217 810000 887000 A User's Manual for the ORIGEN2 Computer Code. Croff, A.G. O R N L / T M - 7 1 7 5 A V A I L A B I L I T Y - N T I S , PC A 0 9 / M F A01 O A R N L

- 6468 Date Dec. 1977 111210 329000 511110 820000 853100 861000 Radiation Doses as a Function of Thickness and Shielding

Material Surrounding a 14 McV Neutron Source. Hansen, L.F.; Komoto, T.; Wong, C. CONF-770401, PP.881 -888 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR?, PR INCETON, NJ 08540^

365-

LALL

6472 Date Dec. 1977 112400 112500 512220 820000 861000 870082 Secondary Gamma Radiation Study in Reactor Shielding. Abagjan, A.A.; Gasnikov,'^-N.K.; Germogenova, T.A.;

Bubinin, A.A.; Zhuravlyov, V.L; Kolevatov, Yu.J.; Kurachenko, Yu.A.; Mashkovich, V.P.; Sakharov, V.K.



6544 Date December 1977 111110 020000 329000 719A00 820000 870092 Monte Carlo Analyses to T R X Slightly Enriched-H /sub

2/ O Critical Experiments with E N D F / B - I V and Related Data Sets. (AWBA Development Program).

Hardy, J.,Jr. W A P D - T M - 1 3 0 7 A V A I L A B I L I T Y - W E S T I N G H O U S E ELECTRIC

CORPORATION, BETTIS A T O M I C POWER DIVI -SION

BETTIS

6578 Date March 1978 111110 329000 421130 795203 511120 820000 A First-Order Approximation to Fast-Neutron Penetra-

tion Spectra for Non-Normal ly Incident Neutrons on Water Slabs. (Tech. Note)

Miller, W.H.; Hollabaugh, D.; Meyer, W. NUCL. SCL ENG., 65(3), 554-557 U - M O



Green, L.; Ullo, J.J. W A P D - T M - 1 3 6 5 A V A I L A 3 I L I T Y - N T I S BETTIS

6867 Date May 1978 111210 111220 422110 511120 795123 820000 Thermal Neutron Fluxes Produced in Water by Various Iso-

tope and Accelerator Neutron Sources. Holland, L.; Walker, J. NUCL. INSTRUM. METHODS, 151(1,2), 175-182 ENGLAN

o

6869 Date May 1978 112200 329000 512110 512210 820000 861000 870013



Nakamura, T.; Hirayama, H.; Shin, K. NUCL. INSTRUM. METHODS, 151(1,2), 277-284 JAPAN

6976:v Date August 1978 111110 122310 326000 511120 820000 870098 Spatial Distribution Measurements of Fission Neutrons in

Water as an Oxygen Data Test. Green, L.; Ullo, J.J. NUCL. SCL ENG., 67(2), 172-183 BETTIS

7073 Date January 1977 111110 540000 870001 870006 820000 Neutron Thermalization in Hydrogenous Moderators. Kothari, L.S. NBS SPEC. PUB. 461, PP. 149-162 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


7098 Date July 1976 111110 112110 112400 112500 325000 521130 522130

632110 820000 An Integrated Method of Calculating Reactor Shielding. Veselkin, A.P.; Gur'yeva, N.A.; Netecha, M.Ye; Nikit in,

A.V. E R D A - T R - 1 2 5 , PP. 6 - 1 0 A V A I L A B I L I T Y - N T I S RUSSIA

7099 Date July 1976 „ 112B00 111500 322000 330000 521130 522130 820000 Using Korobov's Method in Radiation Shielding Calcula-

tions. Gogotova, L.G.; Nikit in, A.V. E R D A - T R - 1 2 5 , PP. 11-16 A V A I L A B I L I T Y - N T I S RUSSIA



A.N.

366


7115 Date July 1976 112B00 421200 522210 610000 820000 870013 861000


Gamma-Quanta for Organic Mediums. Viktorov, A.A.; Mashkovich, V.P. E R D A - T R - 1 2 5 , PP. 152-15f> A V A I L A B I L I T Y - N T I S RUSSIA S

8034 Date August 1978 111110 220000 32A000 551110 552210 820000 861000


with Experimental Data. Santoro, R.T.; Alsmiller, R.G.,Jr.; Barnes, J.M. O R N L / T M - 6 4 0 1 / R 1 A V A I L A B I L I T Y - N T I S $4.00 O A R N L

8149 Date October 1978 540000 820000 Thermal-Neutron Steady-State Spectra in Pure and Poi-

soned Light Water Assemblies. (Tech. Note) Swaminathan, K.; Tewari, S.P.; Bansal, R.M. NUCL. SCL ENG., 68(1), 137-140 INDIA

8215 Date September 1978 112B00 121200 329000 820000

'A Monte Carlo Code (PHOEL) for Generating Initial Ener-gies of Photoelectrons and Compton Electrons Produced by Photons in Water.

Turner, J.E.; Modolo, J.T.; Sordi, G.M.A.A.; Hamm, R.N.; Wright, H.A.


0 " 8500 Date June 1977 111110 122110 324000 326000 327000 820000 861000

870013 870092 511110 521130 Moments of the Fourier -Transformed^ Neutron Slow-

ing-Down Kernel: The Computer Code "MAGGIE" . Gado, J.; Keresziuri, A. « KFKI -1977-44 A V A I L A B I L I T Y - K O Z P O N T I F I Z I K A I KUTATO

INTEZET, BUDAPEST'" ( H U N G A R Y ) ISBN 9633712637

H U N G A R

8688 Date March 1979 325000 540000 820000 882000 Neutron Diffusion in Water Containing 1 /v and Non - 1 /v

Absorbers. Bansal, R.M.; Tewari, S.P.; Kothari, L.S. N U C L . SCL ENG., 69(3), PP.367-374 I N D I A

8689 Date March 1979 112BOO 512110 632110 820000 861000 870082 Gamma-Ray Dose Rate Conversion and Buildup Factors.

(Tech. Note) Shure, K. NUCL . SCL ENG., 69(3), PP.432-436 " BETTIS

8920 Date May 1979 112BOO 512110 632110 820000 861000 870013 On the Polynomial Form of Gamma-Ray Buildup Factor

Functions. Metghalchi, M. NUCL. SCL ENG., 70(2), 207-209 I R A N

8993 Date February 1, 1979 111110 220000 511110 632110 820000 842000 853100 Depth-Dose Distribution for Fission Neutron Spectra

Degraded Through Low Z Shields. Singh, D.; Bisht, J.S.; Madhvanath, U. NUCL. INSTRUM. METHODS, 159(1), 229-234 I N D I A ,

9185 Date August 1979 112720 512110 329000 820000 User's Manual for PHOEL-2 , a Monte Carlo Computer



O R N L / T M - 6 9 5 4 A V A I L A B I L I T Y - N T I S $4.50 O A R N L o

9289 Date 1978 111220 220000 329000 421130 511120 820000 In-Phantom Neutron Spectrometry: A Comparison of

Experiment and Calculation. Harrison, K.G.; Taylor, A.J.; Holt, P.D.; Boot, S.J. EUR-5848,PP.411 -423; CQNF-770597,PP.411 -423

367-

A V A I L A B I L I T Y - O F F I C E FOR OFFIC IAL PUBLICA-T IONS OF T H E EUROPEAN COMMUNIT IES , BOITE POSTALE 1003 - LUXEMBOURG ISBN 92-825-0256-2

E N G L A N

Ci

9730 . Date January 1980 112B00 327000 512110 632110 820000 830000 861000 Photon Point Source Buildup Factors for Air , Water, and

Iron. (Tech. Note) Chilton, A.B.; Eisenhauer, C.M.; Simmons, G.L. NUCL. SCI. ENG., 73(1), 97-107 U - I L

Bartine, D.E.; Knight, J.R.; Pace, J.V.,III; Roussin, R. O R N L / T M - 4 8 4 0 A V A I L A B I L I T Y - D E P . , NTIS $5.50 O A R N L

8032 Date September 1978 111210 122100 312000 32A000 511110 512210 717000


Reactor Shielding Experiments. Seki, Y.; Santoro, R.T.; Oblow, E.M.; Lucius, J.L. ORNL-5467 A V A I L A B I L I T Y - N T I S $4.50 OARNL

Air




6706 Date October 10, 1977 111210 329000 4231,10 511120 521230 830000 861000 Dosimetry Measurements External to a 10 Kiloliter Liq-

u i d -A i r Vessel Containing a D - T Neutron Source. Tripler, D.J.; Goldberg, E.; Farley, W.E. UCRL-52334 A V A I L A B I L I T Y - D E P . , NTIS L A L L

6875 . Date June 1978 111210 421160 511120 512210 830000 Transport of Neutron and Secondary Gamma Radiations

Through a Liquid Air Sphere Surrounding a 14-MeV Neutron Source. (Tech. Note)


NUCL. SCI. ENG., 66(3), 428-433 L A L L

8116 .<•' Date July 1978 112130 121200 329000 512110 610000 830000 The Time Dependence of the Compton Current and Energy

Deposition from Scattered Gamma Rays. Malik, J.S.; Cashwell, E.D.; Schrandt, R.G. L A - 7 3 8 6 - M S ° A V A I L A B I L I T Y - L O S ALAMOS SCIENTIFIC LAB.,

P.O. BOX 1663, LOS ALAMOS, N E W MEXICO 87545

LOASL |

8197. . Date January 1976 111130 112 l20 ' l l2130 113100 512110 512210 632110

795179 830000 Version 4 of ATR (Air Transport of Radiation). Huszar, L.; Woolson, W.A.; Straker, E.A. DNA-3995F A V A I L A B I L I T Y - N T I S SCA 0

8565 Date 1977 111210 32A000 329000 511110 512210 830000 853100


Facility. Peng, W.H.; Celnik, J. CONF-771029,VOL.11, PP.1704-1706 A V A I L A B I L I T Y - I E E E SERVICE CENTER, S INGLE


BURNS

7129 Date March 1977 111130 111400 122110 122210 32A000 511110 512210

830000 853100 810000 Production and Testing of the DNA Few-Group Coupled

Neutron-Gamma Cross-Section Library.

•a

8736 Date March 1979 111400 112130 210000 32A000 521130 522130 551110


Point Sources Above an Air -Ground Interface. Lillie, R.A.; Santoro, R.T.

368-

O R N L / T M - 6 6 5 5 A V A I L A B I L I T Y - N T I S 54.50 O A R N L

SCA

9071 !.J Date 1977 111110 112110 122110 328000 329000 511110 512110"



T IONS GROUP, I N C , 3 WESTCHESTER PLAZA, ELMSFORD, N.Y. 10523

M A A G

9099 Date April l ^ S 112B00 329000 510000 512110 795166 830000 Time-Dependent Dose Rate and Compton Electron Gener-

ation from Mono-Energetic Gamma Sources in Homogeneous Air.

Engstrom, G. FOA RAPPORT C 20236-A2 A V A I L A B I L I T Y - F O R S V A R E T S FORSKNINGSAN-

STALT, N A T I O N A L DEFENSE RESEARCH INSTITUTE, S-104 50 STOCKHOLM 80, SWE-DEN

^ SWEDEN

9192 Date May 10, 1977 111110 111210 112110 32A000 511110 512110 512210



Straker, E.A.; Gritzner, M.L.; Harris, L„Jr. ; Schanzler, L. SAI - 7 7 - 657 - L J A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, I N C , ,

P.O. BOX 2351, 1200 PROSPECT ST , L A JOLLA, C A L I F O R N I A 92037-

SCA

9193 Date Apri l 27, 1978 111110 111210 421130 430000 312000 32A000 522130

793000 795254 830000 N E - 2 1 3 Detector Perturbations to Measured and Calcu-

lated Neutron and Gamma-Ray Fluences in Liquid Air .

Scott, W.H,J r . ; Gritzner, M.L.; Albert, T.E.; Hagan, W.K.; Schanzler, L.

S A I - 7 8 - 6 4 8 - L J r i K . , A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, I N C ,

P.O. BOX 2351, 1200 PROSPECT S T , LA JOLLA, C A L I F O R N I A 92037 " p ' r

9557 Date January 1980 112720 32AOOO 522120 795209 830000 Analysis of 60-Co Gamma-Ray Transport Through Ai r

by Discrete -Ordinates Transport Codes. Sasamoto, N.; Takeuchi, K. NUCL. TECHNOLOGY, 47(1), 189-199 JAPAN

9730 Date January 1980 U2B00 327000 512110 632110 820000 830000 861000 Photon Point Source Buildup Factors for Air, Water, and

Iron. (Tcch. Note) Chilton, A.B.; Eisenhauer, C.M.; Simmons, G.L. NUCL. SCI. E N G , 73(1), 97-107 U - I L ,,

Organic Material - Hydrocarbon ''


" A

8188 ) \ Date June 1978 111210 210000 717000 841000 842000 844000 The Effects of Radiation on Electrical Insulators in Fusion

Reactors. Phillips, D.C. A E R E - R - 8 9 2 3 A V A I L A B I L I T Y - N T I S E N G L A N


and Projected Reactors. Miley, G.H. NASA CONTRACTOR REPORT 3043 A V A I L A B I L I T Y - N T I S 0

NAASA U

. 8992 Date February 1, 1979 112760 422200 52221? 841000 853100 861000 870013

870082 Measurement of Number Albedo of Backscattered Photons. Biswas, M.; Sinha, A.K.; Roy, S.C. s

NUCL. INSTRUM. METHODS, 159(1), 157-162 IND IA

369-

9337 Date June 1979 210000 841000 842000 844000 Compilation of Radiation Damage Test Data. Part 1: Cable

Insulating Materials. Schonbacher, H.; Stolarz-lzycka, A. C E R N - 7 9 - 0 4 A V A I L A B I L I T Y - EUROPEAN O R G A N I Z A T I O N

FOR N U C L E A R RESEARCH (CERN), GENEVA CERN

Organic Material - Plastic


7069 Date January 1977 111110 32AOOO 423140 511110 511120 793000 795254

842000 870098 861000 870082 Transmission of 252-CF Fission Neutions Through Vari-


W A S H I N G T O N , D.C. 20402 N A V Y


and Projected Reactors. Miley, G.H. NASA CONTRACTOR REPORT 3043 A V A I L A B I L I T Y - N T I S N A A S A

(I t> »



Grant, W.H.; Otte, V.A. ° H E A L T H PHYS., 35(6), 807-816 U - T X

8993 Date February 1, 1979 11111,0 220000 511110 632110 820000 842000 853100

'Depth-Dose Distribution for Fission Neutron Spectra Degraded Through Low Z Shields.

Singh, D.; Bisht, J.S.; Madhvanath, U. NUCL. INSTRUM., METHODS, 159(1)^ 229-234 ,. I N D I A „ „.

8032 Date September 1978 111210 122100 312000 32A000 511110 512210 717000


Reactor-Shielding Experiments. Seki, Y.; Santoro, R.T.; Oblow, E.M.; Lucius, J.L. ORNL-5467 A V A I L A B I L I T Y - N T I S S4.50 „ ,v 0

O A R N L o

8188 Date June 1978 n 111210 210000 717000 841000 842000 844000' The Effects of Radiation on Electrical Insulators in Fusion

Reactors. u Phillips, D.C. A E R E - R - 8 9 2 3 A V A I L A B I L I T Y - N T I S j

• E N G L A N q 1'


Storage Safe, a Transport Vessel and a Portable Shield, for/Californium-252. (Notes)

Sharma, S.C.; Hood, J.T. H E A L T H PHYS., 35(3), 496-498 U - M N ^

9290 < • Date 1978 111220 220000 421140 421200 760000 842000 845000 Determination of Neutron and Gamma Spectra in a Mixed

(n, gamma)-Field. Schmidt, R.; Magiera, E. EUR - 5848,PP.443-454; CONF-770597,PP.443-454 A V A I L A B I L I T Y - O F F I C E FOR OFF IC IAL PUBLICA-

T IONS OFoTHE EUROPEAN C O M M U N I T I E S , BOITE POSTALE J003 - L U X E M B O U R G ISBN

,, 92]-825-0256-2 G E R M A N

£337 Date June 1979 210000 841000 842000 844000 Compilation of Radiation Damage Test Data. Part 1: Cable

Insulating Materials. Schonbacher, H.; Stolarz-lzycka, A. C E R N - 7 9 - 0 4 " A V A I L A B I L I T Y - E U R O P E A N ORGANIZAT ION,

FOR NUCLEAR RESEARCH (CERN) , GENEVA CERN

10015 Date June 1980 111110 311000 32A000 329000 511110 842000 870094


mated Beams «of Particles Using One-Dimensional Adjoint Transport Techniques.

O

370-

Dupree, S.A. S A N D - 8 0 - 0 4 3 2 A V A I L A B I L I T Y - S A N D I A N A T I O N A L LABORATO-

RIES, A L B U Q U E R Q U E , N M , T H E O R E T I C A L DIV.

S A N D I A

Organic Material - Wood o


8530 Date December 1978 111220 422140 511120 843000 842000 861000 Shielding for Neutron Radiotherapy Sources Created t . th'*-


Grant, W.H.; Ottc, V.A. H E A L T H PHYS., 35(6), 807-816 U - T X

Organic Material - Other Cf


8188 Date June 1978 111210 210000 717000 841000 842000 844000 The Effects of Radiation on Electrical Insulators in Fusion

Reactors. " Phillips, D.C. A E R E - R - 8 9 2 3 A V A I L A B I L I T Y - N T I S E N G L A N


and Projected Reactors. u Miley, G.H.

N A S A C O N T R A C T O R REPORT 3043 A V A I L A B I L I T Y - N T I S N A A S A

9337 Date June 1979 210000 841000 84::000 844000 Compilation of Radiation Damage Test Data. Part 1: Cable

Insulating Materials. Schonbacher, H.; Stolarz-Izycka, A. C E R ' N - 7 9 - 0 4 A V A I L A B I L I T Y - E U R O P E A N O R G A N I Z A T I O N

FOR N U C L E A R RESEARCH (CERN) , GENEVA C E R N

9826 Date March 1980 111210 32AOOO 521130 522130 795254(,717000 844000; Evaluation of Organic Moderator/Coolants for Fusion

Breeder Blankets. Romero, J.B. A N L / F P P / T M - 130 A V A I L A B I L I T Y - N T I S , PC A 0 3 / M F A01 A R G O N N

Organic Material - Biological Tissue


6510 Date 1976 020000 111110 111210 111220 122100 122200 810000

^845000 __ Basic Physical Data for Neutron Dosimetry." " Broerse, J.J. (Ed.) EUR-5629 A V A I L A B I L I T Y - I N I S N E T H E R

o • '>

u 6698 Date Apr i l 1978

113100 220000 329000 423210 423250 553120 845000 An Evaluation of the Distribution of Absorbed Dose in Child

Phantoms Exposed to Diagnostic Medical X -Rays . Chen, W.; Poston, J.W.; Warner, G.G. O R N L / T M - 5 9 3 3 A V A I L A B I L I T Y - N T I S O A R N L


age Neutron Spectra from Crit ical Assemblies. Singh, D.; Bisht, J.S.; Madhvanath, U. N U C L . I N S T R U M . METHODS, 151(1,2), 331-338 JAPAN

8213 Date Apr i l 25, 1978 1121:10 112710 220000 845000 Estimates of Internal Dose Equivalent to 22 Target Organs


Killough, G.G.\ Dunning, D.E.,Jr.; Bernard, S.R.; Pleasant, J.C. t-

O R N L / N U R E G / T M - 190; N U R E G / C R - 0 1 5 0 A V A I L A B I L I T Y - D E P . , N T I S O A R N L

371-




NUREG/CR-0134 ; O R N L / N U R E G / T M -215 A V A I L A B I L I T Y - D E P , NTIS O A R N L

8785 Date Apr i l 1979 u 112760 220000 795337 810000 845000 Dose-Rate Conversion Factors for External Exposure to

Photon and Electron;, Radiation from Radionuclides Occurring in Routine Releases from Nuclear Fuel Cycle Facilities.

Kocher, D.C._ N U R E G / C R - 0 4 9 4 r O R N L / N U R E G / T A V A I L A B I L I T Y - N T I S O A R N L

882S Date February 1979 122200 423250 220000 845000 Dosimetry of Very Low Energy Photons. Reddy, A.R.; Mehta, S.C. H E A L T H PHYSICS, 36(2), 175-182 I N D I A




Plister, G.; Hehn, G.; Mattes, M.; Friedlein, H.P. CONF-780921, PP.621-627 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, FRANCE v, G E R M A N

8855 Date September 1978 010000 122100 210000 760000 845000 Basic Nuclear Data for Dosimetry in Radiotherapy and

Radiobiology. Ricourt, A.; Chemtob, M.; Nguyen, V.D.; Parmentier, N. CONF-780921, PP.628-635 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L , '


8857 (J Date September 1978 010000 122100 210000 760000 845000 Nuclear Data for Radiotherapy with Neutrons. Cross, W.G. CONF-780921, PP.648-666 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

75775 PARIS CEDEX,16, FRANCE CANADA.-;-' ! !

8858 Date September 1978 010000 122100 210000 760000 845000 Recent Trends in Nuclear Reaction Data Needs for Nuclear

Medicine. " Stocklin, G.; Qaim, S.M. CONF-780921, PP.667-687 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, FRANCE G E R M A N - V j '


Human Dosimetry Applications. Kaul, D.; Chen, S.; Jarka, R. jj S A I - 1 2 1 - 1 3 2 - 1 / / A V A I L A B I L I T Y - S C I E N C E APPLIATIONS, I N C ,

1701 EAST WOODFIELD R D , SUITE 819, SCHAUMBURG, ILL. 60195 < f

SCA,

' , J 8905. Date May 1979

111130 111400 112130 220000 794000 793000 845000 Predicting Probability of Early Mortality from Acute Expo-

sure to Mixed LET Radiation.'' Kaul, D. SAI -121 - 1 3 2 - 4 - 7 9 A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, I N C ,

1701 EAST WOODFIELD R D , SUITE 819, SCHAUMBURG, ILL. 60195

SAI ....

8974 Date June 1979 220000 845000 Internal Dosimetry Data and Methods of I C R P - - P a r t 1. Ford, M.R.; Bernard, S.R.; Dillman, L.T.; Watson, S.B. NUREG/CR-0789; O R N L / N U R E G / T M - 3 1 5 A V A I L A B I L I T Y - N T I S O A R N L


Recommendations.

372-

Dobson, R.L. UCRL-81'774; CONF-790316-1 A V A I L A B I L I T Y - D E P . , NTIS L A L L

*)

9044 Date December 1978 112B00 329000 220000 845000 Realistic Calibration of Whole - Body Counters for Measur-

ing Plutonium. Parkinson, W.W.,Jr.; Goans, R.E.; Good, W.M. , ST I /PUB-471 (VOL.2),PP. 155-166;

CONF-77I209-P2,PP.155-166; A V A I L A B I L I T Y - I N T E R N A T I O N A L A T O M I C

ENERGY AGENCY, V I E N N A (AUSTRIA) \ O A R N L "

9070 Date June V979 111500 329000 220000 845000 Calculation of Fast Neutron Depth-Dose in the ICRU

Standard Tissue Phantom and the Derivation of Neutron Fluence-to-Dose-Index Conversion Factors.

Chen, S . -Y . ; Chilton, A.B. R A D I A T I O N RES., 78(3), 335-370 U - I L

9282 Date 1978 121100 845000 Stopping Power Ratios for Neutrons and Alpha Particles in

Tissue Equivalent Media. ' Thwaites, D.L; Watt, D.E. EUR - 5848,PP.45 - 60; C O N F - 770597,PP.45 - 60 A V A I L A B I L I T Y - O F F I C E FOR OFFIC IAL PUBLICA-

TIONS OF T H E EUROPEAN COMMUNIT IES , BOITE POSTALE 1003 > r LUXEMBOURG ISBN 92 -825 -0256-2

E N G L A N

li 928 4 Date 1978

111500 32A000 220000 551110 552210 795203 845000 Recent Results in Neutron Depth Dose Calculations. Burger, G.; Morhart, A.; Schra;ibe, H. EUR-5848,PP. 125 - 143; CONl^-770597,PP. 125-143 A V A I L A B I L I T Y - OFFICE FOR OFFIC IAL PUBLICA-

TIONS OF THE EUROPEAN COMMUNIT IES , BOITE POSTALE 1003' - LUXEMBOURG ISBN 92 -825 -0256-2

G E R M A N

928 5 v Date 1978 111220 760000 845000 Transport Calculations, Analytical Representations of

Absorbed Dose and Determination of Isoeffect Curves for Therapy with Fast Neutrons.

Bohm, J.K.; Eissa, H.M.; Hehn, G.; Pfister, G.; Stiller, P. EUR-5848,PP. 145-163; CONF-770597,PP. 145- 163 A V A I L A B I L I T Y - O F F I C E FOR OFF IC IAL PUBLICA-

TIONS OF T H E EUROPEAN COMMUNIT IES , BOITE POSTALE 1003 - LUXEMBOURG ISBN 92 -825 -0256 -2

G E R M A N

O 9290 Date 1978

11 1220 220000 421140 421200 760000 842000 845000 Determination of Neutron and Gamma Spectra in a Mixed

(n, gamma)-Field. Schmidt, R.; Magiera, E. EUR -5848,PP.443 -454; CONF-770597,PP.443-454 A V A I L A B I L I T Y - O F F I C E FOR OFF IC IAL PUBLICA-

TIONS OF T H E EUROPEAN C O M M U N I T I E S , BOITE POSTALE 1003 - L U X E M B O U R G ISBN 92 -825 -0256 -2

G E R M A N

9330 Date July 1979 y 2760 220000 329000 845000 Monte Carlo Calculations of the Response of an External

Detector to a Photon Source in the Lungs of a Heteroge-neous Phantom.

Bhati, S.; Sharma, R.C.; Somasundaram, S. H E A L T H PHYSICS, 37(1), 145-159 I N D I A



Kelly, G.N.; Simmonds, J.R.; Smith, H.; Stather, J.W. NRPB-R87 « .</ A V A I L A B I L I T Y - H M S O ISBN 0 85951 110 3 E N G L A N " «




NUREG/CR-0150,VOL.2; O R N L / N U R E G / T M - 1 9 0 / V 2


373-


Dose-Equivalent Index Presentedjin ANSI N13 . l l . Yoder, R.C.; Bartlett, W.T.; Courtney, J.W.; Hooker, C.D.;

Holland, J.A.; Hogan, B.T. NUREG/CR-1057 ; PNL-3219 (J

A V A I L A B I L I T Y - D E P . , NTIS, PC A 0 5 / M F A01 P A N L

Lillie, R.A.; Santoro, R.T. O R N L / T M - 6 6 5 5 A V A I L A B I L O A R N L

T Y - N T I S $4.50

\\ 9532., . Date February 1979 111500 112B00 220000 32A000 551110 552110 552210

793000 795276 845000 Development o f 'a M id -Head Radiation Dose Response

Function. Trubey, D.K.;, Knight, J.R.; Bartine, D.E.; Pace, J.V.,11I O R N L / T M - 6 6 3 4 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

9928 Date May 1980 112760 220000 795310 845000 SFACTOR: A Computer Code for Calculating Dose Equiv-

alent to a Target Organ Per Microcurie- Day Residence of a Radionuclide in a Source Organ — Supplemen-tary Report. «

Dunning, D.E.,Jr.; Pleasant, J.C.; Killough, G.G. NUREG/CR-1523; O R N L / N U R E G / T M - 8 5 / S ' i ^ . ° A V A I L A B I L I T Y - G P O SALES PROGRAM, DIVI -

SION OF T E C H N I C A L I N F O R M A T I O N jkND D O C U M E N T CONTROL, U.S. NUCLEAR REGU-LATORY COMMISSION, " W A S H I N G T O N / D . C . i, 20555

O A R N L

10001 Date August 1980 112B00 220000 311000 329000 795299 845000 Adjoint M C Techniques and Codes for Organ Dose Calcula-

f tions. ,, ! Koblinger, L. 1 O R N L / R S I C - 4 ^ P P . 2 0 3 - 2 1 7 I A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 (-| H U N G A R O

\ * ^ Siliceous Material - Earth and Sand

<T CATEGORY NUMBER 851000

j : 8736 Date March 1979 111400 112130 210000 32A000 521130 522130 551110 [ 552110 552220 830000 851000 853900 795320 '

Radiation Transport in Earth for Neutron and Gamma Ray Point Sources Above an A i r -Ground Interface.

9618 Date August 1979 113100 210000 851000 Probabilistic Approach to EMP Assessment. Bevenseo, R.M.; et al. UCRL-52,804 " A V A I L A B I L I T Y - N T I S L A L L

. 10080., Date August 1980 112760 230000 532000 851000 Expected Environments in High-Level Nuclear Waste and

Spent Fuel Repositories in Salt. Claiborne, H.C.; Rickertsen',JL.D.; Graham, R.F. O R N L / T M - 7 2 0 1 ° A V A I L A B I L I T Y - N T I S , PC^A10/MF A01 O A R N L ' .

• • a „ "O

Siliceous Material - Glass ,.


8875 Date 1979 111210 210000 717000 810000 852000 Radiation Damage in Diagnostic Windows for the TFTR. Primak, W. CONF-790125-12 A V A I L A B I L I T Y - D E P . , NTIS A R G O N N

Siliceous Material - Ordinary Concrete


O t-6395 Date Dec. 1977

722100 853100 Calculation of Duct and Annular Gap Problems Wi th

ESTOQ-DOT and Analytical Expressions. Zumach, W. CONF-770401, PP.253-261 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


ft 374-

6468 Date Dec. 1977 111210 329000 511110 820000 853100 861000 Radiation Doses as a Function of Thickness and Shielding

Material Surrounding a 14 MeV Neutron Source. Hansen, L.F.; Komoto, T.; Wong, C. ^ CONF-770401, PP.881-888 <-> A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 L A L L

6935 Date June 1978 111210 710000 717000 793000 79525^853100 Shielding Calculations for the Intense Neutron Source Facil-

ity. Final Report. Battat, M.E.; Henninger, R.J.; Macdonald, J.L.; Dudziak,

D.J. L A - 7 3 3 2 - M S A V A I L A B I L I T Y - N T I S $4.00 LOASL

6471 Date Dec. 1977 853100 Fresh Concrete Control in Situ of Biological Shields of

Nuclear Reactors. Honig, A. CONF-770401, PP.905-912 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., PRINCETON, NJ 08540 CZECHO

6517. ? i ' ^ D a t e Apri l 16, 1975 111220 421130 430000 521230 522230 853100 861000 Time-Dependent Measurements of Fast-Neutron and

Secondary Gamma-RayjTransport Through a Thick Concrete and Steel Shield. Final Report.

Young, J.C.; Harris, L.,Jr.; Bryan, D.E.; Lurie, N.A.; Stein-man, D.K.; Friesenhahn, S.J.; Gober, W.E.; Schanzler, L. <•

IRT-8025-723 A V A I L A B I L I T Y - I N S T R U M E N T A T I O N

RESEARCH TECHNOLOGY, 7650 CONVOY COURT, P.O. BOX 80817, SAN DIEGO, CALIFOR-N I A 92138

IRT t :

6566.'.» . . . . . Date September 15, 19^7 423250 853100 Concrete Shielding for Thermoluminescent Dosimeter Mon-

itoring Post to Reduce Background Interference. Weng, P.; Hsu, P. NUCL. " INSTRUM. METHODS, 145(3), 433-435 C H I N A

6804 Date September 5, 1970 111 110 710000 740000 853100 853300 853400 853700 N Reactor Shielding. Davis, H.S. D U N - S A - 1 5 1 A V A I L A B I L I T Y - N T I S DOUGLA

7125 Date July 197"Cx,-1111 10 210000 853100 " x

Requirements on Concrete and Structures ,of Reinforced Concrete Reactor Shield. {,

Korenevskiy, V.V.; Pergamenshchik, B.K.; Perevalov, V.S. E R D A - T R - 1 2 5 , PP. 251-259 A V A I L A B I L I T Y - N T I S , RUSSIA

7127 Date July 1976 , 111110 112500 421150 511120 521230 853100 853200


; Pankrat'yev, Yu.V.; Piskunov, V.I.; Staurin, N.V. E R D A - T R - 1 2 5 , PP. 273-290 A V A I L A B I L I T Y - N T I S RUSSIA ,,

511110 512210 i/ o 7129 Date March 1977

111130 111400 122110 122210 32A000 830000 853100 810000

Production and Testing of the DNA Few-Group Coupled Neutron-Gamma Cross-Section Library.

Bartine, D.E.; Knight, J.R.; Pace, J.V.,III; Roussin, R. O R N L / T M - 4 8 4 0 A V A I L A B I L I T Y - D E P . , NTIS $5.50 O A R N L o i\

;,8032 Date September 1978 111210 122100 312000 32A000~511110 512210 717000


Reactor Shielding Experiments. Seki, Y.; Santoro, R.T.; Oblow, E.M.; Lucius, J.L'.' ORNL-5467 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8034 Date August 1978 111110 220000 32A000 551110 552210 820000 861000

853100 793000 0

Nuclear Accident Dosimetry: Calculations and Comparison with Experimental Data.

O

- 375

Santoro, R.T.; Alsmiller, R.G.,Jr.; Barnes, J.M. O R N L / T M - 6 4 0 1 / R 1 A V A I L A B I L I T Y - N T I S $4.00 O A R N L

8095 Date September 1978 112B00 512110 632110 853100 Berger Coefficients fo r v the Eisenhauer-Simmons

Gamma-Ray Buildup Factors in Ordinary Concrete. (Tech. Note) u

Metghalchi, M. NUCL. SCI. ENG., 67(3), 341-342 » I R A N

8199 Date August 1977 112500 11.1500 112BOO 32A000 311000 511110,512110

795254 853100 ^ Neutron- and Gamma-Ray Transport Calculations of

Dose Transmission Factors in Concrete.u It Engstrom, G.; Lefvert, T. FOA RAPPORT C 20195 - A2 C A V A I L A B I L 1 T Y - F O R S V A R E T S FORSKNINGSAN-

STALT, H U V U D A V D E L N I N G 2, 104 50 S T O C K H O L M

SWEDEN

I 8216. . Date June 1978

112120 230000 853100 A Review of Radioactive Waste Immobilization in Concrete. Lokken, R.O. PNL-2654 » « A V A I L A B I L I T Y - B A T T E L L E PACIFIC NORTH-

WEST LAB. B A M I

•-.J-.. /,'

8517. . .0>: Date February 1979 020000 111210'122310 312000 32A000 551110 552110

795276,717000 721100 793000 794000 861000 853100 Cross Section Sensitivity Analysis of a Proposed Neutron



O R N L / T M - 6 5 8 8 ^ A V A I L A B I L I T Y - N T I S $4.50 O A R N L [t

i.i

8565 Date 1977 111210 32A000 329000 511110 512210 830000 853100


Facility. Peng, W.'H.; Celnik, J.

CONF-771029,VOL.11, PP.1704-1706 A V A I L A B I L I T Y - I E E E SERVICE CENTER, S INGLE

P U B L I C A T I O N SALES DEPT., 445 HOES L A N E , P ISCATAWAY, N.J. 08853

BURNS <„,' o

8690 Date March 1979 112B00 512110 632110 853100 Tchebycheff-'Fitted Berger Coefficients for Eisen-


Chilton, A.B. NUCL. SCI. ENG., 69(3), PP.436-438 U - I L

8792 n Date February 1979 010000 111110 223000 32A000 521110 522110 610000


LWRs. Rahn, F.; Ti l l , H. ORNL/RSIC-43,PP.1-21 ; ANS/SD-79 /16 ,PP.1-21 A V A I L A B I L I T Y - N T I S EPRI

08797 Date February 1979 l l l l 10 "329000 721,100 722100 793000 719A00 610000,,


HarmonicsiExpansion of Albedo Data. Albert, T.E.; Simmons, G.L. ORNL/RSIC-43,PP.68-75; ,

" ANS/SD-79/16,PP.68-75 A V A I L A B I L I T Y - N T I S SCA

//

8885. ; Date March 1979 111500 32AOOO 329000 551110 552210 853100 861000

795203 793000 The SAI /EPRI Albedo Information Library. , Simmons, G.L. EPRI -NP-1017 A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, INC.,

u 1200 PROSPECT ST., LA JOLLA, C A L I F O R N I A "92038

SCA

8983 Date March 1979 113100 513120 750000 853100 Attenuation of Primary and Leakage Radiation in Concrete

for X -Rays from a 10 M V Linear Accelerator. Tochilin, E.; LaRiviere, P.D. H E A L T H PHYS., 36(3), 387-392

376-

VARIAN

8992 Date February 1, 1979 112760 422200 522210 841000 853100 861000 870013

870082 Measurement of Number Albedo of Backscattered Photons. Biswas, M.; Sinha, A.K.; Roy, S.C. „ NUCL. INSTRUM. METHODS, 159(1), 157-162 I N D I A

FRANCE

10005 Date August 1980 010000 329000 721100 853100 870011 Deep-Penetration Calculations. Thompson, W.L.; Deutsch, O.L.; Booth, T.E. O R N L / R S I C - 4 4 , PP.267-294 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 LOASL

8993 Date February 1, 1979 II1110 220000 511110 632110 820000 842000 853100 Depth-Dose Distribution for Fission Neutron Spectra

Degraded Through Low Z Shields. Singh, D.; Bisht, J.S.; Madhvanath, U. o NUCL. INSTRUM. METHODS, 159(1), 229-234 I N D I A

10006 Date August 1980 111220 329000 521130 853100 861000 795372 Experience with TRIPOLI at ORNL. Cramer, S.N.; Roussin, R.W. v -O R N L / R S I C - 4 4 , PP.295-304 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 O A R N L ^

9062 Date February 15, 1979 1II220 329000 750000 853100 Neutron and Photon Measurements Through Concrete from

a 15 GeV Electron Beam on a Target Comparison with Models and Calculations.

Jenkins, T.M. NUCL. INSTRUM. METHODS, 159(2,3), 265-288 STLAC

9634 i> Date March 1980 512110 632110 853100 Concrete Buildup Factors Based on the American National

Standard for Fj lux-to-Dosc-Rate Conversion. (Let-ter to the Editor) «

Chilton, A.B.; Brown, R.W. V NUCL. SCI. ENG., 73(3), 301 U - I L

9724 Date January 1980 111500 329000 521110 853100 795203 793000 Neutron Spectra from Monoenergetic Source Neutrons


Hagan, W.K.; Simmons, G.L. " NUCL . SCL ENG., 73(1), 35-41 SCA



Ueki, K. ORNL /RS IC-44 , PP.329-344 A V A I L A ' B I L I T Y - N T I S , PC A 1 6 / M F A01 JAPAN

Siliceous Material - Barytes Concrete


r? ° 7126 o Date July 1976

111110 740000 853200 853800 The Use of Barium-Serpentine Cement in Reactor Shields


Kutateladze, K.S.; Lekishvili, R.A.; Pankrat'yev, Yu.V.; Piskunov, V.I.



Through a One-Bend Sodium D:ict. Sartori, E. ^ ORNL/RSIC-44 , PP.219-229 " " A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01

7127 Date July 1976 111110 112500 421150 511120 521230 853100 853200


Pankrat'yev, Yu.V.; Piskunov, V.I.; Staurin, N.V. E R D A - T R - 1 2 5 , PP. 273-290 A V A I L A B I L I T Y - N T I S

377- \<

RUSSIA

Siliceous Mater ia l - Fe r rophosphorous Concrete


6804. . .ji Date September 5, 1970 111110 710000 740000 853100 853300 853400 853700 N Reactor Shielding. Davis, H.S. , D U N - S A - 1 5 1 " ^

. A V A I L A B I L I T Y - N T I S DOUGLA

9702 Date Apr i l 1979 713000 853400 " Thermal Performance Test on "Serpentine Concrete for Fast

Breeder Reactor Shielding(II). Shiozaki, T.; Hozumi, Y.; Hiratsuka, A.; Yasuda, M.;

Ishimi, K.; Okawa, K? JAPFNR-462; PNC S/f230 78-01 TR A V A I L A B I L I T Y - P O W E R REACTOR A N D

N U C L E A R FUEL DEVELOPMENT CORP., TOKYO, JAPAN

JAPAN

// Siliceous Ma te r i a l I lmenite Concrete '


7127 Date July 1976 111110 112500 421150 511120 521230 ,,853100 853200

853300 853400 853500 853600 853700 \f Analysis of the Shielding Properties of Various Concretes. Veselkin, A.P.; Voskresenskiy, Ye.V.; Yegorov, Yu.A.;


853100 /•j'53200 UU 13. Vih

7127 Date July 1976 111110 112500 421150 511120 521230

853300 853400 853500 853600 853700 Analysis of the'Shielding Properties of Various Concretes. Veselkin, A.P.; Voskresenskiy, Ye.V.; 'Yegorov, Yu.A.;

Pankrat'yev, Yu.V.; Piskunov, V.L; Staurin, N.V. E R D A - T R - 1 2 5 , PP. 273-290 A V A I L A B I L I T Y - N T I S RUSSIA

Siliceous Mater ia l - Magne t i t e Concrete'5

JJ r- CATEGORY NUMBER 853400

6804. . Date September 5, 1970 111110 710000 740000 853100 853300 853400 853700 N Reactor Shielding. Davis, H.S. D U N - S A - 1 5 1 A V A I L A B I L I T Y - N T I S DOUGLA

9060 Date June 1979 a 111220 329000 421160 511120 853500

Jj Attenuation of Fast Neutrons in llmenite Concretes, Adams, R.J.; Lokan, K.H. H E A L T H PHYS., 36(6), 671-678 C A N A D A » V

Siliceous Ma te r i a l - Limonite,.Concrete

CD CATEGORY NUMBER 853600

7127 vV Date July 1976 111110 1125.00 421150 511120 {-521230 853100 853200.

853300 853400 853500 853600 853700 <> Analysis of the Shielding Properties of Various Concretes. Veselkin, A.P.; Voskresenskiy, Ye.V.; Yegorov, Yu.A.;

Pankrat'yev, Yu.V.; Piskunov, V.L; Staurir.-, N.V. E R D A - T R - 1 2 5 , PP. 273-290 A V A I L A B I L I T Y - N T I S ° * RUSSIA

7127 Date July 1976 J11110 112500 421150 511120 521230 853100 853200

853300 853400 853500 853600 853700 Analysis'of the Shielding Properties of Various Concretes. Veselkin, A.P.; Voskresenskiy, Ye.V.; Yegorov, Yu.A.;

Pankrat'yev. Yu.V.; Piskunov, V.L; Staurin, N.V. E R D A - T R - 1 2 5 , PP. 273-290 A V A I L A B I L I T Y - N T I S RUSSIA ^ «

378-

Siliceous Mater ia l - Heavy-addi t ive Concrete


6804. . . ][. Date September 5, 1970 111110 710000 7^0000 853100 853300 853400 853700 N Reactor Shielding. 0

Davis, H.S. D U N - S A - 1 5 1 A V A I L A B I L I T Y - N T I S D O U G L A

0 7127 Date July 1976

111110 112500 421150 511120 521230 853100 853200 853300 853400 853500 853600 853700

Analysis of the Shielding Properties of Various Concretes. Veselkin, A.P.; Voskresenskiy, Ye.V.; Yegorov, Yu.A.;


8035 Date August 1978 111220 122110 32A000 511110 853900 853700 861000


Energies to 60 MeV. Alsmiller, R.G.,Jr. Q y O R N L / T M - 6 4 8 6 A V A I L A B I L I T Y - N T I S S4.50 O A R N L

Siliceous Mater ia l - Serpent ine Concrete o


7112 Date July 1976 111110 421140 721100 721200 719A00 853800 861000 n Passage'-of Neutrons with Intermediate Energies Through



Bolyatko, V.V.; Gorbatov, V.S.; Reytblat, V.L.; Tkachenko, V.V.; Khokhlov, V.F.; Tsypin, S.G.


7126.Q, Date July 1976 111110 740001/853200 853800 The Use of Barium-Serpentine Cement in Reactor Shields


K;utateladze, K.S.; Lekishvili, R.A.; Pankrat'yev, Yu.V.; Pu-kunov, V . I . / f i'

E R D A - T R - 1 2 5 / P P . 260-272 A V A I L A B I L I T Y - N T I S RUSSIA

Siliceous Mate r i a l - Special or Local /j Aggrega t e Concrete


8035 Date August 1978 111220 122110 32A000 511110 853900 853700 861000

512210 793000 Neutron-Photon Multigroup/'Cross Sections for Neutron

Energies to 60 MeV. ^ Alsmiller, R.G.,Ji. O R N L / T M - 6 4 8 6 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8736 Date March 1979 111400 112130 210000 32AOOO 521130 522130 551110

552110 552220 830000 851000 853900 795320 Radiation Transport in Earth for Ncutron and Gamma Ray

Point Sources Above an A i r -Ground Interface. Lill ie, R.A.; Santoro, R.T. 0


O

< Iron and Iron Alloys


7114 Date July 1976 112500 423250 32A000 511110 512210 512220 853800

861000 Investigation of the Field of Capture Gamma-Radiat ion in

Solid Shielding. b

C> 6247 . . Date December 1977 111210 32AOOO 210000 5$H30 522130 531000 532000

717000 793000 795254 810000 861000 870003 Nuclear Performance Calculations for the E L M O Bumpy

Torus.Reactor (EBTR) Reference Design. Santoro,~R.T.; Barnes, J.M.

c 0 " )i

379 O O


A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROCKSTONE DR., PR INCETON, N J 08540

RUSSIA

A 6382 Date Dec. 1977 312000 713000 861000 870011 o Fast Reactor Shield Sensitivity Studies for

Steel -Sodium-I ron Systems. Oblow, E.M.;<Weisbin, C.R. J) CONF-770401, PP.140-148 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., P R I N C E T O N , NJ 08540 O A R N L

11 6479 Date January 1978 111500 121100 210000 794000 861,000 Sensitivity of Primary Knock-on Atom Spectra and Dis-

placement per Atom Cross-Sections to Different Secondary Neutron Energy and Angular Distributions and " In -Group" Weighting Schemes.

Gabriel, T.A.; Bishop, B.L. O R N L / T M - 6 I O 8 A V A I L A B V L I T Y - N T I S $4.50 O A R N L

6459 Date Dec. 1977 122310 861000 870011 Use of Integral Data for the Prediction of Neutron Propaga-

tion in I ron-Sodium Mixtures. Estiot, J.C.; Trapp, J.P.; Palmiotti, G.; Salvatores, M. CONF-770401, PP.804-811 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

DR., P R I N C E T O N , NJ 08540 o F R A N C E o

6462 Date Dec. 1977 020000 111110 421140 551120 795254 795222 861000


Iron at Y A Y O I . Oka, Y.; An, S.; Kasai, S.; Sakata, S.; Miyasaka, S.; Koya-


DR., PR INCETON, NJ 08540 J A P A N

6468 Date Dec. 1977 '' 111210 329000 511110 820000 853100 86l'000 Radiation Doses as a Function of Thickness and Shielding

Material Surrounding a 14 MeV Neutron Source. Hansen, L.F.; Komoto, T.; Wong, C. CONF-770401, PP.881-888 0

A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE DR., PR INCETON, NJ 08540

L A L L C/

6472 . . Date Dec. 1977 112400 112500 512220 820000 861000 870082 Secondary Gamma Radiation Study-in Reactor Shielding. Abagjan, A.A.; Gasnikov, N.K.; Germogenova, T.A.;

Bubinin, A.A.; Zhuravlyov, V.I.; Kolevatov, Yu.J.; Kurachenko, Yu.A.; Mashkovich, V.P.; Sakharov, V.K.

CONF-770401, PP.913-921 .

6517 Date Apr i l 16, 1975 111220 421130 430000 521230 522230 853100 861000 Time-Dependent Measurements of Fast-Neutron and

Secondary Gamma-Ray Transport Through a Thick Concrete and Steel'Shield. Final Report.

Young, j .C.; Harris, L.,Jr.; Bryan, D.E.; Lurie, I$.A.; Stein-man, D.K.; Friesenhahn, S.J.; Gober, W.E.;<Schanzlcr, L. ,,,

1RT-8025-723 A V A I L A B I L I T Y - I N S T R U M E N T A T I O N ^

RESEARCH T E C H N O L O G Y , 7650 C O N V O Y COURT, P.O. BOX 80817, S A N DIEGO, CAL IFOR-N I A 92138 t i

IRT "

6573 Date March 1978 122310 861000 Consistent Utilization of Shielding Benchmark Experiments. D'Angelo, A.; Oliva, A.; Palmiotti, G.; Salvatores, M. ; Zero,

S. " N U C L . SCL ENG., 65(3), 477-491 I T A L Y ,

6609 DajxDecember 1977 £ 111110 210000 311000 32A000'/551110 795276 719A00


of an^LWR. Final Report (Research PrSject 827-2) . Iiivesay, R.B.; Wells, M.B. E P R I - N P - 6 1 7 ° A V A I L A B I L I T Y - R A D I A T I O N RESEARCH ASSOCI-

ATES, INC. RARA o

6677 Date June 1977 111110 121100 210000 421140 861000 Importance and Status of (n, alpha)-Cross Sections for a

Reliable Prediction of Radiation Damage in Stainless Steel.

380-

o

Goel, B. EURFNR-1465 A V A I L A B I L I T Y - N T I S G E R M A N


u i d - A i r Vessel Containing a D - T Neutron Source. Tripler, D.J.; Goldberg, E.; Farley, W.E.

r. UCRL-52334 A V A I L A B I L I T Y - D E P . , NTIS

o L A L L

6709 Date'September 1976 111110 111210 121100 210000 713Q00 717000 861000 A Systematic Approach to the Radiation Damage Problem

in Fission and Fusion Reactor Structural Alloys. " Bullough, R.: Eyre, B.L.; Kulcinski, G.L. U W F D M - 1 8 4 ^ „ A V A I L A B I L I T Y - N U C L E A R ENGINEERING

DEPARTMENT, UNIVERSITY Ol;, WISCONSIN, MADISON, WISCONSIN

U - W I

6734 Date May 1978 111210 122310 312000 521130 795204 717000 870006

870092 861000 Cross-Section Sensitivity Analysis of 235 -U and 238 -U


Seki, Y.; Maekawa, H. NUCL . SCI. ENG., 66(2), 243-251 JAPAN

o a j f 6799 Date June 1978

/ / D20000 421140 421130 32A000 861000 511120 <s Benchmark Shielding Experiments for Testing Iron and

Steel Data. " McCombie, C.; Gmur, K.; Jermann, M.; Richmond, R.; Sch-

mocker, U.; Seth, S. CONF-780401, PP.53-62 A V A I L A B I L I T Y - N T I S SWITZ

6803 Date 1975 111110 324000 32AOOO 511110 861000 870092 Multigroup Formalism for Evaluation of Continuous Slow-

ing Down Theory-'Parameters. Parvez, A.; Becker, M. COO-2458-18 A V A I L A B I L I T Y - D E P . , NTIS

J ' -

6810 Date 1978 010000 210000 421130 421140 511120 719A00 861000 Power Reactor Pressure Vessel Benchmarks. Rahn, F.J. IAEA-208 , VOL.I, PP.105-140 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE EPRI

6848 Date 1,978 111110 210000 511120 861000 870092 One Material Experiments in the Frame of Power Rcactor

Pressure Vessel Benchmarks. De Leeuw-Gicrts, G.; De Leeuw, S. IAEA-208 , VOL.11, PP.375-383 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE BELGIU

6869 Date May 1978 112200 329000 512110 512210 820000 861000 870013

870082 Shielding Study of Bremsstrahlung in Bulk Media with Elec-j!.

trons. Part I I : Spatial Bremsstrahlung Distribution in"y

Water, Aluminum, Iron and Lead Bombarded by 22 MeV Electrons. „

Nakamura, T?\> Hirayama, H.; Shin, K. NUCL. INSTRUM. METHODS, 151(1,2), 277-284 JAPAN Q o

G 6873 Date June 1978 <

111110 112400 421120 421130 795066 512210 512220 861000 870098 %

Measurement and CalculationS-of Californium-262 Fission Neutron-Induced Gamma Yields in Iron.

Jiang, S.H.; Werle, H. NUCL. SCI. ENG., 66(3), 354-362 G E R M A N

6948 , Date August 1978 111210 421000 32AOOO 551110 795276 861000

cpVsign Calculations for a 14-MeV Neutron Collimator. Litlie, R.A.; Alsmiller, R.G,Jr. O R N L / T M - 6 4 8 7 A V A I L A B I L I T Y - N T I S $4.50 O A R N L O

7069 Date January 1977 111110 32A000 423140 511110 511120 793000 795254

842000 870098 861000 870082 C Transmission of 252-CF Fission Neutrons Through Vari-

ous Shields. Song, Y.T. f

>7$

0 381

NBS SPEC. PUB. 461, PP. 119-123 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS,


GPO,

7101 Date July 1976 111500 321000 323000 5H110 C61000 870006 Asymptotic Characteristics of the Distribution of Fast Neu-

tron fluxes in Heterogeneous Shielding. Germogenova, T.A.; Konovalov, N.V.; Suvorov, A.P. E R D A - T R - 1 2 5 , PP. 25-34« A V A I L A B I L I T Y - N T I S RUSSIA

a ' " 7102 Date July 1976,.,

111500 321000 511110°55I110 820000 861000 Spatial and Angular Distributions of Fast Neutrons in Coni-


A.N. E R D A - T R - 1 2 5 , PP. 35-45 „/i A V A I L A B I L I T Y - N T I S RUSSIA *

RUSSIA , O

Q " (t 7115 Date July 1976

112B00 421200 522210 610000 820000 870013 861000 870082 lJ ft

Differential Characteristics of the Energy Albedo of Gamma-Quanta for Organic Mediums.

Viktorov, A.A.; Mashkovich, V.P. >, ° E R D A - T R - 1 2 5 , PP. 152-156 A V A I L A B I L I T Y - N T I S RUSSIA O

&" 7117 Date July 1976*

112110 329000 532000 861000 87008? Investigation of Radioactive Heat Generation in Structural

Materials of Shielding Placed inL igh t Mediums. Avayev, V.N.; Yefimov, Ye.P. <5,. c E R D A - T R - 1 2 5 , PP/169-175 A V A I L A B I L I T Y - N T I S ' , RUSSIA " ' " /

7108 Date July 1976 112B00 329000 512110 861000 Investigating the Field of :Soattered Radiation at Great Dis-

tances From the Source. ^ Zolotukhin, V.G.; Ksenofontov, A.I.; Panchenko, A.M.;

Sinev, V.N. 0 „ E R D A - T R - 1 2 5 , PJ>. 92-99 A V A I L A B I L I T Y - N T I S RUSSIA

7118 Date July 1976 010000 420000 421150 511120 861000 Modern Methods and Experience of Analyses of Neutron ^

Energy Distributions in Nuclear Reactor Experiments! Yegorov, Yu.A.; Pankrat'yev, Yu.V. , (b E R D A - T R - 1 2 5 , PP. 176-190 o A V A I L A B I L I T Y - N T I S RUSSIA

o 7112 'i . . . Date July 1976 111110 421140 721100 721200 719A00 853800 861000 Passage of Neutrons with Intermediate Energies Through

Shielding with Complex Irregularities. <~< Bolyatko, V.V.; Sakharov, V.M.; Suvorov, A.P.; Kharizo-

menov, Yu.V. E R D A - T R - 1 2 5 , PP. 127-139 A V A I L A B I L I T Y - N T I S '< RUSSIA

\) 7114 Date July 1976 r,

112500 423250 3 ^ 0 0 511110 5'l 2210 512220 853800 861000 ~

Investigation of the Field of Rapture Gamma-Radiation in Solid Shielding'^

Bolyatko, V.V.; Gor\<atov, V.S.;.Reytblat, V.L.; Tkachenko, V.V.; Khokhlov, V.F.; Tsypin, S.G. ^ ,,

E R D A - T R „ 1 2 5 , PP. 145-151 A V A I L A B I L I T Y - N T i S c

7120 Date July 1976 111110 4JM 150 511120 861000 870013 870022 Application of Hydrogen Spectrometer for Spectral Analysis

of Neutrons in^Reactor Shield Materials Badyayev, V.V.; Yegorov,


Yu.A.; Kulagin, V.A.f

o / 8032 . Date September 1978

111210 122100 312000 32AOOO 511110 512210 717000 830000 842000 853100 861000 882000

Macroscopic. Cross Section Sensitivity Study for Fusion v Reactor Shielding Experiments.

Seki, Y.; Santoro, R.T.; Oblow, E.M.; Lucius, J.L. ORNL-5467 % A V A I L A B I L I T Y - N T I S S4.50 O A R N L , » „ 0 D

O "382

803 4 Date August 1978 111110 220000 32A000 551110 552210 820000 861000


with Experimental Data. Santoro, R.T.; Alsmiller, R.G,Jr. ; Barnes, J.M. O R N L / T M - 6 4 0 1 / R 1 A V A I L A B I L I T Y - N T I S S4.00 O A R N L

l i

803 5 Date August 1978 .111220 122110 32A000 511110 853900 853700 861000

512210 793000 Neutron-Photon Mult igroup Cross Sections Tor Neutron

Energies to 60 MeV. Alsmiller, R.G.,Jr. O R N L / T M - 6 4 8 6 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8375 Date February 1978 111210 421160 329000 511120 861000 870022 Pulsed Sphere Measurements for Weapons and Fusion

Reactor Design. U C R L - 5 2 0 0 0 - 7 8 - 2 , PP.9-14 A V A I L A B I L I T Y - D E P . , N T I S o L A L L

8389 Date 1978 112730 329000 522110 522210 870004 870006 853100



Pozdneev, D.B.; Savyuk, S.N.; Fadeev, M .A . K E R N E N E R G I E , 21(5), 148-149 ( I N R U S S I A N ) RUSSIA


a Portable Smelter and to the Surrounding Population. Randolph, M.L. ; Watson, A.P.; O'Donnell, F.R. O R N L / T M - 6 4 4 2 A V A I L A B I L I T Y - N T I S O A R N L o

8465 Date June 1978 111210 210000 717000 861000 870003 810000 Materials Considerations for Inert ial ly-Confined Fusion

Reactors ( ICFR) . Hovingh, J. ^ U C R L - 8 1 2 0 6

A V A I L A B I L I T Y - L A W R E N C E L I V E R M O R T . L A B O -R A T O R Y

L A L L

8477 Date January 1979 210000 861000 n

Helium Production in Stainless Steel. (Tech. Note) Goel, B. N U C L . SCI. ENG., 69(1), 99-104 G E R M A N

8500 Date June 1977 111110 122110 324000 326000 327000 820000 861000

. 870013 870092 511110 521130 Moments of the Fourier-Transformed Neutron Slow-

ing-Down Kernel: The Computer Code "MAG.GIE" . Gado, J.; Keresziuri, A. K F K I - 1 9 7 7 - 4 4 A V A I L A B I L I T Y - K O Z P O N T 1 F I Z I K A I K U T A T O

I N T E Z E T , BUDAPEST ( H U N G A R Y ) ISBN 9633712637

H U N G A R

8517 Date February 1979 020000 111210 122310 312000 32A000 551110 552110



Seki, Y. ; Santoro, R.T.; Oblow, E.M.; Barnes, J.M.; Lucius, J.L.




Grant, W.H. ; Otte, V.A. H E A L T H PHYS., 35(6), 807-816 U - T X

8577 Date November 1978 111110 32A000 122310 31°2000 551110 551200 793000

794000 870011 861000 795276 795254 795203 Investigation of Stee l -Sod ium-I ron Shields. Oblow, E.M.; Maerker, R.E. C O N F - 7 8 1 1 1 7 - 6 A V A I L A B I L I T Y - D E P . , NT IS O A R N L

383-



Peng, W^H. COO-'2509 - 6 A V A I L A B I L I T Y - D E P . , NTIS U - N Y


siderations in LWR Pressure Vessels. Serpan, C.Z,Jr . EUR-5667E/F,PT.I , PP.41 -51;'" CONF-750935,PT.I,

PP.41 - 51 ^ A V A I L A B I L I T Y - O F F I C E FOR OFFICIAL PUBLICA-

TIONS OF THE EUROPEAN COMMUNIT IES , BOITE POSTAL 1003 - L U X E M B O U R G

N U R C

8588 Date 1977 111110 210000 521130 713000 719A00 795254 861000


Outside the Reactor Core. „ Hehn, G.; Stiller, P. EUR-5667E/F?PT.I, PP.52-62; CONF-750935,PT.I,


T IONS OF T H E EUROPEAN COMMUNIT IES , BOITE POSTAL 1003 - L U X E M B O U R G

G E R M A N

A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L PUBLICA-T IONS OF T H E EUROPEAN C O M M U N I T I E S , BOITE POSTAL 1003 - L U X E M B O U R G

I T A L Y .

8659 Date February 1979 111110 122310 210000 421140 719A00 861000 795112

430000 Use of H E D L Codes in the Sensitivity and Uncertainty

Analysis of the Pressure VesseliEmbrittlement Damage Function Problem.


O R N L / R S I C - 4 2 , PP.135-143 A V A I L A B I L I T Y - N T I S HANFOR

8660 Date February 1979 111110 122310 210000 430000 521130 861000 810000 Varied Applications of a New Maximum-Likel ihood Code

with Complete Covariance Capability. Schmittroth, F. O R N L / R S I C - 4 2 , PP.145-159 A V A I L A B I L I T Y - N T I S HANFOR

8672 Date February 1979 1.11110 122310 795254 795204 421140 861000 The Linearity Assumption in Adjustment Procedures. Yeivin, Y. O R N L / R S I C - 4 2 , PP:343-350 A V A I L A B I L I T Y - N T I S ISRAEL ' ,.


tors. :v

Etherington, E.W. !

EUR-5667E/F,PT. I , PP.375-413; CONF-750935,PT.I, PP.375-413

A V A I L A B I L I T Y - O F F I C E FOR OFFIC IAL PUBLICA-TIONS OF THE EUROPEAN COMMUNIT IES , BOITE POSTAL 1003 - LUXEMBOURG

NETHER

8622 Date 1977 111110 210000 422110 861000 Vessel's Material Surveillance Program Fast Neutron (E

greater greater than 1 MeV) Flux Measurement. Galliani, M.; Benatti, P.I.N.; Puliandri, P.I.A. EUR-5667E/F,PT. I , PP.763-777;

CONF-750935,PT.I, PP.763-777 >•

8674 Date February 1979 111110 122310 32A000 312000 521130 713000 719A00


Adjustment. Chestnutt, M.M.; MCracken, A.K. ORNL /RS IC -42 , PP.363-373 A V A I L A B I L I T Y - N T I S E N G L A N

8678 Date March 1979 112120 32A000 552110 795217 719A00 795320 861000 Calculated, Two-Dimensional Dose Rates from a PWR

Fuel Assembly. Croff, A:G.;» Hermann, O.W.; Alexander, C.W. O R N L / T M - 6 7 5 4 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

i-384

8689 Date March 1979 112B00 512110 632110 820000 861000 870,082 G a m m a - R a y Dose Rate Conversion and Buildup Factors.

(Tech. Note) Shure, K. N U C L . SCL ENG., 69(3), PP.432-436 BETT IS

U 8792 Date February 1979

010000 11<110 223000 32A000 521110 522110 610000 719A00 722100 853100 861000

Neutron Flux Determination in the Reactor Cavities of LWRs.

Rahn, F.; T i l l , H. O R N L / R S I C - 4 3 , P P . 1 - 2 1 ; ANS/SD-79 /16 ,PP.1 - 2 1 A V A I L A B I L I T Y - N T I S EPRI

8797 Date February 1979 111110 329000 721100 722100 793000 719A00 610000

861000 853100 A n Improved Streaming Analysis Technique; Spherical

Harmonics Expansion of Albedo Data. Albert , T.E.; Simmons, G.L. O R N L / R S I C - 4 3 , PP.68-75;

ANS /SD-79 /16 ,PP .68 -75 A V A I L A B I L I T Y - N T I S SCA

8829 Date 1978 112B00 329000 522110 861000 870006 870013 870050


Monte -Car lo Method. Seda, J.; Kluson, J.; Cechak, T. I N T . J. APPL. RAD1AT. ISOTOP., 29, 419-422 C Z E C H O

8847 Date September 1978 010000 122100 861000 862000 Resonance Cross Sections for Structural Material. Frohner, F.H. CONF-780921 , PP.268-287 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,


8873 Date September 1978 122110 122310 861000 The Linearity Assumption in Adjustment Procedures: Is I t

a Real Problem? Yeivin, Y . CONF-780921 , PP.1172-1177

A V A I L A B I L I T Y - O E C D , 2, R U E A N D R E - P A S C A L , 75775 PARIS CEDEX 16, F R A N C E

I S R A E L

8881 Date 1979 111110 112400 112500 421200 522230 795065 795223


Induced in Iron by 252 -C f Fission Neutrons. Jiang, S.H. D O E - T R - 7 2 ; K F K - 2 4 4 4 ( I N G E R M A N ) A V A I L A B I L I T Y - U S D O E T E C H N I C A L I N F O R M A -


8885 Date March 1979 111500 32A000 329000 551110 552210 853100 861000

795203 793000 The S A I / E P R I Albedo Information Library. Simmons, G.L. " E P R I - N P - 1 0 1 7 A V A I L A B I L I T Y - S C I E N C E A P P L I C A T I O N S , I'N.C.,

1200 PROSPECT ST., LA J O L L A , C A L I F O R N I A ' 92038

SCA 'O

- 8887 Date March 1979 111210 210000 717000 861000 The Application of Martensitic Stainless Steels in Long Life-

time Fusion First Wall/Blankets. Rosenwasser, S.N;; Mi l ler, P.; Dalessandro, J.A.; Rawls,

J.M.; Toffolov, W.E.; Chen, W. G A - A 1 5 3 5 6 A V A I L A B I L I T Y - N T I S S4.00 GEAC

8916 Date May 1979 421160 511120 861000 The Transmission of Neutrons Through I ron -56 at 24.37

keV. Liou, H.I.; Chrien, R.E.; Block, R.C.; Singh, U.N. N U C L . SCI. ENG. , 70(2), 150-154 B R O O K H

8962 Date Apr i l 1979 111110 111600 210000 521230 719A00 795254 861000



Simmons, G.L. E P R I - N P - 1 0 5 6

385-

A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, INCORPORATED, 1200 PROSPECT ST., LA JOLLA, C A L I F O R N I A 92038

SCA

8992 Date February 1, 1979 ' 112760 422200 522210 841000 853100 861000 870013

870082 Measurement of Number Albedo of Backscattered Photons. Biswas, M. ; Sinha, A.K.; Roy, S.C. N U C L . I N S T R U M . METHODS, 159(1), 157-162 I N D I A r^



Reactor Neutronic Performance. |C3arnes, J.M.; Bishop, B.L.; Santoro, R.T.; Gabriel, T.A.

O R N L / T M - 6 5 4 3 A V A I L A B I L I T Y - N T I S $4.00 OARNL-., " " Q

(< - P

9069 Date Mid-December 1978 111210 210000 32AOOO-521130 810000 861000 717000

795323 Minimizing Radioactivity and Other Features of Elemental

and Isotopic Tailoring of Materials for Fusion Reactors. Conn, R.W.;,Okula, K.; Johnson, A.W. N U C L . T E C H N O L O G Y , ^ . 41(3), 389-400;

U W F D M - 3 0 5 A

U - W I C -

9448 , Date August 1979 111110 122310 32AOOO 521130 793000 794000 719A00


240-Pu, and H /sub 2 / O for Homogeneous Plutonium Systems.

Jenquin, U.P.; Thompson, J.K.; Trapp, T.J.; Kottwitz, D.A. N U R E G / C R - 0 9 6 5 ; PNL -3071 A V A I L A B I L I T Y - D E P . , NTIS, PC A 0 5 / M F A01 P A N L

9455 Date 1979 111110 210000 861000 422110 511120 The Determination of Fast Neutron Fluence in Radiation

Stability Tests of Steel Samples. Hogel, J.; Vespalec, R. ZJE-237 A V A I L A B I L I T Y - S K O D A WORKS, N U C L E A R

POWER C O N S T R U C T I O N DEPT., I N F O R M A -T I O N CENTRE, P L Z E N - C Z E C H O S L O V A K I A

C Z E C H O

9456 Date 1979 111110 210000 719A00 861000 Radiation Damage and Annealing of C r - M o - V Steel. Vacek, M.; Havel, S.; Brunovsky, M . ZJE-239 ' A V A I L A B I L I T Y - S K O D A WORKS, N U C L E A R

POWER C O N S T R U C T I O N DEPT., I N F O R M A -T I O N CENTRE, P L Z E N - C Z E C H O S L O V A K I A

CZECHO

9632 Date March 1980 111110 112400 112500 421140 423250 551120 551110

795209 861000 Neutron and Gamma-Ray Penetrations in Thick Iron. Oka, Y.; An, S.; Kasai, S.; Miyasaka, S.;< Koyama, K. N U C L . SCI. ENG., 73(3), 259-273 JAPAN

9730 Date January 1980 , 112B00 327000 512110 632110 820000 830000 861000 Photon Point Sources-Buildup Factors for A i r , Water, and

Iron. (?!ech. Note);., Chilton, A.B.; Eisenhauer, C.M.; Simmons, G.L. N U C L . SCI. ENG., 73(1), 97-107 U - I L . /

«J 9797 . . Date January 1980

111500 329000 511110 861000 Computational Benchmark Problem for Deep Penetration in

Iron. Hendricks, J.S.; Carter, L.L. L A - 8 1 9 3 - M S A V A I L A B I L I T Y - D E P . , NTIS , PC A 0 6 / M F A01 L O A S L

10006 Date August 1980 111220 329000 521130 853100 861000 795372 Experience with TR IPOL I at O R N L . Cramer, S.N.; Roussin, R.W. O R N L / R S I C - 4 4 , PP.295-304 A V A I L A B I L I T Y - N T I S , PC A16 /MF .A01 O A R N L

10078 Date September 1980 122100 861000 Evaluation of Resonance Parameters for Neutron Interac-

tion with Iron Isotopes for Energies up to 400 keV. Perey, C.M.; Perey, F.G. O R N L / T M - 6 4 0 5 ; ENDF-298 A V A I L A B I L I T Y - N T I S , PC A 0 5 / M F A01

386-

O A R N L

Nickel and Nickel Alloys


8133 Date July 1978 111210 210000 717000 862000 Effccts of Bombarding Ions on the Void Swelling Profile in

Nickel. Whitley, J.B.; Kulcinski, G.L.; Smith, H.V.,Jr.; Wilkes, P. U W F D M - 2 5 2 A V A I L A B I L I T Y - F U S I O N ' R E S E A R C H PROGRAM,


U - W I

8847.'! .4 . . Date September 1978 010000 122100 861000 862000 ^ , Resonance Cross Sections for Structural Material. Frohner, F.H. J CONF-780921, PP.268-287 A V A I L A B I L I T Y - O E C D , 2, Rl/ '- i ANDRE-PASCAL ,


o

9030 Date October 1978 111210 210000 32A000 52113C 717000 861000 862000

870023 870027 793000 The Effects of F c - N i - C o - V Structural Alloys on Fusion

Reactor Neutronic Performance. Barnes, J.M.; Bishop, B.L.; Santoro, R.T.; Gabriel, T.A. O R N L / T M - 6 5 4 3 A V A I L A B I L I T Y - N T I S $4.00 O A R N L ,

Tungsten and Tungsten Alloys




Shin, K.; Hayashda, Y.; Nakamura, T. NUCL. INSTRUM. METHODS, 151(1,2), 271-276 JAPAN "

8733 Date February 1979 112120 410000 712000 863000 Safety Analysis Report for Packaging: The O R N L Tung-

sten-Shielded Cask. Addendum 1, Evans, J.H.; Mouring, R.W. O R N L / E N G / T M - 3 / A 1 A V A I L A B I J i l T Y - N T I S $4.50 O A R N L

Tritium


8251 ? Date November 1978 222000 717000 869999 Trit ium Pathways and Handling Problems in a Laser Fusion

Reactor. ( ) Larsen, E.M.; Abdel-Khal ik, S.I.; Ortman, M.S. NUCL. TECHNOLOGY, 41(1), 12-26 U - W I

i i

8923Date Hemmendinger, A.; Ragan, C.E.;"Wal-lace, J.M. 111210 870003 869999 Trit ium Production in a Sphere of 6 - L i D Irradiated by

14-MeV Neutrons. 1

NUCL. SCL ENG., 70(3), 274-280 A V A I L A B I L I T Y - J U N E 1979 LOASL

9389. . Date October 1979 010000 111210 717100 810000 869999 A Brief Summary of Different Trit ium Sources for a Trit i-

umless Hybrid Reactor. Moses, G.A. UWFDM-317 A V A I L A B I L I T Y - F U S I O N „ ENGINEERING PRO-

GRAM, NUCLEAR ENGINEERING DEPT., UNIVERSITY OF WISCONSIN, MADISON, W I 53706

U - W I

Hydrogen


6627 Date March 1978 122310 312000 521130 719AOO 870092 870013 870001

870008 810000 ,, A Compendium or Energy-Dependent Sensitivity Profiles

for the T R X - 2 Thermal Lattice.

387-

Tomlinson, E.T.; Lucius, J.L.; Drischler, J.D. ORNL-5336 ; ENDF-253 A V A I L A B I L I T Y - N T I S S8.00 O A R N L

7073 Date January 1977 111110 540000 870001 870006 820000 Neutron Thermalization in Hydrogenous Moderators. " Kothari, L.S. NBS SPEC. PUB. 461, PP. 149-162 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

W A S H I N G T O N , D.C. 20402 I N D I A ((

/_>8I13 Date August 1978 122100 870001 Neutron Cross-Sections of Deuterium in the Energy Range

o.opo 1 eV-15 MeV. V ' Bazazyants, N.O.; Zabrodskaya, A.S.; Larina, A.F.; Nikola-

ev, M .N . . INDG(CCP) - 107/L A V A I L A B I L I T Y - I A E A NUCLEAR DATA SECTION,

K A R N T N E R R I N G 11, Ay, 1010 V I E N N A IAEA °

JJ C> - „



Dimbylow, P.J. NRPB-R78 . A V A I L A B I L I T Y - H M S O E N G L A N

o Lithium


j j 6247 Date December 1977 l l i ' 210 32A000 210000 521130 522130 531000 532000

717000 793000 795254 810000 861000 870003 , Nuclear Performance Calculations for the ELMO Bumpy


6522 Date January 1978 111210 122110 122310 32A000 321130 717000 795042


Neutronics Data. (Thesis) Reupke, W.A. L A - 7 0 6 7 - T A V A I L A B I L I T Y - N T I S LOASL u \ \

6763 Date March 1978 122100 870003 Cross Sections for the 7 -L i (n ,xn) and 7-Li(n,n'gamma)

Reactions Between 1 and 20 MeV. Morgan, G.L. O R N L / T M - 6 2 4 7 , ., A V A I L A B I L I T Y - N T I S $4.50 O A R N L

<f 6877 Date July 1978 111210 421160 511110 511120 717000 870003 Neutron Spectra and Tr i t ium Production Measurements tin

' i a Lithium Sphere to Check Fusion Reactor Blanket Cal-culations.

Bachmann, H.; Fritscher, U.; Kappler, F.W.; Rusch, D.; Werle, H.; Wiese, H.W.

NUCL. SCI. ENG., 67(1), 74-84 G E R M A N

7031 Date September 1976 111210 122310 312000 37!AOOO 511110 870003 717000 Neutronic Data Consistency Analysis for Lithium Blanket

Shield Design. Reupke, W.A.; Muir, D.W. CONF-760935-P3, PP. 861-871; L A - U R - 7 6 - ' 2 0 9 2 A V A I L A B I L I T Y - N T I S U - G A

7033 Date September 1976 111210 32A000 521230 422130 717000 717100 870003

870006 870092 793000 795254 Fission-Rate Distributions in Lithium and Hybr id Fusion

Blanket Assemblies. Maekawa, H.; Seki, Y.

'CONF-760935-P3, PP. 883-894 A V A I L A B I L I T Y - N T I S JAPAN

1 8428 Date October 1978

111210 329000 32A000 422110 511120 870003 881000 Tri t ium Production in a Sphere of 6 - L i D Irradiated by

14-MeV Neutrons. Hemmendinger, A.; Ragan, C.E.; Shunk, E.R.; Ellis, A.N.;

Anaya, J.M.; Wallace, J.M.

LA-7310 ,, Beryl l ium A V A I L A B I L I T Y - N T I S L 0 A S L CATEGORY N U M B E R 870004



RATORY L A L L

7"'8465 Date June 1978 111210 210000 717000 861000 870003 810000 Materials Considerations for Inertially-Confined Fusion

Reactors ( ICFR). Hovingh.J. " UCRL-81206 A V A I L A B I L I T Y - L A W R E N C E L IVERMORE LABO-

RATORY L A L L

8923Date Hemmendinger, A.; Ragan, C.E.; Wal-lace,'-'J.M. 0 "i, , . 11 111210 870003 869999 Trit ium Production in a Sphere of 6 - L i D Irradiated by

14-MeV Neutrons. NUCL. SCI. ENG., 70(3), 274-280 A V A I L A B I L I T Y - J U N E 1979 LOASL

8953 Date May 1978 111210 32A000 329000 421130 521230 795203 795254

870003 870006 Measurements and Calculations of Fast Neutron Spectra in

a Graphite-Reflected Lithium Assembly. Itoh, S.; Seki, Y.; Maekawa, H. CONF-780508,VOL. l , PP.385-393 A V A I L A B I L I T Y - D E P . , NTIS JAPAN


8f0000 870003 Thermal-Hydraul ic and Neutronic Considerations for

Designing a Lithium-Cooled Tokamak Blanket. Mikic, B.; Todreas, N. COO-2431 - 2 AVAILABIL ITY ; -DEP. , NTIS, PC A 0 6 / M F A01 U - M A ^

8389 Date 1978 112730 329000 522110 522210 870004 870006 853100




8924 Date June 1979 111210 717000 870004 Neutron Multiplication Studies in Beryllium for Fusion

Reactor Blankets. (Tech. Note) Basu, T.K.; Nargundkar, V.R.; Cloth, P.; Filges, D.; Tacza-

nowski, S. NUCL. SCI. ENG., 70(3), 309-313 G E R M A N

9369." Date July 1979 122100 870004 w Evaluated Data for n plus 9 -Be Reactions. Young, P.G.; Stewart, L. L A - 7 9 3 2 - M S ; ENDF-283 A V A I L A B I L I T Y - N T I S ,, LOASL

Carbon


6398 Date Dec. 1977 719DOO 32A000 870006 Neutron Dosage at Steel Components in the THTR. Wahsweiler, H.G.; Hehn, G. CONF-770401, PP.280-287 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE

"DR., PRINCETON, NJ 08540 G E R M A N

6734 Date May 1978 111210 122310 312000 521130 795204 717000 870006

870092 861000 Cross-Section Sensitivity Analysis of 235-U and 238 -U


389-


70/(3- Date January 1977 }r

6767. Date October 1977 111210 210000 717000 870CC6 870042 Response of First Walls in Inertial Confinement Reactors to

Thermonuclear Radiation. Hunter, T.O.; Abdel-Khal ik , S.I.; Kulcinski, G.L. U W F D M - 2 2 1 A V A I L A B I L I T Y - F U S I O N RESEARCH 'PROGRAM,

UNIV . OF WISCONSIN, MADISON, WISCONSIN 53706

U - W I

7025 Date September 1976 111210 521130.71-7000 870006 First Wall Studies of a Laser-Fusion Hybrid Reactor


^ 7032 Date°September 1976

111210 112120 230000 32A000 795217 795254 717000 870006 810000

Neutronic Performance of Graphite Fusion Reactor Blan-kets Containing Sr -90 and 1-129.

Parish, T.A.; Davidson, J.W.; Draper, E.L.,Jr. CONF-760935-P3, PP. 873-882 A V A I L A B I L I T Y - N T I S U - T X

111110 540000 870001 870006 820000 Neutron Thermalization in Hydrogenous Moderators. Kothari, L.S. NBS SPEC. PUB. 461, PP. 149-162 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

WASHINGTr-»! , D.C. 20402 I N D I A

7101 Date July 1976 111500 321000 323000 511 110 861000 870006 Asymptotic Characteristics of the Distribution of Fast Neu-

tron fluxes in Heterogeneous Shielding. • Germogenova, T.A.; Konovalov, N.V.; Suvorov, A.P. E R D A - T R - 1 2 5 , PP. 25-34 A V A I L A B I L I T Y - N T I S

, RUSSIA • ^

1 8389 Date 1978 112730 329000 522110 522210 870004 870006 853100


' : Gamma Quanta Back Scattered from Different Types of Barriers.


8523 Date December 1978 113100 410000 424000 870006

c X - R a y Transmission/Scattering Technique for Thick-ness-Independent Density Measurement.

Giacomelli, E.J. Y-2166 A V A I L A B I L I T Y - N T I S UNCAR

703 3 Date September 1976 111210 32A000 521230 422130 717000 717100 870003


Blanket Assemblies. Maekawa, H.; Seki, Y. CONF-760935-P3, PP. 883-894 A V A I L A B I L I T Y - N T I S JAPAN r,

i f 703 4 '""T Date September 1976

111110 210000 870006 717000 Neutron Irradiation Effects on Graphite Cloth. Gray, W.J. CONF-760935-P3, PP. 1049-1059 A V A I L A B I L I T Y - N T I S BANW



Dimbylow, P.J. NRPB-R78 A V A I L A B I L I T Y - H M S O ENGLAN

8823 Date September 1978 122100 870006 Neutron Scattering Cross Sections of Carbon Below 2 MeV

Recommended from R - M a t r i x Fits to Data. Fu, C.Y.; Perey, F.G. A T O M I C DATA A N D NUCL. DATA TABLES, 22(3),

249-267

390-

O A R N L „

" " > v

'I 8829 Date 1978 2B00 329000 522110 861000 870006 870013 870050

' ' . 870082 The Calculation of Gamma-Rays Albedo by the

Monte-Carlo Method. Seda, J.; Kluson, J.; Cechak, T. INT. J. APPL. RADIAT. ISOTOP, 29, 419-422 CZECHO

8840 Date September 1978 010000 122100 122310 870006 870092 Covariance Matrices of Experimental Data. Perey, F.G. CONF-78092L PP.104-115 " A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,



ments. West, D.; Sherwood, A.C. CONF-780921, PP.610-614 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,


8854 Date September 1978 010000 122100 122200 220000 312000 32A000 760000



Pfister, G.; Hehn, G.; Mattes, M.; Friedlein, H.P. CONF-780921, PP.621 -627 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,


8951 Date May 1978 111210 210000 717000 870006 870014 An Assessment of Carbon and Silicon Carbide as First Wall

Materials in Inertial Confinement Fusion Reactors. Hopkins, G.R.; Price, R.J.; Bullock, R.E.; Dalessandro, J.A.;

Hovingh, J. CONF-780508,VOL.1, PP.324-333 A V A I L A B I L I T Y - D E P . , NTIS GEAC

8953. Date May 1978 111210 32A000 329000 421130 521230 795203 795254

870003 870006 , „ Measurements and Calculations of Fast Neutron Spectra in

a Graphite-Reflected Lithium Assembly. Itoh, S.; Seki, Y.; Maekawa, H. CONF^780508,VQL. l , PP.385-393 A V A I L A B I L I T Y - D E P . , NTIS " JAPAN

9142 Date September 1979 111220 421130 421200 511120 512110 329000 870006 Penetration of Secondary Neutrons and Photons from a

Graphite Assembly Exposed to 52 -MeV Protons. Shin, K..; Uwamino, Y.; Yoshida, M.; Hyodo, T.; Nakamura,

T. NUCL. SCI. ENG., 71(3), 294-300 JAPAN

° „ 0

9723 Date January 1980 210000 717000 8'?0006 870014 Radiation Damage by High-Energy Neutrons. Primak, W. NUCL. SCI. ENG., 73(1), 29-34 A R G O N N

0

10074 Date July 1980 111110 112760 870006 795217 719B00 Carbon-14 Production in the Peach Bottom HTGR Core. Wichncr, R.P.; Dyer, F.F. ORNL-5597 A V A I L A B I L I T Y - N T I S O A R N L

Nitrogen

CATEGORY N U M B E R 87000'^

9192 Date May 10, 1977 111110 111210 112110 32A000 511110 512110 512210


the Californium Tank Experiment for Comparison with 2" x 2" NE-213 Detector Measurements. 1

Straker, E.A.; Gritzner, M.L.; Harris, L,Jr . ; Schanzler, L. S A I - 7 7 - 6 5 7 - L J A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, INC.,

P.O. BOX 2351, 1200 PROSPECT ST., LA JOLLA, CAL IFORNIA 92037

SCA

391-

9825 Date March 1980 112720 210000 717000 870007 Gamma Irradiation of Nitrate-Based Salts. Breon, S.R.; Chellew, N.R.; Clemmer, R.G.; Hoh, J.C. A N L / F P P / T M - 1 2 9 A V A I L A B I L I T Y - N T I S , PC A 0 3 / M F A01 A R G O N N

Oxygen


6627 Date March 1978 122310 312000 521130 719A00 870092 870013 870001


for the T R X - 2 Thejmal Lattice. Tomlinson, E.T.; Lucius, J.L.; Drischler, J.D. ORNL-5336 ; ENDF-253 A V A I L A B I L I T Y - N T I S $8.00 O A R N L



Cramer, S.N;; Oblow, E.M. O R N L / T M - 5 5 3 5 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8111 Date June 1978 713000 870008 870096 Subcritical Reactivity Monitoring: Neutron Yields from

Spontaneous (alpha,n) Reactions in FFTF Fuel. Ombrellaro, P.A.; Johnson, D.L. H E D L - T M E - 7 8 - 3 9 A V A I L A B I L I T Y - D E P . , NTIS (U.S. SALES O N L Y ) HANFOR "




Plister, G.; Hehn, G.; Mattes, M.;'Friedlein, H.P. CONF-780921, PP.621-627 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,


Fluorine


6702 Date 1978 111210 122100 870009 Evaluation of Neutron Cross Sections for 19 —F in the

Energy Range from 100 keV to 20 MeV. , Sugi, T. O R N L - T R - 4 6 0 5 A V A I L A B I L I T Y - N T I S J A P A N " ;

/

Sodium

CATEGORY NUMBER 870011 w

6382 Date Dec. 1977 312000 713000 861000 870011 Fast Reactor Shield Sensitivity Studies for

Steel-Sodium-Iron Systems. ,, Oblow, E.M.; Weisbin, C.R. CONF-770401, PP.140-148 A V A I L A B I L I T Y - S C I E N C E PRESS.I/8 BROOKSTONE


S£


Hydrogen, Carbon, Nitrogen and Oxygen in the Energy, Range 2O-~50 MeV.

Dimbylow, P. a NRPB-R-78-^ ji A V A I L A B I L I T Y - H M S O 7

E N G L A N

6394 Date Dec. 1977 713000 721200 870011 Q Neutron Transport Through Straight and Once Bent K.

Sodium Pipe in Shielding of Fast Reactors. Burian, J.; Jansky, B.; Osmera, B.; Otopal, P.; Rataj, J.;


DR., PRINCETON, NJ 08540 RUSSIA V Y -

392-


with Various Source Spectra on H A R M O N I E and TAPIRO. « ^

it Calamand, D.; Desprets, A.; Rancurel, H, j^ ienot , R.; Esti-

ot, J.C.; Trapp, J.P.; Bargellini, M.L^;'Bozzi, L.; Martini, M.; Moioli, P.; Antonini, D.; De Carti, A.; Rado, V.

CONF-770401, PP.795-803 A V A I L A B I L I T Y - S C I E N C E P R E S S , 8 BROOKSTONE

DR., PRINCETON, NJ 08540 F R A N C E a

6459 C< Date Dec. 1977

< 122310 861000 870011 Use of Integral Data for the Prediction of Neutron Propaga-

t ion1^ Iron-Sodium Mixtures. Estiot, J.C.; Trapp, J.P.; Palmiotti, G.fSalvatores, M. CONF-770401, PP.804-811 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6462 Date Dec. 1977 020000 111110 421140 551120 795254 795222 861000


Iron at YAYOI . Oka, Y.; An, S.; Kasai, S.; Sakata, S.; Miyasaka, S.; Koya-



6880 Date July 1978 122310 870011 794000 Interactive Graphics Interpretation of Calculation Measure-


Parvez, A.; Becker, M. NUCL. SCI. ENG., 67(1), 130-136 U - N Y

8580 ' Date 1977 111110 122310 327000 511110 861000 870011 Neutron Slowing Down and Transport in Monoisotopic

Media with' Constant Cross Sections or with a Square-Well Minimum.

Peng, W.H. COO-2509-6 A V A I L A B I L I T Y - D E P . , NT IS <• U - N Y

8969 Date May 1979 111110 329000 721100 870011 Contributon Monte Carlo. Dubi, A.; Gerstl, S.A.W. L A - 7 8 4 9 - M S A V A I L A B I L I T Y - N T I S LOASL „

9707 Date January 1980 111210-311000 329000 551110 870011 Application of Biasing Techniques to the Contributon Monte

Carlo Method. Dubi, A.; Gerstl, S.A.W. LA-8201 - MS A V A I L A B I L I T Y - D E P . , NTIS, PC A03 /MF A01 LOASL


Through a One-Bend Sodium Duct. Sartori, E. ORNL /RS IC -44 , PP.219-229 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 FRANCE

10005 Date August 1980 010000 329000 721100 853100 870011 Deep-Penetration Calculations. Thompson, W.L.; Deutsch, O.L.; Booth, T.E. ORNL /RS IC-44 , PP.267-294 A V A I L A B I L I T Y - N T I S , PC A 1 6 / M F A01 LOASL

8577 Date November 1978 111110 32AOOO 122310 3120$) 551110 551200 793000


"10076 Date September 1980 122100*8700l'l An Evaluation of Cross Sections for Neutron-Induced

Reactions in Sodium. Larson, D.C. ORNL-5662; ENDF-299 A V A I L A B I L I T Y - N T I S , PC A 0 9 / M F A01 O A R N L

o 393

Magnesium



ments. West, D.; Sherwood, A.C. CONF-780921, PP.610-614 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL ,


Shin, K.; Hayashda, y . ; Nakamura, T. , NUCL. INSTRUM. METHODS, 151(1,2), 271-276 JAPAN

6869 E>ate May 1978 10-2200 329000 512110 512210 820000 861000 870013

"'870082 Shielding Study of Bremsstrahlung in Bulk Media with Elec-

trons. Part I I : Spatial Bremsslrahlung,Distribution in Water, Aluminum, Iron and'Lead Bombarded jj»y 22 MeV Electrons.

Nakamura, T:; Hirayama, H.; Shin, K. NUCL. INSTRUM. METHODS, 151(1,2), 277-284, JAPAN

8902 >ry Date 1979 121100 122100 870012 870013 870029 870040 Evaluation of the Cross - Sections for the Reactions 24 - Mg

(n,p) 24-Na, 6 4 - Z n (n,p) 64-Cu, 63-Cu (n,2n) 62-Cu and'_C0-Zr (n,2n) 89-Zr .

Tagesen, S.; Vonach, H.;,Strohmaier, B. PHYSICS D A T A - N R . 13-1 A V A I L A B I L I T Y - I S S N 0344-8401 GERMAN

, 7115 Date July 1976 112B0"B* 421200 522210 610000 820000 870013 861000

870082 „ Differential Characteristics of the Energy Albedo of

Gamma-Quanta for Organic Mediums. Viktorov, A.A.; jyfashkovich, V.P. ERDA - TR - J/ifC PP. 152-156 A V A I L A B I L I T Y - N T I S RUSSIA

Aluminum



Test Reactor. Fillo, J.A.; Powell, J.R.; Benenati, R.; Makowitz, H. BNL-23411; CONF-771029-132 A V A I L A B I L I T Y - D E P . , NTIS C

BROOKH

6627 Date March 1978 122310 312000 521130 7;°AV„ ,70092 870013 870001

870008 810000 V A Compendium of Energy-Dependent Sensitivity Profiles

for the T R X - 2 Thermal Lattice. u " " Tomlinson,. E.T.; Lucius, J.L.; Drischler, J.D. O R N L - 5 3 | 6 ; ENDF-253 A V A I L A B I L I T Y - N T I S $8.00 O A R N L s

6868. . . 5 Date May 1978 112200 329C0'5v863000 870013 870082 a

Shielding Study of Bremsstrahlung in Bulk Media with Elec-trons. Part rf I: Monte Carlo Calculations of Thick-Target Bremsstrahlung Spectrum. <

7120. . ? Date July 1976 111110 421150 511120 861000 870013 870022 Application of Hydrogen Spectrometer for Spectral Analysis



o - o

8500 <5 . S a t e June 1977 111110 122110 324000 326000* 32'7t)00 820000 861000.

870013 870092 511110'521130 Moments of the Fourier-Transformed Neutron Slow-

ing-Down Kernel: The Computer Code " M A G G I 2 " . Gado, J.; Keresziuri, A. t,o °0i, KFKI -1977-44 <> „ , ' , ' , ! " A V A I L A B I L I T Y - K O Z P O N T I F I Z I K A I KUTATO * INTEZET, BUDAPEST" j(HLJNGARY) ISBN " 9633712637 0 • „ n \ J

H'UNGAR 111 • 4 V

>n • o x • ; „ 8829 .1 '. ."n Date 1978

112B00 329000 522110 861000 870006 870013 870050 1 870082 ' i' " o 0

The Calculation of Gamma-Rays Albedo by the Monte-Carlo Method. "

Seda, J.; Kluson, J.; Cechak, T. <?

INT . J. APPL. RAD I AT. ISOTOP., 29, 419-422 CZECHO

8852. Date September 1978 010000 111220 870006 870012 870013 870014 Neutron Yields from (alpha,n) Reactions in the Light Ele-

ments. West, D.; Sherwood, A.C.' 1

CONF-780921, PP.610-614 ,, A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, FRANCE „ ° E N G L A N

^8902 Date 1979" 121100 122100 870012 870013 870029 870040 o Q

Evaluatiori-of the Cross-Sections for the Reactions 2 4 - M g ^ (n,p) 24-Na, 6 4 - Z n (n,p) 64-Cu, 63-Cu (n,2n)' < 62 -Cu and 9 0 - Z r (n,2n) 89 -Z r . o '

Tagesen, S.; Vonach, H.; Strohmaier, B. . „ PHYSICS D A T A - N R . I 3 - 1 A V A I L A B I L I T Y - I S S N 0344-8401 G E R M A N

a-

ft

Silicon


o"8753 Date Apr i l 1979 210000 870014 u Transfer Damage Characterization by Neutron displace-

ment Cross Section isi Silicon: Experimental. (

Verbinski, V.V.; Cassapakis, C.; Pease, R.L.; Scott, H.L. NUCL . SCI. ENG., 70(1), 66-72 SCA

0 8852 Date September'1978

010000 111220 870006 870012 870013 870014 Neutron Yields from (alpha,n) Reactions in the Light Ele-

" ments. ° V'esl, D.; Sherwood, A.C. CONF-780921,,PP.610-614 A V ^ \ I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

(75775 PARIS CEDEX 16, FRANCE • E N G L A N

u

8920 . Date Mav 1979 112BOO 512110 632110 820000 861000 870013 On the Polynomial Form of Gamma-Ray Buildup Factor -

Functions; Metghalchi, M. 0

NUCL. SCI. ENG., 70(2), 207-209 „ I R A N

8992. . Date February 1, 1979 112760 422200 522210 841000 853100 861000 870013

870082 Measurement of Number Albedo of Backscattered Photons. Biswas, M.; Sinha, A.K.; Roy, S.C. NUCL. INSTRUM. METHODS. 159(1), 157-162 I N D I A

CJ (8951 - Date May 1978 I i 1210210000 717000 870006 870014 An Assessment of Carbon and Silicon Carbide as First Wall

| o ?; Materials in Incrtial Confinement Fusion Reactors. Hopkins,iG.R.; Price, R.J.; Bullock, R.E.; Dalessandro, J?A.;

o rHovingh, J. "CONF-780508, VOL.1, PP.324-AV A l L A B I L I T Y - DEP., NTIS GEAfc

333

a o O 9123 Date January 1980

"210000 717000 870006 870014 Radiation Damage by High-Energy Neutrons. Primak, W. NUCL. SCI. ENG.. A R G O N N

73(1), 29-34

9494 Date 1979 111210 210000 717000 870013 o Fusion-Fission Neutron Damage Ratio for Alumina. Evans, B.D.; Stapelbroek, M. C O N F - 7 9 0 1 2 5 , PT.A, PP.497-502; J. N U C L E A R

MATER. . 85 A.ND 86, A V A I L A B I L I T Y - N O R T H - H O L L A N D PUBLISH-

ING C O M P A N Y - A M S T E R D A M NAVY

Chlorine


6580. . ': Date March 1978] 325000 540000 870017 Expansion About a Local Maxwellian for Evaluating the

Spatially Dependent Neutron Spectrum. (Tech. Note) Molinari, V.G.; Simonini, R. NUCL. SCI. ENG., 65(3), 560-565 I T A L Y

if 395 o

Potassium

CATEGORY NUMBER 870019 \)

6744 Date May 1978 111110 111210 111 ifjO 210000 121100 870019 Fusion/Fission Damage Ratios, for-Neii tron - Induced Dis-

placement Damage in SilifionT" Van Antwerp, W.R.; Hollandsworth, C.E.; Youngblood, J.E. A R B R L - M R - 0 2 8 3 6 A V A I L A B I L I T Y - N T I S A R M Y

Titanium


7120 Date July 1976 111110 421150 511120 861000 870013 870022 Application o^Hydrogen Spectrometer for Spectral Analysis



o

Jones, R.H.; Leonard, B.R.,Jr.; Johnson, A.B.,Jr. EPRI-AP-1433 A V A I L A B I L I T Y - R E S E A R C H REPORTS CENTER,

BOX 50490, PALO ALTO, CA 94303 , B A N L "

^Vanadium


8375. . . !' Date February 1978 111210 421160 329000 511120 861000 870022 Pulsed Sphere Measurements for Weapons and Fusion

Reactor Design. UCRL-52000-78-2 , PP.9-14 A V A I L A B I L I T Y - D E P . , NTIS LALL

9492 Date 1979 l t l 1 1 0 210000 717000 870022 870023 870041 New Approach to Simulation of Helium and Simultaneous

i^vDamage Production in Fusion Reactors - In Reactor "Tri t ium Trick. ,,


MATER./85 A N D 86, A V A I L A B I L I T Y - N O R T H - H O L L A N D PUBLISH- •


9965 Date June 1980 111210 210000 717000 870022 ; Assessment of Titanium Alloys for Fusion.. Reactor

First - Wall and Blanket Applications (Research Project 1045-3) Final Report.

6635 ! . f Date January 1978 , 111210 111220 210000 717000 870023 870029 870041 Exploratory Experiments Comparing Damage Effects of

High-Energy.JNeutrons and Fission-Reactor Neu-trons in Metal. „

Mitchell, J.B. UCRL-52,388' „ ,, A V A I L A B I L I T Y - L A W R E N C E

CALIFORNIA UNIV. L A L L

L IVERMORE LAB.,

8411-3 D a t e Apri l 1978 111210 210000717000 870023 ^ Technical Assessment of Vanadium-Base Alloys for Fusion

Reactor Applications. Vol. l . Assessment of Data Base, Needs and Recommendations. Final Report.^

Gold," R.E.; Harrod, D.L.; Ammon, R.L.; Buckman;, R.W.,Jr.; Svedberg, R.C. i f "

COO-4540 - l (VOL . l ) 0

A V A I L A B I L I T Y - N T I S S5.25 WEE°



Reactor Neutronic Performance. Barnes, J.M.; Bishop, B.L.; Santoro, R.T.; Gabriel, T.A. ORNL/TM-6543 A V A I L A B I L I T Y - N T I S S4.00 OARNL

9492 Date 1979 111110 210000 7,17000 870022 870023 870041 New Approach to Simulation of Helium and Simultaneous

Damage Production in Fusion Reactors - In Reactor Tritium Trick.


MATER., 85 A N D 86, A V A I L A B I L I T Y - NORTH - H O L L A N D PUBLISH-

ING COMPANY - A M S T E R D A M „ ,

%

ft

396 a

U - M A

Chromium


9828. i Date February 1979 122100 870024 Evaluation of Natural Chromium Neutron Cross Sections

for E N D F / B - V . Prince, A.; Burrows, T.W. BNL-NCS-51152 ; ENDF-286 A V A I L A B I L I T Y - N T I S $6.00 BROOKH

Cobalt


9030 Date October 1978 111210 210000 32A000 521130 717000 861000 862000


Rcactor Neutronic Performance. Barnes, J.M.; Bishop, B.L.; Sanloro, R.T.; Gabriel, T.A. O R N L / T M - 6 5 4 3 A V A I L A B I L I T Y - N T I S $4.00 O A R N L

Copper


Hunter, T.O.; Kulcinski, G.L. U W F D M - 2 3 3 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,


U - W I


Electron Irradiations. Goldstone, J.A. L A - 7 4 2 4 - T ; THESIS A V A I L A B I L I T Y - N T I S LOASL

9 8859 Date September 1978

122310 111210 329000 421130 421200 511120 512220 717000 717000 870090 870092 870029 870041

Neutron Spectra from Materials Used in Fusion and Fusion-Fission Hybrid Reactors.

Hansen, L.F.; Wong, C.; Komoto, T.; Pohl, B.A. CONF-780921, PP.766-77I A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL ,


8902 Date 1979 121100 122100 870012 870013'870029 870040 Evaluation of the Cross-Sections for the Reactions 24- Mg

(n,p) 24-Na, 6 4 - Z n (n,p) 64-Cu, 63-Cu (n,2n) 62-Cu and 9 0 - Z r (n,2n) 89-Zr .

Tagesen, S.; Vonach, H.; Strohmaier, B. PHYSICS D A T A - N R . 1 3 - 1 A V A I L A B I L I T Y - I S S N 0344-8401 G E R M A N

6635. . Date January 1978 .111210 111220 210000 717000 870023 870029 870041 Exploratory Experiments Comparing Damage Effects of


Mitchell, J.B. UCRL-52,388 A V A I L A B I L I T Y - L A W R E N C E L IVERMORE LAB.,

CAL IFORNIA UNIV . L A L L

6770. Date Apri l 1978 111210 210000 717000 870029 Surface Damage and Thermal Effects from Transient Ther-

monuclear Radiation in Inertial Confinement Fusion Reactors.

9387 Date September 1979 111110 111210 210000 870029 870079 The Radiation Induced Order-Disorder Transformation in

Cu/sub 3/Au. Zee, R.; Wilkes, P. UWFDM-314 A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-

GRAM, NUCLEAR ENGINEERING DEPT., UNIVERSITY OF WISCONSIN, MADISON, WI 53706

U - W I

9495 Date 1979 111210 111220 210000^17000 870029 870079 The Nature of High Energy Neutron Damage in Copper and

Gold. ' s'

397 o

Narayan, J.; Ohr, S.M. CONF-790125, PT.A, PP.515-519; J. NUCLEAR


I N G COMPANY - AMSTERDAM O A R N L

Krypton


9274 Date January 1979 122100 870036 ( )

E N D F / B - V Neutron Cross Section Evaluation for the Krypton Isotopes.

Prince, A. BNL-NCS-51028 ; ENDF-279 A V A I L A B I L I T Y - N T I S $5.25 BROOKH

Zirconium

Niobium


6463 Date Dec. 1977 122310 870041 870098 430000 794000 Integral Tests of Niobium Cross Sections Through Simulta-





High - Energy Neutrons and Fission-Reactor Neu-trons in Metal. , ,

Mitchell, J.B. » UCRL-52,388 / A V A I L A B I L I T Y - L A W R E N C E L IVERMORE LAB.,

CAL IFORNIA UNIV . L A L L "


8902 Date 1979 121100 122100 870012 870013 870029 870040 Evaluation of the Cross-Sections for the Reactions 2 4 - M g

(n,p) 24-Na, 6 4 - Z n (n,p) 64-Cu, 63-Cu (n,2n) 62 -Cu and 9 0 - Z r (n,2n) 89-Zr .

Tagesen, S.; Vonach, H.; Strohmaier, B. PHYSICS D A T A - N R . 1 3 - 1 A V A I L A B I L I T Y - I S S N 0344-8401 G E R M A N

9021 Date Apri l 1979 122100 870040 Calculation of Neutron Cross Sections on Isotopes of

Yttr ium and Zirconium. Arthur, E.D. L A - 7 7 8 9 - M S A V A I L A B I L I T Y - N T I S LOASL


14-MeV Neutrons from Critical-Property Changes in Irradiated Nb/SUB3/Su.

Snead, C.L,Jr.; Parkin, D.M.; Guinan, M.W.; Van Konynenburg, R.A.

CONF-760935-PI , PP. 229-237 A V A I L A B I L I T Y - N T I S BROOKH

8620 Date 1977 111110 210000 422110 810000 870041 Application de la Reaction 9 3 - N b (n,n') 93m-Nb a la

Dosimetric des Irradiations de Materiaux. Lloret, R. r

EUR-5667E/F,PT.I, PP.747-756(IN FRENCH); CONF-750935,PT.I, PP.747-756(IN FRENCH)

A V A I L A B I L I T Y -OFF ICE FOR OFFICIAL PUBLICA-TIONS OF T H E EUROPEAN' COMMUNIT IES, BOITE POSTAL 1003 - LUXEMBOURG

FRANCE

# 8621 Date 1977 lYl 110 210000 422110 810000 870041 Utilization of the Reaction 9 3 - N b (n,n') 93m-Nb for Fast

Neutron Flucnce Measurement.

398-

Hegedus, F. EUR-5667^/F,PT. I , PP.757-762;^



SWITZ

8662 Date February 1979 111110 32AOOO 312000 421130 511110 870041 794000


Cross Sections. -Ingersoll, D.T.; Wehring, B.W. ORNL/RSIC-42 , PP.179-189 A V A I L A B I L I T Y - N T I S O A R N L

8859 Date September 1978 122310 111210 329000 421130 421200 511120 512220


Fusion-Fission Hybrid Reactors. Hansen, L.F.; Wong, C.; Komoto, T.; Pohl, B.A. CONF-780921, PP.766-771 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,


9492 " Date 1979 111110 210000 717000 870022 870023 870041 New Approach to Simulation of Helium and Simultaneous

Damage Production in Fusion Reactors - In Reactor Trit ium Trick.




Molybdenum


U - W I

7007 Date September 1976 111110 210000 870042 Neutron-Irradiation Effects on Molybdenum and Molyb-

denum Alloys. Bcntley, J.; Wiflen, F.W. CONF-760935-P1, PP. 209-218 A V A I L A B I L I T Y - N T I S O A R N L

Silver



0.1 and 1.0 MeV with Silver. Kondo, I. EUR-5667E/F.PT.I, PP.579-590;


T IONS OF THE EUROPEAN COMMUNIT IES, BOITE POSTAL 1003 - LUXEMBOURG

JAPAN

Tin



14-MeV Neutrons from Critical-Property Changes in Irradiated Nb/SUB3/Sn.

Snead, C.L.,Jr.; Parkin, D.M.; Guinan, M.W.; Van Konynenburg, R.A.

CONF-760935-P1, PP. 229-237 A V A I L A B I L I T Y - N T I S ' BROOKH


Thermonuclear Radiation. -Hunter, T.O.; Abdel-Khal ik, S.I.; Kulcinski, G.L. U W F D M - 2 2 1 A V A I L A B I L I T Y - F U S I O N RESEARCH PROGRAM,

UNIV . OF WISCONSIN, MADISON, WISCONSIN 53706

8389 Date 1978 112730 329000 522110 522210 870004 870006 853100




o 399

8829 Date 1978 1I2B00 329000 522110 861000 870006 870013 870050


Monte-Car lo Method. Seda, J.; Kluson, .1.; Cechak, T. INT . J. APPL. RAD1AT. ISOTOP., 29, 419-422 CZECHO

Tantalum


8097 Date September 1978 112500 121100 870073 The Dependence of the Gamma- Ray Spectral Shape on the

Neutron Energy Averaging Interval Size for the 181-Ta(n,gamma) Reaction. (Tech. Note)

Stelts, M.; Browne, J.C. NUCL. SCL ENG., 67(3),344-347 L A L L

Gold


6821 Date 1978 122100 870079 Evaluation of the Capture Cross Section of 197-Au. Mughabghab, S.F. IAEA-208 , VOL.I , PP.395-406 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE BROOKH

9093 Date 1979 122110 32A000 794000 870079 Range Calculations Using Multigroup Transport Methods. Hoffman, T.J.; Robinson, M.T.; Dodds, H.L.,Jr. CONF-7,90125-57 A V A I L A B I L I T Y - D E P . , NTIS O A R N L

9387 Date September 1979 111110 111210 210000 870029 870079

<• The Radiation Induced Order-Disorder Transformation in Cu/sub 3 /Au.

Zee, R.; Wilkes, P. « U W F D M - 3 1 4

A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-GRAM, NUCLEAR ENGINEERING DEPT., UNIVERSITY OF WISCONSIN, MADISON, WI 53706

U - W I

9495 Date 1979 111210 111220 210000 717000 870029 870079 The Nature of High Energy Neutron Damage in Copper and

Gold. Narayan, J.; Ohr, S.M. CONF-790125, PT.A, PP.515-519; J. N U C L E A R


ING COMPANY - A M S T E R D A M O A R N L

!. Lead


6472 Date Dec. 1977 112400 112500 512220 820000 861000 870082', Secondary Gamma Radiation Study in Reactor Shielding. Abagjan, A.A.; Gasnikov, N.K.; Germogenova, T.A.;

Bubinin, A.A.; Zhuravlyov, V.I.; Kolevatov, Yu.J.; Kurachenko, Yu.A.; Mashkovich, V.P.; Sakharov, V.K,





Shin, K.; Hayashda, Y.; Nakamura, T. NUCL. INSTRUM. METHODS, 151(1,2), 271-276 JAPAN

6869 Date May 1978 112200 329000 512110 512210 820000 861000 870013



Nakamura, T.; Hirayama, H.; Shin, K. NUCL. INSTRUM. METHODS, 151(1,2), 277-284 JAPAN

400-

t\ 7069 Date January 1977

111110 32AOOO 423140 511110 511120 793000 795254 842000 870098 861000 870082

Transmission of 252-CF Fission Neutrons Through Vari-" ous Shields.

Song, Y.T. NBS SPEC. PUB. 461, PP. 119-123 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


7115 Date July 1976 112B00 421200 522210 610000 820000 870?13 861000


Gamma-Quanta for Organic Mediums. Viktorov, A.A.; Mashkovich, V.P. E R D A - T R - 1 2 5 , PP. 152-156 A V A I L A B I L I T Y - N T I S RUSSIA


Materials of Shielding Placed in Light Mediums. '•>*' Avayev, V.N.; Yefimov, Ye.P. E R D A - T R - 1 2 5 , PP. 169-175 A V A I L A B I L I T Y - N T I S RUSSIA

Seda, J.; Kluson, J.; Cechak, T. INT. J. APPL. RADIAT. 1SOTOP., 29, 419-422 CZECHO

8992 Date February 1, 1979 112760 422200 522210 841000 853100 861000 870013

870082 Measurement of Number Albedo of Backscattered Photons. Biswas, M.; Sinha, A.K.; Roy, S.C. NUCL. INSTRUM. METHODS, 159(1), 157-162 I N D I A

9288 Date 1978 111110 111210 329000 795017 870082 511110 Calculated Leakage Spectrum from 238-U Spheres Con-

taining Sources of 14-MeV or Fission Neutrons for Radiobiological Applications.

Ing, H.; Cross, W.G. EUR-5848,PP.357-368; CONF-770597,PP.357-368 A V A I L A B I L I T Y - O F F I C E FOR OFFIC IAL PUBLICA-

TIONS OF T H E EUROPEAN COMMUNIT IES , BOITE POSTALE 1003 - L U X E M B O U R G ISBN 92-825-0256-2

C A N A D A

Radium


8389 Date 1978 112730 329000 522110 522210 870004 870006 853100



Pozdneev, D.B.; Savyuk, S.N.; Fadeev, M.A. KERNENERGIE, 21(5), 148-149 ( IN RUSSIAN) RUSSIA

8689 Date March 1979 112B00 512110 632110 820000 861000 870082 Gamma-Ray Dose Rate Conversion and Buildup Factors.

(Tech. Note) Shure, K. NUCL. SCI. ENG., 69(3), PP.432-436 BETTIS

8829 Date 1978 112B00 329000 522110 861000 870006 870013 870050


Monte-Car lo Method.

10073 Date July 1980 112760 424000 870092 870088 Estimates of Uranium Content and Radon Flux for Uranium

Mine Dumps Based on Borehole Radioactivity Logs. Riedel, D.W. NUREG/CR-1549 A V A I L A B I L I T Y - N T I S NUUS

Thorium




Shirley, G.W. GA-A14635 A V A I L A B I L I T Y - N T I S S6.00 ' GEAC

401-

6532 Date December 1977 122100 870090 u

Evaluation of the 232 -U Neutron Cross Sections for Inci-dent Neutron Energies up to 3 keV.

de Saussure, G.; Macklin, R.L. O R N L / T M - 6 1 6 1 A V A I L A B I L I T Y - N T I S $5.25 O A R N L

6657 Date November 1977 111110 521130 551110 329000 795203 870090 870092





AUSTRA

6659 Date February 1978 122100 870090 Evaluated Nuclear Data File of Th-232. Meadows, J.; Poenitz, W.; Smith, A.; Smith, D.; Whalen, J.;

Howerton, R. A N L / N D M - 3 5 A V A I L A B I L I T Y - N T I S A R G O N N

6700 Date May 1978 111500 122100 870090 Evaluation of 232-Th(n,n') , (n,2n), and (n,3n) Cross Sec-

tions. Fu, C.Y. O R N L / T M - 6 3 1 6 ; ENDF-267 , A V A I L A B I L I T Y - N T I S $4.50 V< O A R N L

6761 Dale May 1978 111110 122100 870090 Review and Combination of Experimental Results for Neu-

tron Emission per Fission of 232-Th. Gwin, R. O R N L / T M - 6 2 4 5 ; ENDF-262 A V A I L A B I L I T Y - N T I S $4.00 O A R N L


' 870092 The Quality of Fissile Fuel Bred in a Fusion Reactor Blan-

ket.

Leonard, B.R,Jr.; Jenquin, U.P. CONF-760935-P2, PP. 711 -722 A V A I L A B I L I T Y - N T I S B A N W

7061 Date January 1977 -122110 870090 870092 NuclearTheory Based Cross Sections of Th-232, Th-233

and U - 2 3 3 and Their Applications in Reactor Technol-ogy.

Garg, S.B.; Kumar, A. NBS SPEC. PUB. 461, PP. 70-73 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,

W A S H I N G T O N , D.C. 20402 I N D I A '

8191 Date 1978 010000 111110 122310 870090 870092 Evaluation of Fast Integral Data Related to 2 3 3 - U and

Thorium. Beck, C.L.; Lineberry, M.J.; Schacfer, R.W.; Carpenter,

S.G.; Wade, D.C. GONF-780401 - 1 4 A V A I L A B I L I T Y - D E P . , NT IS A R G O N N

8192 Date 1978 111110 122310 312000 521130 713000 870090 870092 Nuclear Data Sensitivity Coefficients for a

( 2 3 3 - U - - 2 3 2 - T h ) Fueled LMFBR. Turski, R.B.; McKnight, R.D, CONF-780401 -15 A V A I L A B I L I T Y - D E P . , NTIS A R G O N N


Fission-Product Aggregate Decay Data in the Calcula-tion of Decay- Energy Spectra.



8498 Date January 1979 122100 870090 870095 HEDL Evaluation of Thorium Cycle Cross Sections for

E N D F / B - V . Mann, F.M. H E D L - T M E - 7 8 - 1 0 0 >? A V A I L A B I L I T Y - N T I S

402-

HANFOR O A R N L



Hi l l , G.S. O R N L / O E P A - 7 A V A I L A B I L I T Y - N T I S O A R N L


Reactors ( A W B A Development Program). Hardy, J.,Jr.; Ullo, J.J.; Steen, N.M. W A P D - T M - 1 4 4 9 A V A I L A B I L I T Y - B E T T I S A T O M I C POWER LABO-

RATORY, WEST M IFFL IN , PA. BETTIS

8819 !: Date March 1979 111110 32AOOO 521130 793000 795254 870090 870092 Analysis of a Water Moderated Critical Assembly with

A N I S N - V I T A M I N C. Green, L. WFPS:TME-79-01S A V A I L A B I L I T Y - F U S I O N POWER SYSTEMS


WEE


Resonance Region. Keyworth, G.A.; Moore, M.S. CONF-780921, PP.241-267 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, FRANCE LOASL

8859 Date September 1978 122310 111210 329000 421130 421200 511120 512220


Fusion-Fission Hybrid Reactors. Hansen, L.F.; Wong, C.; Komoto, T.; Pohl, B.A. CONF-180921, PP.766-771 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,



Fuel Production: Evaluation of ORNL's Proposed TMF. -ENFP.

Burns, T.J.; Bartine, D.E.; Renier, J.P. O R N L / T M - 6 8 2 8 A V A I L A B I L I T Y - N T I S S4.50

Uranium



mal Operation of L iquid-Metal-Cooled Fast Breeder Reactors.

Erdman, C.A.; Kelly, J.L.; Kirbiyik, M.; Reynolds, A.B. EPA-520 /3 -75 -019 A V A I L A B I L I T Y - D E P T . OF NUCLEAR ENGINEER-


U - V A


cessing. Schultz, K.R.; Brogli, R.H.; Hopkins, G.R.; Jonzen, M.

Shirley, G.W. GA-A14635 A V A I L A B I L I T Y - N T I S $6.00 GEAC

6317 Date January 1978 I I I I 1 0 122100 870092 Evaluation of the 2 3 8 - U Neutron Cross Sections for Inci-

dent Neutron Energies Up to 4 kcV. de Saussure, G.; Olsen, D.K.; Perez, R.B.; Difilippo, F.C. O R N L / T M - 6 1 5 2 ; ENDF-257 A V A I L A B I L I T Y - N T I S $6.50 O A R N L

6498 Date 1976 111110 122100 870092 870094 Proceedings of the N E A N D C / N E A C R P Specialists Meet-

ing on Fast Neutron Fission Cross Sections of U -233 , U -235 , U -238 , and Pu-239, June 28-30, 1976, at Argonne National Laboratory.

403-

Poenitz, W.P.; Guenther, P.T. A N L - 76-90CSUPPL.); CONF-760647-SUPPL. A V A I L A B I L I T Y - N T I S $5.50 A R G O N N

6543 Date October 1977 111110 325000 511110 719A00 870092 Analysis of Homogeneous U233 and U235 Critical Assem-

blies with E N D F / B - I V Data (AWBA Development Program).

Ullo, J.J.; Hardy, J.,Jr. W A P D - T M - 1299 A V A I L A B I L I T Y - W E S T I N G H O U S E ELECTRIC

CORPORATION, BETTIS A T O M I C POWER DIVI-SION

BETTIS

6544 Date December 1977 111110 020000 329000 719A00 820000 870092 Monte Carlo Analyses to TRX Slightly Enriched-H /sub

2/ O Critical Experiments with E N D F / B - I V and Related Data Sets. ( A W B A Development Program).

Hardy, J,Jr. W A P D - T M - 1 3 0 7 A V A I L A B I L I T Y - W E S T I N G H O U S E ELECTRIC

CORPORATION, BETTIS ATOMIC POWER DIVI-S ION'

BETTIS

6570 : Date March 1978 122310 870092 An Evaluation of E N D F / B - I V and Hansen-Roach Ura-

nium-233 Cross Sections for Use in Criticality Calculations.

McNeany, S.R.; Jenkins, J.D. NUCL. SCI. ENG., 65(3), 441-453 O A R N L

658 3 Date 1976 010000 111110 121100 870092 870094 Theory of Nuclear Fission: A Review, Mosel, U. A N L - 7 6 - 9 0 , PP.3-30 A V A I L A B I L I T Y - N T I S G E R M A N

658 4 Date 1976 111110 122310 713000 870092 870094 The III. .Ttance of Fast Fission Cross Sections in Fast Reac-

tui,-. Bohn, L.M.: McKnight, R.D. A N L - 7 6 - 9 0 , PP.31-44 A V A I L A B I L I T Y - N T I S

A R G O N N


for U - 2 3 8 and Pu-239 to U -235 . Poenitz, W.P.; Guenther, P. A N L - 7 6 - 9 0 , PP.154-169 A V A I L A B I L I T Y - N T I S A R G O N N

6586 Date 1976 020000 122100 870092 The Status of U - 2 3 5 Fission as a Cross Section Standard. Carlson, C.W.; Czirr, J.B. A N L - 7 6 -90, PP.258-269 A V A I L A B I L I T Y - N T I S L A L L

6588 Date 1976 111110 122100 870092 Evaluation of the U - 2 3 5 Fission Cross Section from lOOeV

to 20 keV. Bhat, M.R. A N L - 7 6 - 9 0 , PP.307-332 v A V A I L A B I L I T Y - N T I S ^ BROOKI I ))


6611 ]|. . . Date February 1978 020000 111110 329000 551120 795209 795254 870092

870094 885000 ' o Analysis of Some Uranium Oxide and Mixed-Oxide Lat-

tice Measurements. „ Sher, R.; Fiarman, S. E P R I - N P - 6 9 1

6590 Date 1976 111110 121100 870092 870094 What Happens to the Fission Process Above the 2nd- and

3rd- Chance Fission Threshold? Stewart, L.; Howerton, R.J. A N L - 7 6 - 9 0 , PP.398-414 A V A l L A B I L I T Y - N T I S

, -LALL

404-

A V A I L A B I L I T Y - D E P A R T M E N T OF MECHANI -C A L ENGINEERING, STANFORD UNIVERSITY, STANFORD, CALIFORNIA 94305

EPRI

6627 Date March 1978 122310 312000 521130 719A00 870092 870013 870001

870008 810000 A Compendium of Energy-Dependent Sensitivity Profdes

for the T R X - 2 Thermal Lattice. Tomlinson, E.T.; Lucius, J.L.; Drischler, J.D. ORNL-5336; ENDF-253 A V A I L A B I L I T Y - N T I S S8.00 O A R N L

6638 Date 1977 112120 121100 870092 New Possibilities of Calculating Independent Fission Prod-

uct Yields. Valenta, V. ZJE-207 A V A I L A B I L I T Y - S K O D A WORKS, NUCLEAR

POWER CONSTRUCTION DIVISION, INFOR-M A T I O N CENTRE, PLZEN, CZECHOSLOVAKIA

CZECHO

6657 Date November 1977 111110 521130 551110 329000 795203 870090 870092



McGregor, B.J. AAEC/E -432 A V A I L A B I L I T Y - A U S T R A L I A N ATOMIC ENERGY


AUSTRA


240-Pu and 241 -Pu Adopted in J E N D L - 1. Prelimi-nary Results.

Kikuchi, Y.; Nakagawa, T.; Matsunobu, H.; Kanda, Y.; Kawai, M.

J A E R I - M - 6 9 9 6 A V A I L A B I L I T Y - D E P . , NTIS (U.S. SALES ONLY) JAPAN

6695 Date Apri l 1978 111110 122310 311000 312000 719A00 795217 870092

870094

Sensitivity and Uncertainty Analysis for Functionals of Time-Dependent Nuclide Density Field.

Williams, M.L.; Weisbin, C.R. ORNL-5393; ENDF-263 A V A I L A B I L I T Y - N T I S S6.00 O A R N L ' /

6734 Date May 1978 111210 122310 312000 521130 795204 717000 870006

870092 861000 0

Cross-Section Sensitivity Analysis of 235 -U and 238-U Fission Rates Measured in a Graphite-Reflected Lith-ium Assembly. (Tech. Note)


6747 Date February 1978 112120 532000 870092 A Calorimetric Measurement of Decay Heat from 235-U

Fission Products from 10 to 10**5 Seconds. Schrock, V.E.; Grossman, L.M.; Prussin, S.G.; Sockalingam,

K.C.; Nuh, F.; Fan, C - K . ; Cho, N.Z.; Oh, S.J. EPRI -NP-616, VOL. l A V A I L A B I L I T Y - U N I V E R S I T Y OF CALIFORNIA,

BERKELEY, CALIF. 94720 EPRI

6750 Date March 1978 112120 870092 Nuclear Physics Constants of Gamma - Emitting Isotopes in

the Technological Environment of Reactors. Nesterov, B.V. ,, INDC(CCP)- 1 i o / L N P

O A V A I L A B I L I T Y - I A E A IAEA

6803 Date 1975 111110 324000 32A000 511110 861000 870092 Multigroup Formalism for Evaluation of Continuous Slow-

ing Down Theory Parameters. Parvcz, A.; Becker, M. COO-2458- 18 A V A I L A B I L I T Y - D E P . , NTIS U - N Y

6813 Date 1978 010000 111110 870092 870098 A Review on Standard Fission Neutron Spectra of 235-U

and 252-Cf. Knitter, H.H. IAEA-208, VOL.1, PP.183-195 A V A I L A B I L I T Y - I N I S , MICROFICHE CLEARING-

HOUSE • O

405-

0 BELGIU

6814 Date 1978 010000 l i t 110 421110 421120 421130 870092 In -P i le Neutron Spectrometry: Status. De Leeuw-Gierts, G.; De Leeuw, S. I A E A - 2 0 8 , VOL.I , PP.197-230 A V A I L A B I L I T Y - I N I S M I C R O F I C H E CLEARING-

HOUSE BEL'GIU




I A E A - 2 0 8 , VOL.I , PP.233-263 A V A I L A B I L I T Y - I N I S M I C R O F I C H E CLEARING-

HOUSE H A N F O R


Some Known Spectra. Zi jp, W.L.; Nolthenius, H.J.; Baard, J.H. I A E A - 2 0 8 , VOL.I, PP.265-300 A V A I L A B I L I T Y - I N I S M I C R O F I C H E CLEARING-

HOUSE N E T H E R


Thermal and Californium-252 Neutrons. Debertin, K. IAEA-208 , VOL.11, PP.261-263 A V A I L A B I L I T Y - I N I S M I C R O F I C H E CLEARING-

HOUSE G E R M A N

f 6848 Date 1978 ~

111110 210000 511120 861000 870092 One Material Experiments in the Frame of Power Reactor

Pressure Vessel Benchmarks. De Leeuw-Gierts, G.; De Leeuw, S. I A E A - 2 0 8 , VOL.11, PP.375-383 A V A I L A B I L I T Y - I N I S M I C R O F I C H E CLEARING-

HOUSE BELGIU

6858 Date June 1978 112120 112730 532000 719A00 870092 Fission Product Source Terms for the L W R

Loss-of-Coolant Accident: Summary Report. Lorenz, R.A.; Collins, J.L.; Malinauskas, A.P. NUREG/CR-0091 ; O R N L / N U R E G / T M - 206 A V A I L A B I L I T Y - N T I S O A R N L

6951 Date March 23, 1978 < »• 112200 810000 870092 Beta-Induced External Bremsstrahlung from Spent-Fuel

Fission Products. Stamatelatos, M.G. S A I - 7 8 - 6 0 0 - L J A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, P.O.

BOX 2351, 1200 PROSPECT STREET, LA JOLLA , C A L I F O R N I A 92037

SCA


Elements, Scgev, M. NUCL. SCI. ENG., 67(2), 221 -234 A R G O N N

7022 Date September 1976 I I I 110 111210 32A000 521130 717000 810000 870090


ket. Leonard, B.R.,Jr.; Jenquin, U.P. CONF-760935-P2, PP. 711 -722 A V A I L A B I L I T Y - N T I S BANW

7033. Date September 1976 111210 32A000 521230 422130 717000 717100 870003


Blanket Assemblies, 'vlaekawa, H.; Seki, Y. i O N F - 7 6 0 9 3 5 - P 3 , PP. 883-894 A V A I L A B I L I T Y - N T I S JAPAN

7046 Date October 1977 112120 421200 430000 870092 Fission-Product Energy Release for Times Following Ther-

mal-Neutron Fission of 235-U Between 2 and 14000 Seconds.

406-

Dickens, J.K.; Emery, J.F.; Love, T.A.; McConnell, J.W. Norlhcutt, K.J.; Peelle, R.W.; Weaver, H.

O R N L / N U R E G - 1 4 A V A I L A B I L I T Y - N T I S S8.00 -O A R N L

7061 Date January 1977 122110 870090 870092 IjJuclear Theory Based Cross Sections of Th-232, Th-23-3^. '-'•-"and U - 2 3 3 and Their Applications in Reactor Technol- ^

ogy-Garg, S.B.; Kumar, A. NBS SPEC. PUB. 461, PP. 70-73 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,



Technique for Cylindrical Systems.'! Sundaram, V.K.; Gopinath, D.V. ' NBS SPEC. PUB. 461, PP. 94-96 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,




A V A I L A B I L I T Y - L O S ALAMOS SCIENTIFIC LAB., P.O. BOX 1663, LOS ALAMOS, NEW MEXICO 87545

LOASL

8191 Date 1978 010000 111110 122310 870090 870092 Evaluation of Fast Integral Data Related to 233 -U and 1

Thorium. Beck, C.L.; Lineberry, M.J.; Schaefer, R.W.; Carpenter,

S.G.; Wade, D.C. CONF-780401 - 1 4 A V A I L A B I L I T Y - D E P . , NTIS ARGONN

8192 Date 1978 111110 122310 312000 521130 713000 870090 870092 Nuclear Data Sensitivity Coefficients for

( 2 3 3 - U - - 2 3 2 - T h ) Fueled LMFBR. Turski, R.B.; McKnight, R.D. CONF-780401 -15 A V A I L A B I L I T Y - D E P . , NTIS ARGONN

8198.' Date September 1978 020000 422110 719AOO 870092 870094 Clean Critical Experiment Benchmarks for Plutonium Recy-

cle in LWRs. Smith, R.I.; Konzek, G.J. EPRI -NP-196, VOL.2 A V A I L A B I L I T Y - B A T T E L L E PACIFIC NORTH-

WEST • LABORATORIES, R ICHLAND, WASHINGTON 99352

BANW "

7092 Date January 1975 112930 220000 222000 795185 795304 870092 870094 A Comparison of the Potential Radiological Impact of Recy-


Til l, J.E. O R N L - T M - 4 7 6 8 A V A I L A B I L I T Y - O A K RIDGE N A T I O N A L LABO-

RATORY O A R N L

8206 Date September 1978 112120 532000 795309 870090'870092 870094 The Application of a Library of Processed E N D F / B - I V




8118 . . % ,o._. Date August 1978 112120 532000 870092'870094" Integral Decay-Heat Measurements and Comparisons to

E N D F / B - I V and V. England, T.R>; Schenter, R.E.; Schmittroth, F. NUREG/CR-0305; L A - 7 4 2 2 - M S

8235 Date April 1975 111110 329000 719A00 870092 Monte Carlo Analysis of Direct Measurements of the Ther-

mal Eta(0.025 eV) for 233-U and 235-U (LWBR Development Program).

Ullo, J.J.; Goldsmith, M. W A P D - T M - 1217

407-h

A V A I L A B I L I T Y - D E P . , NTIS BETTIS

8236 Date Apri l 1975 111110 329000 719A00 870092 " Monte Carlo Analysis of Thermal Spectrum Averaged Mea-

surements of, Eta of 233 -U and 235 -U (LWBR Development Program).

Goldsmith, M.; Ullo, J.J. W A P D - T M - 1 2 1 8 A V A I L A B I L I T Y - D E P . , NTIS BETTIS

8268 Date August 1978 010000 112120 870092 870094 Review of Existing Compilations and Evaluations of FPND. Lammer, G. 1AEA-213, PP.5-32 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F ONLY) IAEA


ment of Environmental Aspects. Lindberg, L.

,.IAEA-213, PP.33-39 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F ONLY) SWEDEN

827 0 Date August 1978 010000 112120 713000 719A00 870092 870094 Needs and Accuracy Requirements for FPND in the Physics

Design of Power Reactor Cores. Rowlands, J.L. IAEA 213, PP.41-60 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F ONLY) E N G L A N

<• >>

827 1 Date August 1978 010000 112120 532000 870092 870094 The Importance of Fission Product Nuclear Data in Reactor

Design and Operation. Devillers, C. IAEA-213, PP.61-89 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) FRANCE

8272 Date August 1978 010000 112120 230000 870092 870094 Needs and Accuracy Requirements for FPND in :'the

Out -o f -P i le Fuel Cycle.

McKay, H.A.C. IAEA-213, PP.91-104 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) E N G L A N

8273 Date August 1978 010000 112120 230000 870092 870094 A Review of FPND Requirements for Investigation of I r ra- "

dialed Nuclear Fuel: Burnup Measurements, Neutron Dosimetry, Nuclear Safeguards.

Maeck, W.J. IAEA-213 , PP.105-108 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) ALCC

8277. Date August 1978 010000 112120 870092 870094 Status of Fission Product Yield Data. Cuninghame, J.G. IAEA-213, PP.351 -419 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) E N G L A N


or System atics. Denschlag, J.O. IAEA-213, VOL.11, PP.421-485 A V A I L A B I L I T Y - I A E A ( M F O N L Y ) GERMAN

8419 Date August 1978 010000 112120 870092 870094 Status of Decay Data of Fission Products. Blachot, J. 0

IAEA-213, VOL.11, PP.487-565 A V A I L A B I L I T Y - I A E A (MF O N L Y ) FRANCE

8420 <f.- Dale August 1978 010000 111120 870092 Status or Delayed Neutron Data. Rudstam, G. IAEA-213, VOL.11, PP.567-626 A V A I L A B I L I T Y - I A E A ( M F O N L Y ) SWEDEN


Decay Power.

408-

Schenter, R.E.; England, T.R. I A E A - 2 I 3 , VOL.11, PP.677-741 A V A I L A B I L I T Y - I A E A ( M F O N L Y ) H A N F O R

8436. . . ^ ' Date January 1979 112930 ££2000 870092 Potential Radiological Impacts of Recovery of Uranium

from Wet-Process Phosphoric Acid. Davis, W., Jr.fHaywood, F.F.; Danek, J.L.; Moore, R.E.;

Wagner, E.B.; Rupp, E.M:» O R N L / E P A - 2 A V A I L A B I L I T Y - N T I S $8.00 O A R N L

c

8500 Date June 1977 111110 122110 324000 326000 327000 820000 861000


Oing-Down Kernel: The Computer Code "MAGGIE" . Gado, J.; Keresziuri, A. KFK1-1977-44 A V A I L A B I L I T Y - K O Z P O N T I F I Z I K A I KUTATO


H U N G A R

8502 Date January 1979 112120 510000 512220 870092 870094 " Fission Product Gamma Spectra. Jurney, E.T.; Bendt, P.J.; England, T.R. L A - 7 6 2 0 - M S A V A I L A B I L I T Y - N T I S LOASL


Nuclear Data. • t-Kotov, V.V.; Maynard, Ch.W.; Markovskii, D.V.; Shatalov,

G.E. L A - T R - 7 8 - 6 5 ; IAE-2817 ( I N RUSSIAN) A V A I L A B I L I T Y - L O S A L A M O S SCIENTIFIC LAB. RUSSIA

8510 Date September 1978 112120 423240 532000 870092 870094 Calometric Fission Product Decay Heat Measurements for

239-Pu, 233-U, and 235-U. Yarnell, J.L.; Bendt, P.J. , NUREG/CR-0349; LA-7452 j A V A I L A B I L I T Y - N T I S LOASL l t

it •i"//'

8511 Date J u l y ^ S 111110 112120 122310 532000 870092 887000,. The Effects of the Depletion and Buildup of Fissile Nuclides

and of 238 -U Fast Fissions on Fission Product Decay Power. '

Trapp, T.J.,Jr. NUREG/CR-0404 ; OSU-NE-7806 ; THESfS A V A I L A B I L I T Y - N T I S U - O R

860 4 Date 1977 111110 210000 421140 422130 430000 870092 870094 Fission Rate Measurements for Materials Neutron Dosime-

try in Reactor Environments. Grundl, J.; Eisenhauer, C. EUR-5667E/F,PT.I , PP.425-454;

CONF-7509;35,PT.I, PP.425-454 AVAILABILS / * ' -OFF ICE FOR OFFICIAL PUBLICA-

TIONS O F " T H E EUROPEAN COMMUNIT IES , BOITE POSTAL 1003 - LUXEMBOURG

NABS

860 5 Date 1977 111110 421140 422130 430000 870092 870094 Techniques de Fission. Bouchard, J.; Menessier, P. EUR-5667E/F,PT.I , PP.476-497(IN FRENCH);



FRANCE

860 6 Date 1977 111110 210000 421140 422130 870092 870094 Specimen Fission Rate Estimation in the JMTR. Mizuho, M.; Oyamada, R.; Sezaki, K. EUR-5667E/F,PT.I , PP.498-523;


TIONS OF THE EUROPEAN COMMUNIT IES, BOITE POSTAL 1003 - LUXEMBOURG 'J

JAPAN

8632 Date 1977 111110 421140 713000 719A00 870092 In'ercomparison of Reactor Dosimetry Cross Sections^Iea-

sured in a Thermal Reactor, in a Fast Reactor and with ff an Enriched Uranium Fission Plate.

Kimura, I.; Kobayashi, K. EUR-5667E/F,PT.I I , PP.142-151;


TIONS OF THE EUROPEAN COMMUNIT IES , BOITE POSTAL 1003 - LUXEMBOURG

o S. 409-

JAPAN

8645 Date December 1978 112120 713000 719A00 795309 870092 870094 Radiation Source Terms in LWR and LMFBR Spent Fuel

Final Report. Tech. Services Agreement 78-156. Stamatelatos, M.G. EPRI -NP-948 A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, INC.,

LA JOLLA, C A L I F O R N I A SCA

8657 Date February 1979 111110 112120 122310 532000 7i9AOO 8700' ,: 870094 Fission Product Decay Power and Uncertainty After Real-

istic Reactor Operating Histories. Trapp, T.J.; Spinrad, B.I. O R N L / R S I C - 4 2 , PP.105-118 A V A I L A B I L I T Y - N T I S P A N L


111110 870092 870094 870096 Summary of Fission Spectrum Workshop. Held at the


Stewart, L. (Ch.) L A - 7 7 3 9 - C ; ENDF-278 ' A V A I L A B I L I T Y - U N I V E R S I T Y O F C A L I F O R N I A ,

LOS A L A M O S J S C I E N T I F I C LABORATORY, P.O. BOX 1663, LOS ALAMOS, N.M. 87545

LOASL

8819 Date March 1979 111110 32A000 521130 793000 795254 870090 870092 Analysis of a Water Moderated Critical Assembly with

A N I S N - V I T A M I N C. Green, L, WFPS:TME-79-015 A V A I L A B I L I T Y - F U S I O N POWER SYSTEMS


WEE

8840 Date September 1978 010000 122100 122310 870006 870092 Covariance Matrices of Experimental Data. Perey, F.G. CONF-780921, PP.104-115 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,


8846 Date September 1978 "OIOOOO 122100 870090 870092^870094 Cross-Sections of the Major Transactinium Isotopes in the

Resonance Region. Keyworth, G.A.; Moore, M.S. CONF-780921, PP.241-267 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, FRANCE ,, LOASL

8859 Date September 1978 '.iw 122310 111210 329000 421130 421200 511120 512220 h'

717000 717000 870090 870092 870029 870041 }'£<, Neutron Spe'ctra from Materials Used in Fusion '-and

Fusion-Fission Hybrid Reactors. Hansen, L.F.; Wong, C.; Komoto, T.; Pohl, B.A. „ CONF-780921, PP.766-771 A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,

75775 PARIS CEDEX 16, FRANCE li, ... L A L L

" o

8867 Date September 1978 111210 122310 32AOOO 521130.795254 717100 810000

870092 - Reproduction of the Weale Experiment Results with Modi-

fied E N D F / B - I V U - 2 3 8 Data. Segev, M.; Krumbein, A. CONF-780921, PP. 1028 — 1032 e> A V A I L A B I L I T Y - O E C D , 2, RUE A N D R E - P A S C A L ,


89,01 Date May 1979 111220 717500 870090 870092 870094 Concept Evaluation of a Nuclear Design for Electronuclear

Fuel Production: Evaluation of ORNL's Proposed T M F - E N F P .

Burns, T.J.; Bartine, D.E.; Renier, J.P. O R N L / T M - 6 8 2 8 0

A V A I L A B I L I T Y - N T I S S4.50 O A R N L .

8860 ! . . . . Date September 1978 111210 551110 717100 870092 810000 Neutronic Studies of a 2 3 3 - U Fusion Breeder. , n Hansen, L.F.; Maniscalco, J.A. . A

CONF-78Q921, PP.772-777 ' ^ A V A I L X B I L I T Y - O E C D , 2,{RUE A N D R E - P A S I A L ,

75775 PARIS CEDEX I f t / f R A N C E L A L L

o 410

8918 Date May 1979 111120 870092 Calculated Time-Dependent Delayed Neutron Group

Yields for Thermal - Neutron Fission of Uranium-235. Alexander, D.R.; Peng, Y.K. NUCL. SCL ENG., 70(2), 184-191 U - N B

Fission-Product Energy Release for Times Following Ther-mal-Neutron Fission of 2 3 5 - U Between 2 and 14 000 s.

Dickens, J.K.; Love, T.A.; McConnell, J.W.; Peelle, R.W. NUCL. SCL ENG., 74(2), 106-129 O A R N L

8968 Date Apri l 1979 122100 870092 Determination of the Errors in Evaluated Data with Allow-

ance for Correlations. Evaluation of U - 2 3 5 Fission Cross-Scctions, alpha (235-U) , alpha(239-Pu) and 239-Pu Fission Cross-Sections for the Evaluated Nuclear Data Library BOYaD-3.

Kon'shin, V.A.; Sukhovitskij, E.Sh.; Zharkov, V.F. INDC(CCP) - 132/LV A V A I L A B I L I T Y - I A E A NUCLEAR DATA SECTION,

K A R N T N E R R I N G 11, A-1010 V I E N N A RUSSIA i

9024 , Dale-May 1979 112120 532000 870092 ^ Nuclear Data Library of Fission Products for Decay Power

Calculation. Tasaka, K. , ~ > NUREG/CR-0705; TREE-1?25 ' V ' ' ' A V A I L A B I L I T Y - E G A N D G IDAHO, INC., IDAHO EDGERT

9129 Date June 1979 010000 020000 122310 329000,7,19A00 870090 870092 Integral Testing of Thorium and U233 Data for Thermal

Reactors (AWBA Development Program). Hardy, J.,Jr.; Ullo, J.J.; Steen, N.M. W A P D - T M - 1449 A V A I L A B I L I T Y - B E T T I S ATOMIC POWER LABO-

RATORY. WEST M IFFL IN , PA. BETTIS

(t O 9503 Date September 1979

112120 870092 870094 Measurements of 239-Pu and 235 -U Fission Produc!

Decay Power from 1 to 10**5 Seconds. Friesenhahn, S.J.; Lurie, N.A. EPRI -NP-998 A V A I L A B I L I T Y - I R T CORPORATION, 7650 CON-

VOY COURT, SAN DIEGO, CA 92111 IRT

9819 Date May 1980 112120 870092

10073 Date July 1980 112760 424000 870092 870088 Estimates of Uranium Content and Radon Flux for Uranium

Mine Dumps Based on Borehole Radioactivity Logs. Riedel, D.W. NUREG/CR-1549 A V A I L A B I L I T Y - N T I S NUUS

Neptunium



Meteer, J.W. 1CP-1050-3 A V A I L A B I L I T Y - D E P . , NTIS ALCC

6657 Date November 1977 111110 521130 551110 329000 795203 870090 870092





.'VUSTRA

8478 Date January 1979 422130 870093 The Importance of Subthreshold Fission Phenomena in Cer-

tain Applications of Fission Threshold Detectors: An Example of Neptunium-237 for Nondestructive Assay. (Tech. Note)

Difilippo, F.C.; Ragan, G.L. NUCL. SCL ENG., 69(1), 104-107 O A R N L

411-

Plutonium


6213 . Date November 1975 010000 112710 112760 112930 713000 870092 870094 Radionuclide Production, Transport, and Release from Nor-

mal Operation of L iquid-Metal -Cooled Fast Breeder Reactors.

Erdman, C.A.; Kelly, J.L.; Kirbiyik, M.; Reynolds, A.B. E P A - 5 2 0 / 3 - 7 5 - 0 1 9 A V A l LABI L ITY - D EPT. OF NUCLEAR ENGINEER-


U - V A

6498 Date 1976 111110 122100 870092 870094 Proceedings of the N E A N D C / N E A C R P Specialists Meet-

ing on Fast Neutron Fission Cross Sections of U-233 , U - 2 3 5 , U -238 , and Pu-239, June 28-30, 1976, at Argonne National Laboratory.

Poenitz, W.P.; Guenther, P.T. ANL-76 -90 (SUPPL . ) ; CONF-760647-SUPPL. A V A I L A B I L I T Y - N T I S S5.50 A R G O N N

6583 Date 1976 010000 111110 121100 870092 870094 Theory of Nuclear Fission: A Review. Mosel, U. A N L - 7 6 - 9 0 , PP.3-30 A V A I L A B I L I T Y - N T I S G E R M A N

6584 Date 1976 111110 122310 713000 870092 870094 The Importance of Fast Fission Cross Sections in Fast Reac-

tors. Bohn, E.M.; McKnight, R.D. A N L - 7 6 - 9 0 , PP.31-44 A V A I L A B I L I T Y - N T I S A R G O N N


for U - 2 3 8 and Pu-239 to U -235 . Poenitz, W.P.; Guenther, P. r

A N L - 7 6 - 9 0 , PP. 154-169 A V A I L A B I L I T Y - N T I S A R G O N N

6590 Date 111110 121100 870092 870094 V What Happens to the Fission Process Above the 2nd-

3rd- Chance Fission Threshold? Stewart, L ; Howerton, R.J. A N L - 7 6 - 9 0 , PP.398-414 A V A I L A B I L I T Y - N T I S , < i L A L L

6611 Date February 1978 020000 111110 329000 551120 795209 795254 870092

870094 885000 ,J

Analysis of Some Uranium Oxide and Mixed-Oxide Lat-tice Measurements.

Sher, R.; Fiarman, S. E P R I - N P - 6 9 1 A V A I L A B I L I T Y - D E P A R T M E N T OF M E C H A N I -

C A L ENGINEERING, STANFORD UNIVERSITY, STANFORD, C A L I F O R N I A 94305

EPRI


240-Pu and 241 -Pu Adopted in J E N D L - 1 . Prelimi-nary Results.

Kikuchi, Y.; Nakagawa, ,T.; Matsunobu, H.; Kanda, Y.; Kawai, M.

J A E R I - M - 6 9 9 6 A V A I L A B I L I T Y - D E P . , NTIS (U.S. SALES O N L Y ) JAPAN

6695 Date Apri l 1978 111110 122310 311000 312000 719A00 795217 870092

870094 Sensitivity and Uncertainty Analysis for Functionals of

Time-Dependent Nuclide Density Field. Williams, M.L.; Weisbin, C.R. ORNL-5393; ENDF-263 A V A I L A B I L I T Y - N T I S $6.00 O A R N L

6696 Date Apri l 1978 111110 112120 221000 532000 422200 430000 794000




O R N L / N U R E G - 3 4 A V A I L A B I L I T Y - N T I S $6.00 ••< O A R N L

412-

6742 Date June 1977 112760 421200 424000 870094 Determination of the Isotopic Composition of Plutonium by a Gamma-Ray Spectrometry.

Banham, M.F. A E R E - R - 8 7 3 7 A V A I L A B I L I T Y - D E P , NTIS (U.S. SALES O N L Y ) E N G L A N


Elements. Segev, M. NUCL . SCI. E N G , 67(2), 221-234 A R G O N N

7049 Date August 1977 111110 112120 713000 870094 Fast Reactor Fission Yields for 239-Pu and 241 -Pu. Maeck, W.J. ICP-1050-11 A V A I L A B I L I T Y - A L L I E D C H E M I C A L CORPORA-

T ION, I D A H O C H E M I C A L PROGRAMS ALCC


Technique for Cylindrical Systems. Sundaram, V.K.; Gopinath, D.V. NBS SPEC. PUB. 461, PP. 94-96 A V A I L A B I L I T Y - S U P T . OF DOCUMENTS, GPO,


7066 V*'. Date January L977 111110 310000 511110 713000 870092 870094 Stochastic Method of Calculations for Fast Systems. Godwal, B.K.; Navalkar, M.P. / - - z ^ . NBS SPEC. PUB. 461, PP. 97-99/ " ^ A V A I L A B I L I T Y - S U P T . OF ^DOCUMENTS, GPO,

W A S H I N G T O N , D.C. 20402" I N D I A

7092 Date January 1975 112930 220000 222000 795185 795304 870092 870094 A Comparison of the Potential Radiological Impact of Recy-


Ti l l , J.E. O R N L - T M -4768 A V A I L A B I L I T Y - O A K RIDGE N A T I O N A L LABO-

' R A T O R Y

O A R N L

8031 Date August 1978 112120 610000 870094 Fission - Product Energy Release for Times Following Ther-

mal-Neutron Fission of 241 - P u Between 2 and 14000 Seconds.


NUREG/CR-0171 ; O R N L / N U R E G - 4 7 A V A I L A B I L I T Y - N T I S O A R N L


E N D F / B - I V and V. England, T.R.; Schenter, R.E.; Schmittroth, F. NUREG/CR-0305 ; L A - 7 4 2 2 - M S A V A I L A B I L I T Y - L O S A L A M O S SCIENTIFIC L A B ,

P.O. BOX 1663, LOS ALAMOS, N E W MEXICO 87545

LOASL

8147 Date October 1978 122100 870094 Multilevel Resonance Parameters of Plutonium-241.

(Tech. Note) Weston, L.W.; Todd, J.H. NUCL. SCI. E N G , 68(1), 125-128 O A R N L

8198 Date September 1978 020000 422110 719A00 870092 870094 Clean Critical Experiment Benchmarks for Plutonium Recy-

cle in LWRs. Smith, R.I.; Konzek, G.J. EPRI -NP-196 , VOL.2 A V A I L A B I L I T Y - B A T T E L L E PACIFIC NORTH-

WEST LABORATORIES, R I C H L A N D , W A S H I N G T O N 99352

BANW





413-

8268 Date August 1978 010000 112120 870092 870094 Review of Existing Compilations and Evaluations of FPND. Lammer, G.

, IAEA-213, PP.5-32 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) IAEA

8277 ' Date August 1978 010000 112120 870092 870094 Status of Fission Product Yield Data. Cuninghame, J.G. IAEA-213 , PP.351-419 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) E N G L A N


ment of Environmental Aspects. Lindberg, L. IAEA-213 , PP.33-39 A V A I L A B I L I T Y - I A E A , V I E N N A (MF O N L Y ) SWEDEN

8270 Date August 1978 010000 U2120 713000 719A00 870092 870094 Needs and Accuracy Requirements for FPND in the Physics

Design of Power Reactor Cores. Rowlands, J.L. IAEA 213, PP.41-60 A V A I L A B I L I T Y - I A E A , V IENNA (MF O N L Y ) E N G L A N


Design and Operation. Devillers, C. IAEA-213, PP.61 -89 A V A I L A B I L I T Y - I A E A , V I E N N A ( M F O N L Y ) FRANCE

827 2 Date August 1978 010000 112120 230000 870092 870094 Needs and Accuracy Requirements Tor FPND in the

Ou t -o f -P i l e Fuel Cycle. McKay, H.A.C. IAEA-213, PP.91 -104 A V A I L A B I L I T Y - I A E A , V IENNA (MF O N L Y ) ENGLAN

827 3 Date August 1978 010000 112120 230000 870092 870094 A Review of FPND Requirements for Investigation of Irra-


Maeck, W.J. IAEA-213, PP.105-108 A V A I L A B I L I T Y - I A E A , V I E N N A (MF O N L Y ) ALCC

%


or Systematics. Denschlag, J.O. IAEA-213, VOL.11, PP.421 -485 A V A I L A B I L I T Y - I A E A ( M F O N L Y ) G E R M A N

8419 1 Date August 1978 010000 112120 870092 870094 Status of Decay Data of Fission Products. Blachot, J. IAEA-213, VOL.11, PP.487-565 A V A I L A B I L I T Y - I A E A ( M F O N L Y ) FRANCE

8502: . Date January 1979 112120 510000 512220 870092 870094 Fission Product Gamma Spectra. Jurney, E.T.; Bendt, P.J.; England, T.R. L A - 7 6 2 0 - M S A V A I L A B I L I T Y - N T I S LOASL

8510 Date September 1978 fJ 112120 423240 532000 870092 870094 Calometric Fission Product Decay Heat Measurements for

239-Pu, 233-U, and 235-U. Yarnell, J.L.; Bendt, P.J. NUREG/CR-0349; LA-7452 A V A I L A B I L I T Y - N T I S LOASL

8604 Date 1977 111110 210000 421140 422130 430000 870092 870094 Fission Rate Measurements for Materials Neutron Dosime-

try in Reactor Environments. Grundl, J.; Eisenhauer, C. EUR-5667E/F.PT.I, PP.425-454;



NABS

414

8605 Date 1977 111110 421140 422130 430000 870092 870094 Techniques de Fission. Bouchard, J.; Menessier, P. EUR-5667E/F,PT.I, PP.'476-497(IN FRENCH);



FRANCE

8606 Date 1977 K 111110 210000 421140 422130 870092 870094 Specimen Fission Rate Estimation in the JMTR. Mizuho, M.; Oyamada, R.; Sezaki, K. EUR-5667E/F,PT.I, PP.498-523;



JAPAN

8645 Date December 1978 112120 713000 7I9AOO 795309 870092 870094 Radiation Source Terms in LWR and LMFBR Spent Fuel

Final Report. Tech. Services Agreement 78-156. Stamatclatos, M.G. EPRI -NP-948 A V A I L A B I L I T Y - S C I E N C E APPLICATIONS, I N C ,

LA JOLLA, CAL IFORNIA SCA

8657 Date February 1979 111110 112120 122310 532000 719A00 870092 870094 Fission Product Decay Power and Uncertainties After Real-'

istic Reactor Operating Histories. Trapp, T.J.; Spinrad, B.I. ORNL/RSIC-42 , PP.105- 118 A V A I L A B I L I T Y - N T I S PANL

8724 Date February 1979 112120 870094 Fast Reactor Fission Yields 240-Pu and 242-Pu. Maeck, W.J.; Eggleston, R.L.; Erickson, A.L.; Tromp, R.L. ICP- 1050-IV A V A I L A B I L I T Y - N T I S $5.25 1DNEL

8730 Date March 1979 111110 870092 870094 870096 Summary of Fission Spectrum Workshop. Held at the


Stewart, L. (Ch.) L A - 7 7 3 9 - C ; ENDF-278 \\ A V A I L A B I L I T Y - U N I V E R S I T Y OF CALIFORNIA,

LOS ALAMOS SCIENTIFIC LABORATORY, P.O. BOX 1663, LOS ALAMOS, N.M. 87545

LOASL



Hil l , G.S. O R N L / O E P A - 7 1 ' A V A I L A B I L I T Y - N T I S O A R N L


Resonance Region. Keyworlh, G.A.; Moore, M.S. CONF-780921, PP.241-267 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL ,

75775 PARIS CEDEX 16, FRANCE LOASL

8874 Date 1978 122100 870094 Review of Microscopic Neutron Cross Section Data for the

Higher Plutonium Isotopes in the Resonance Region. Weston, L.W. CONF-781174-4 A V A I L A B I L I T Y - D E P . , NTIS O A R N L


Fuel Production: Evaluation of ORNL's Proposed T M F - E N F P . u '

Burns, T.J.; Bartine, D.E.; Renier, J.P. O R N L / T M - 6 8 2 8 A V A I L A B I L I T Y - N T I S $4.50 O A R N L

8917 Date May 1979 112120 870094 y'\ Fission Yields for Thermal-Neutron Fission of Plutoni- 5

um-241. Dickens, J.K. NUCL. SCL ENG., 70(2), 177-183 O A R N L

415-

9260 ; Date July 1979 112760 421200 424000 711100 870094 870095 A Nondestructive Assay System for Use in Decommission-

ing a Plutonium-Handling Facility. Roche, C.T.; Vronich, J.J.; Bellinger, F.O.; Perry, R.B. A N L - 7 9 - 6 0 A V A I L A B I L I T Y - A R G O N N E N A T I O N A L LABORA-

TORY, ILL. ARGONN

9265 Date May 1979 122100 122310 870094 242-Pu: Preliminary Evaluation with Consideration of

240-Pu and Some Sensitivity Results. Jary, J.; Lagrange, Ch.; Philis, C. B N L - 50991,PP.83 - 131; C O N F - 781174,PP.83 -131 A V A I L A B I L I T Y - N T I S FRANCE

9266 Date May 1979 122100 870094 Evaluation of High Plutonium Isotopes for the German

Nuclear Data File Kedak. Goel, B. BNL-50991,PP. 165-176; CONF-781174,PP.165-176 A V A I L A B I L I T Y - N T I S G E R M A N

9267 Date May 1979 122100 870094 Evaluation of n plus 242-Pu Reactions from 10 keV to 20

MeV. Madland, D.G.; Young, P.G. BNL-50991,PP.189-230; CONF-781174,PP.189-230 A V A I L A B I L I T Y - N T I S LOASL

9270 Date May 1979 122310 870094 870095 Reactor Application of Actinide Cross Section Data. Beaman, S.L.; Cowan, C.L.-BNL-50991,PP.287-295; CONF-781174,PP.287-295 A V A I L A B I L I T Y - N T I S GEE

9271 Date May 1979 424000 870094 Nuclear Data for Nuclear Material Safeguards. Lemlcy, J.R. B N L - 50991,PP.297 - 303; C O N F - 781174,PP.297 - 303 A V A I L A B I L I T Y - N T I S BROOKH

9273 Date May 1979 020000 870094 Integral Experiments Performed at CEA to Improve the Pu

Higher Isotope Nuclear Data; "PLUTO Programme". Chaudat, J.P.; Hammer, Ph.; Martin-Deidier, L. BNL-50991,PP.349-365; CONF-781174,PP.349-365 A V A I L A B I L I T Y - N T I S FRANCE

9448 , Date August 1979 111110 122310 32AOOO 521130 793000 794000 719A00



Jenquin, U.P.; Thompson, J.K.; Trapp, T.J.; Kottwitz, D.A. NUREG/CR-0965; PNL-3071 AVAILABIL ITY-DEP. , NTIS, PC A 0 5 / M F A01 PANL

9268 Date May 1979 122100 870094 ' 242-Pu Evaluation in the Resolved Resonance Region. Menapace, E.; Motta, M.; Ventura, A. BNL-50991,PP.251 -274; CONF-781174,PP.251 -274 A V A I L A B I L I T Y - N T I S I T A L Y

9269 Date May 1979 122100 870094 870095 HEDL Evaluation of High Plutonium and Americium Cross

Sections for E N D F / B - V . Mann, F.E.; Schenter, R.E. BNL-50991,PP.275-286; CONF-781174,PP.275-286 A V A I L A B I L I T Y - N T I S HANFOR

9450 Date January 1980 112120 870094 Delayed Beta- and Gamma-Ray Production Due to Ther-

mal-Neutron Fission of 239-Pu: Tabular and Graphical Spectral Distributions for Times after Fission Between 2 and 14000 Sec.

Dickens, J.K.; England, T.R.; Love, T.A.; McConnell, J.W.; Emery, J.F.; Northcutt, K.J.; Peelle, R.W.

NUREG/CR-1172; O R N L / N U R E G - 6 6 A V A I L A B I L I T Y - N T I S O A R N L

9503 Date September 1979 112120 870092 870094 Measurements of 239-Pu and 235-U Fission Product

Decay Power from 1 to 10**5 Seconds. c

Friesenhahn, S.J.; Lurie, N.A.

416-

E P R I - N P - 9 9 8 A V A I L A B I L I T Y - I R T CORPORATION, 7650 CON-

VOY COURT, SAN DIEGO, CA 92111 IRT

Americium


9544 Date June 1979 111210 32A000 521130 717100 793000 795254 810000


Blankets With and Without Trit ium Breeding. Henderson, D.L.; Moses, G.A. U W F D M - 3 3 4 A V A I L A B I L I T Y - F U S I O N ENGINEERING PRO-


U - W I

9725 Date January 1980 112120 870094 Fission Product Yields for Thermal-Neutron Fission of

Plutonium-239. Dickens, J.K.; McConnell, J.W. NUCL. SCI. ENG., 73(1), 42-55 O A R N L

!/

10015 Date June 1980 111110 311000 32A000 329000 511110 842000 870094



Dupree, S.A. SAND-80 -0432 A V A I L A B I L I T Y - S A N D I A N A T I O N A L LABORATO-

RIES, ALBUQUERQUE, NM, THEORETICAL DIV.

SANDIA

10015 Date June 1980 111110 311000 32A000 329000 511110 842000 870094



Dupree, S.A. SAND-80 -0432 A V A I L A B I L I T Y - S A N D I A N A T I O N A L LABORATO-

RIES, ALBLIQUERQUE, N M , THEORETICAL DIV.

SANDIA

6235 Date September 1976 122100 870095 Evaluation of 241 -Am Nuclear Data. Lgarasi, S.I. J A E R I - M - 6 2 2 1 A V A I L A B I L I T Y - D I V I S I O N OF TECHNICAL

INFORMATION, JAPAN ATOMIC ENERGY. RESEARCH INSTITUTE, T O K A I - M U R A , N A K A - G U N , IBARAK1-KEN, JAPAN

JAPAN

8498 Date January 1979 122100 870090 870095 HEDL Evaluation of Thorium Cycle Cross Sections for

E N D F / B - V . Mann, F.M. H E D L - T M E - 7 8 - 1 0 0 A V A I L A B I L I T Y - N T I S HANFOR

8853 Date September 1978 010000 111220 870095 Neutron Production from (alpha,n) Reactions in Actinide

Oxides. Lees, E.W. CONF-780921, PP.615-620 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL,


9260 Date July 1979 112760 421200 424000 711100 870094 870095 A Nondestructive Assay System for Use in Decommission-

ing a Plutonium-Handling Facility. Roche, C.T.; Vronich, J.J.; Bellinger, F.O.; Perry, R.B. A N L - 7 9 - 6 0 A V A I L A B I L I T Y - A R G O N N E N A T I O N A L LABORA-

TORY, ILL. ARGONN

9263 Date May 1979 122100 870095 A Review of the Microscopic Cross Sections for the Ameri-

cium Isotopes in the Resolved Resonance Region. Browne, J.C. B N L - 50991 ,PP. 17-32; C O N F - 781174,PP. 17- 32 A V A I L A B I L I T Y - N T I S L A L L

417-

9264 Date May 1979 122100 870095 Evaluation of 241-Am Resonance Parameters and Their

Consequences for the Unresolved Region. Derrien, H.; Fort, E.; Lafond, D. B N L - 50991 ,PP.71-81; CONF-781174,PP.71-81 A V A I L A B I L I T Y - NTIS FRANCE

9269 Date May 1979 122100 870094 870095 HEDL Evaluation of High Plutonium and Americium Cross

Sections for E N D F / B - V . o Mann, F.E.; Schenter, R.E. BNL-50991,PP.275-286; CONF-781174,PP.275-286 A V A I L A B I L I T Y - N T I S HANFOR

9834 Date March 1979 122100 870096 Curium-244 Neutron Data Evaluation. Caner, M.; Yiftah', S. IA-1353 A V A I L A B I L I T Y - S O R E Q NUCLEAR RESEARCH

CENTER, ISRAEL A T O M I C ENERGY COMMIS-SION, Y A V N E

ISRAEL

9837 Date June 1978 122100 870096 Evaluation of Neutron Nuclear Data for 245-Cm. Igarasi, S.; Nakagawa, T. J A E R I - M - 7 7 3 3 ( IN JAPANESE) A V A I L A B I L I T Y - D E P . , NTIS (U.S. SALES ONLY) ,

PC A04 /MF A01 JAPAN

- 9270 Date May 1979 122310 870094 870095 Reactor Application of Actinide Cross Section Data. Beaman, S.L.; Cowan, C.L. B N L - 50991,PP.287 - 295; CONF-781174,PP.287 - 295 A V A I L A B I L I T Y - N T I S GEE

Curium


8111.'- Date June 1978 713000 870008 870096 Subcritical Reactivity Monitoring: Neutron Yields from

Spontaneous (alpha,n) Reactions in FFTF Fuel. Ombrellaro, P.A.; Johnson, D.L. H E D L - T M E - 7 8 - 3 9 A V A I L A B I L I T Y - D E P . , NTIS (U.S. SALES ONLY) HANFOR

8730 Date March 1979 111110 870092 870094 870096 Summary of Fission Spectrum Workshop. Held at the


Stewart, L. (Ch.) L A - 7 7 3 9 - C ; ENDF-278 A V A I L A B I L I T Y - U N I V E R S I T Y OF CALIFORNIA,

LOS ALAMOS SCIENTIFIC LABORATORY, P.O BOX 1663, LOS ALAMOS, N.M. 87545

LOASL

Californium


" 6463 Date Dec. 1977 122310 870041 870098 430000 794000 Integral Tests of Niobium Cross Sections Through Simulta-


Ingersoll, D.T.; Doming, J.J.; Wehring, B.W. CONF-770401, PP.841 -848 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


CP



Green, L.; Ullo, J.J. W A P D - T M -1365 A V A I L A B I L I T Y - N T I S BETTIS

ft 6813 \.\. Date 1978*

010000 111110 870092 87009,8 A Review on Standard Fission Neutron Spectra of 235-U

and 252-Cf. Knitter, H.H. IAEA-208, VOL.I, PP. 183-195 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE

418-

B E L G I U



Fabry, A.; McElroy, W.N.; Kellogg, L.S.; Lippincott, E.P.; Grundl, J.A.; Gill iam, D.M.; Hansen, G.E.

I A E A - 2 0 8 , VOL.1, PP.233-263 A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE H A N F O R


Some Known Spectra. Zi jp, W.L.; Nolthenius, H.J.; Baard, J.H. I A E A - 2 0 8 , VOL. I , PP.265-300 A V A l L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE N E T H E R


Low and High Energy Part of the Cal i fornium-252 Neutron Spectrum.

Mannhart, W. I A E A - 2 0 8 , VOL.11, PP.227-246 A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE G E R M A N

6841 Date 1978 112120 421200 512220 870092 870098 Fission Product Yield Ratios for Uran ium-235 Fission by

Thermal and Cal i fornium-252 Neutrons. Debertin, K. I A E A - 2 0 8 , VOL.11, PP.261-263 A V A I L A B I L I T Y - I N I S M I C R O F I C H E C L E A R I N G -

HOUSE G E R M A N

6873 Date June 1978 111110 112400 421120 421130 795066 512210 512220

861000 870098 Measurement and Calculations of Cal i fornium-262 Fission

Neutron-Induced Gamma Yields in Iron. Jiang, S.H.; Werle, H. N U C L . SCI. ENG., 66(3), 354-362 G E R M A N

6954 '. . Date February 1978 111110 111220 421130 421150 430000 511120 870098 Neutron Spectrum Measurements for Radiation Protection

Purposes. Slaughter, D.R.; Rueppel, D.W.; Fuess, D.A. UCRL-52 ,415 A V A I L A B I L I T Y - C A L I F O R N I A U N I V E R S I T Y ,

L A W R E N C E L I V E R M O R E L A B O R A T O R Y L A L L

6976 Date August 1978 111110 122310 326000 511120 820000 870098 Spatial Distribution Measurements of Fission Neutrons in

Water as an Oxygen Data Test. Green, L.; Ullo, J.J. N U C L . SCI. ENG., 67(2), 172-183 BETTIS

7069 Date January 1977 111110 32A090 423140 511110 511120 793000 795254

842000 87f/098 861000 870082 Transmission of 252 -CF Fission Neutrons Through Vari-

ous Shields. Song, Y.T. NBS SPEC. PUB. 461, PP. 119-123 A V A I L A B I L I T Y - S U P T . OF D O C U M E N T S , GPO,



Storage Safe, a Transport Vessel and a Portable Shield for Cal i fornium-252. (Notes)

Sharma, S.C.; Hood, J.T. H E A L T H PHYS., 35(3), 496-498-U - M N

6853. Date February 1977 111110 421130 430000 870098 Unfolding Code System for the NE21 Sasamoto, N.; Tanaka, S. J A E R I - M - 6 9 5 2 " / A V A I L A B I L I T Y - D E P . , NT IS (6.S. SALES O N L Y ) J A P A N a 9

3 Liquid Scintillator. 8553 Date February 1979

111 110 122310 422110 870098 Measurement and Calculation of Average Activation Cross

Sections in the Spontaneous Fission -Neutron Field of 252-Cf . (Tech. Note) .

Mannhart'/'W.; Alberts, W.G.

419-

N U C L . SCI. ENG., 69(2), 333-338 G E R M A N

8631 Date 1977 111110 421140 810000 870098 Measurements of Integral Cross Sections in the Californi-

u m - 2 5 2 Fission Neutron Spectrum. Alberts, W.G.; Gunther, E.; Matzke, M.; Rassl, G. EUR-5667E/F ,PT. I I , PP.131-141;

CONF-750935,PT. I I , PP.131-141 A V A I L A B I L I T Y - O F F I C E FOR O F F I C I A L PUBLICA-


G E R M A N V

111110;,122310 8658 Date February 1979

210000 421140 430000 521130 810000 870098 (l

Testing of E N D F / B Cross-Section Data in the Californi-um-252 Neutron Benchmark Field.

Mannhart, W. O R N L / R S I C - 4 2 , PP.119-133 A V A I L A B I L I T Y - N T I S G E R M A N

Schwartz, R.B.; Grundl, J.A. S T I / P U B - 4 7 K V O L . 1 ) , PP.367-376;

CONF-771209 -P1 , PP.367-376; A V A I L A B I L I T Y - I A E A NABS

Hydrides


S428 Date October 1978 111210 329000 32AOOO 422110 511120 870003 881000

1 • 'T r i t ium Production in a Sphere of 6 - L i D Irradiated by 14 -MeV Neutrons.

Hemmendinger, A. ; Ragan, C.E.; Shunk, E.R.; Ellis, A .N. ; Anaya, J.M.; Wallace, J.M.

L A - 7 3 1 0 c A V A I L A B I L I T Y - N T I S

LOASL

Boron-Containing Compounds or Mixtures


8881 Date 1979 111110 112400 112500 421200 522230 795065 795223


Induced in Iron by 252 -C f Fission Neutrons. Jiang, S.H. D O E - T R - 7 2 ; KFK-2444 ( I N G E R M A N ) A V A I L A B I L I T Y - U S D O E T E C H N I C A L I N F O R M A -




Reactor Shielding Experiments. Seki, Y.; Santoro, R.T.; Oblow, E.M.; Lucius, J.L. O R N L - 5 4 6 7 A V A I L A B I L I T Y - N T I S S4.50 O A R N L

9192 Date May 10, 1977 111110 111210 112110 32AOOO 511110 512110 512210


the Californium Tank Experiment for Comparison with 2" x 2" N E - 2 1 3 Detector Measurements.

Straker, E.A.; Gritzner, M.L.; Harris, L.,Jr.; Schanzler, L. S A I - 7 7 - 6 5 7 - L J ^ A V A I L A B I L I T Y - S C I E N C E APPL ICATIONS, INC.,

P.O. BOX 2351, 1200 PROSPECT ST., L A JOLLA, C A L I F O R N I A 92037

SCA


Dosimetry Calibration.

8096 Date September 1978 421140 430000 882000 Neutron Attenuation Due to Boron-10 Shields. (Tech.

Note) Harvey, J.T.; Meason, J.L.; Wright, H.L. NUCL . SCI. ENG:, 67(3), 343-344 U - A R

8148 Date October 1978 122100 882000 ^ Best Values for the Cross Section of'tiie^Neutron Standard

Reaction 10-B(n,alpha sub 1)**7-L i*" i i i~ the Range from 0.1 to 2.0 Mev. (Tech. Note)

Liskien, H.; Wattecamps, E. NUCL . SCL ENG., 68(1), 132-137 BELGIU

ts 420-

8688 Date March 1979 325000 540000 820000 882000 Neutron Diffusion in Water Containing t / v and N o n - l / v

Absorbers. Bansal, R.M.; Tewari, S.P.; Kothari, L.S. NUCL. SCI. ENG., 69(3), PP.367-374 IND IA m

v.

Meta l -Hydrogenous Mixtures

0 CATEGORY N U M B E R 883000

6450 Date Dec. 1977 620000 717000 883000 312000 Optimal I ron-Water Shields for Fusion Reactors. Gilai, D.; Greenspan, E.; Levine, P.; Price, W.G.,Jr. CONF-770401, PP.731-738 A V A I L A B l L I T Y - S C I E N G c PRESS, 8 BROOKSTONE


Meta l -Ox ide Compounds or Mixtures


Actinides


6412 Date Dec. 1977 112120 887000 Prediction of Fission Product and Actinide Levels in Irradi-

ated Fuel and Cladding. Burstall, R.F.; Thornton, D.E.J. CONF-770401, PP.416-424 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6466 Date Dec. 1977 111700 719B00 795203 887000 Calculations of Neutron Radiation Levels from HTGR

Spent Fuel. Sund, R.K.; Engholm, B.A.; Su, S. CONF-770401, PP.865-872 A V A I L A B I L I T Y - S C I E N C E PRESS, 8 BROOKSTONE


6611 Date February 1978 020000 111110 329000 551120 795209 795254 870092

870094 885000 Analysis of Some Uranium Oxide and Mixed-Oxide Lat-

tice Measurements. Sher, R.; Fiarman, S. EPRI -NP-691 A V A I L A B I L I T Y - D E P A R T M E N T OF MECHANI -

CAL ENGINEERING, STANFORD UNIVERSITY, STANFORD, CAL IFORNIA 94305

EPRI

8984 Date May 1979 113100 423300 513120 760000 885000 Use of Gypsum Wallboard for Diagnostic X - R a y Protec-

tive Barriers. Glaze, S.A.; Schneiders, N.J.; Bushong, S.C. HEALTH PHYS., 36(5), 587-593 U - T X

8985 Date May 1979 113100 423300 513120 760000 885000 Attenuation Characteristics of Gypsum Wallboard. Christensen, R.C.; Sayeg, J.A. H E A L T H PHYS., 36(5), 595-600 U - K Y

6571 Date March 1978 122100 887000 Predictions of Fission Cross Sections in the 3 - to 5 - M e V

Neutron Energy Range. Behrens, J.W.; Howerton, R.J. NUCL. SCI. ENG., 65(3), 464-467 L A L L

II

6705 Date November 11, 1977 1111 10 121100 122100 887000 Systematics of Neutron-Induced Fission Cross Sections

over the the Energy Range 0.1 Through 15 MeV, and at 0.0253 cV.

Behrens, J.W. U C I D - 17509-2 AVA ILAB IL ITY-DEP. , NTIS LALL

7023 Date September 1976 111210 717000 887000 Design of a Beam-Driven Tokamak for Depletion of Acti-

nide Wastes. Rose, R.P. CONF-760935-P2, PP. 723-739 A V A I L A B I L I T Y - N T I S WEE

421 O

8 0 3 3 - ^ 1 Date August 1978 111110 220000" 325000 551110 713000 887000 793000

794000^ Preliminary Neutronic Study of Actinide Transmutation in

a Fast Reactor. Williams, M.L.; McAdoo, J.W.; Flanagan, G.F. O R N L / T M - 6 3 0 9 A V A I L A B I L I T Y - N T I S S4.50 O A R N L

8963 Date April 1979 122100 887000 Evaluation and Testing of Actinide Cross Sections. Benjamin, R.W.

" E P R I - N P - 1067 A V A I L A B I L I T Y - S A V A N N A H RIVER LAB., E.I. DU

PONT DE NEMOURS A N D CO., INC., A IKEN, S.C. ,29801 - y

DUPONT


and of 238,-rU Fast Fissions on Fission Product Decay Power. I

Trapp, T.J,Jr. v NUREG/CR-0404; OSU-NE-7806 ; THESIS A V A I L A B I L I T Y - N T I S U - O R


Waste Management. (Tech. Note) Meldner, H. NUCL. SCI. ENG., 69(3), PP.438-441 L A L L

8979. Date January 15, 1979 111210 717000 887000 Actinide Cross Section Data and Inertial Confinement

Fusion for Long Term Waste Disposal. Meldner, H. UCRL-82177; CONF-781174-6 A V A I L A B I L I T Y - D E P . , NTIS L A L L

9015 Date April 1979 111110 230000 887000 Transmutation of Waste Actinides in Light Water Reactors. Gorrell, T.C. D P - 1518 AVA1 LABI L I T Y - D U PONT DE NEMOURS (E.I.),

A N D CO., A IKEN, S.C., S A V A N N A H RIVER LAB-ORATORY

DUPONT

8740 Date Augus/l978 112120 222000 719A00 887000 Magnox Fuel Inventories: Experiment and Calculation

Using a Point Source Model. Nair, S.

0 R D / B / N - 4 3 4 9 A V A I L A B I L I T Y - C E N T R A L ELECTRICITY GEN-

ERATING BOARD, HEADQUARTERS SERVICES, REPROGRAPHIC SECTION, COUR-TENAY HOUSE, 18 WARWICK LANE, LONDON ECAP 4EB o

ENGLAN

8843 Date September 1978 010000 122310 713000 887000 Determinatjon of Transactinide Nuclear Data Required

""Accuracy for Burn-up Calculation in Fast Reactors. Usachev, L.N.; Bobkov, Yu.G.; Kolesov, V.E.; Krivtsov, A.S. CONF-780921, PP.181-186 A V A I L A B I L I T Y - O E C D , 2, RUE ANDRE-PASCAL,


9272 Date May 1979 020000 887000 Review or Integral Data on Higher Transactinides. Harker, Y.D.; Anderl, R.A.; Turk, E.H. BNL-50991,PP.327-348; CX)NF-781174.PP.327-348 A V A I L A B I L I T Y - N T I S EDGERT



Camplin, W.C.; Grimwood, P.D.; White, I.F. NRPB-R94 A V A I L A B I L I T Y - H M S O ISBN 0 85951 1219 ENGLAN

10011 Date July T980 112120 112760^532000 795217 810000 887000 A User's Manual for the ORIGEN2 Computer Code. Croff, A.G. O R N L / T M - 7 1 7 5 A V A I L A B I L I T Y - N T I S , PC A 0 9 / M F A01

422-

O A R N L

10057 Date May 1980 010000 122100 887000 Transactiniuni Isotope Nuclear Data - 1979. Proceedings

of the Second Advisory Group Meeting on Transac-tinium Isotope Nuclear Data Organized by the IAEA

and held in Cadarache, 2 - 5 May 1979. IAEA I A E A - T E C D O C - 2 3 2 A V A I L A B I L I T Y - I N I S MICROFICHE CLEARING-

HOUSE, IAEA, WAGRAMERSTRASSE 5, P.O. BOX 100, A-1400 V I E N N A , AUSTRIA

IAEA

4 2 3 j / H j

%

AUTHOR INDEX

AUTHOR INDEX

Aase, D.T. 010000 9935, 32A000 8190, 521130 8190 8373, 717000 8373, 717100 8190 9935, 810000 8190 8373

Abagjan, A.A. 512220 6472, 521110 6473, 521210 6473, 820000 6472, 861000 6472, 870082 6472

Abdel-Khalik, S.I. 010000 6773 8471, 210000 6767, 222000 8251, 329000 9127, 521130 9542, 522130 9542, 717000 6767 8251 9542, 717100 6773 8467 8471 9127, 810000 6773 8467 9127 9542, 869999 8251, 870006 6767, 870042 6767

Abdou, A. 717000 8253, 721100 8253

Abdou, M.A. 010000 6422 7030 8830 9785,121100 8401, 121200 8401, 122100 9785, 122110 8,401 8403, 122200 9785, 122210 8401 8403, 123000 8955, 210000 8495 8830 8955, 220000 8401

'' 8403, 531000 7030 8401 8403,8955, 532000 7030 8401 8403 8955, 717000 6422 7000 7004 7030 8495 8830 9785, 793000 8403 8955, 794000 8401 8403 8955,810000 7000 7004 7030 8401 8403 8495 8830 8955 9785

Abdullaev, Kh.Sh. 122110 8114, 713000 8114, 810000 8114

Abrol, V. 112930 8835, 220000 8835, 222000 8835, 610000 8835

Abu-Shumays, I.K. 311000 9750, 326000 9750, 511110 9750

Aceto, A. 423250 9292, 713000 9292

Ackers, J.G. 020000 9227, 220000 9227, 430000 9227

Ackroyd, R.T. 32C000 8777

Adams, R.J. 511120 9060, 853500 9060

Aframian, A. 422110 8756, 422150 8756

Aikens, A.E.,Jr. 222000 9005, 230000 9005

Aizawa, O. 410000 9737

Akiyama, M. 111110 6832, 410000 6832, 421130 6832, 421140 6832, 511120 6832, 760000 9822

Albert, T.E. 329000 8797, 421130 9193, 430000 • 9193, 511110 6746, 512210 6746, 522130 9193,

551110 6746, 552210 6746, 610000 8797, 719A00 6746 8797, 721100 8797, 722100 8797, 793000 6746 8797 9193, 830000 9193, 853100 8797, 861000 8797

Alberts, W.G. 122310 8553, 220000 9382, 420000 9382, 421140 8631, 422110 8553, 430000 9382, 810000 8631, 870098 8553 8631

Albrecht, H. 112120 8578 9593,112930 8578 9469, 719A00 8578 9469 9593

Alcouffe, R.E. 32A000 9066 9744, 551110 9744

Alder, K. 010000 8239, 112710 8239, 610000 8239

Alexander, C.W. 112120 8678, 552110 8678, 719A00 8678, 861000 8678

Alexander, D.R.J 111120 8918, 870092 8918 o

Allen, E.J. 325000 8603, 719A00 8603, 793000 8603, 810000 8603

Allen, J.W. 410000 8414, 421200 8414, 424000 8414

Allen, P.R. 223000 8795, 32A000 8795, 719X00 8795, 721100 8795, 722100 8795

Almond, P.R. 111220 9287, 410000 9051, 511120 8530, 760000 9051 9287, 842000 8530, 843000 8530, 861000 8530

Alsmiller, F.S. 112930 6945, 222000 6945

426-

Alsmiller, R.G.,Jr. 112760 9114, 112930 6945, 122110 8035, 220000 8034, 222000 6945, 312000 7096, 32AOOO 8034, 325000 7096, 329000 6425, 421000 6948, 510000 9028 9856, 511110 8035, 512210 8035, 531000 7090 8214, 532000 7090 8214, 551110 6948 8034 8214, 552120 8214, 552210 8034, 713000 7096, 717000 6425 7090 8214 9028 9114 9115,721100 6425, 750000 9028, 793000 7090 8034 8035 9028 9856, 810000 7090 8214 9856, 820000 8034, 853100 8034, 853700 8035, 853900 8035, 861000 6948 8034 8035

-V

Altiparmarkov, D. 329000 6234, 511110 6234, 810000 6234

0 Amherd, N.A. 010000 8941, 111210 8941, 717000

8941

Amian, W. 112120 9592, 719B00 9592

Amnion, R.L. 210000 8411, 717000 8411, 870023 8411

An, S. 020000 6462, 551110 9632, 551120 6462 9632, 713000 6397, 721200 6397, 760000 9822, 861000 6462 9632, 870011 6462

Anaya, J.M. 111210 8428, 422110 8428, 511120 8428, 870003 8428, 881000 8428

Anderl, R.A. 020000 9272, 887000 9272

Anderson, J.D. 111220 8752

Anderson, M.D. 111220 9287, 760000 9287

Andresen, H. 210000 9492, 717000 9492, 870022 9492, 870023 9492, 870041 9492

Anghinolfi, M. 421130 9399, 430000 9399

Anno, G.H. 112930 9018, 632110 9018, 731200 9018

Antonini, D. 511120 6458, 713000 6458, 870011 6458

Appelman, K.H. 122110 8640, 421140 8640

Aragones, J.M. 122110 8395

Arcipiani, B. 312000 6576, 53100,0 6576, 717000 6576, 794000 6576

Arkhipov, V.A., et al. 410000 9434, 719A00 9434

Aronson, R. 32DOOO 9726 V- .

Arthur, E.D. 122100 9021, 870040 9021

Asakura, Y. 112760 6978 8915, 719AOO 6978 8915

Asami, T. 122100 9366, 810000 9366

Asaoka, T. 551120 6464, 718000 6387 6464, 721100 6387, 721200 6464, 731300 6464

Ash, W. „ 710000 9195, 750000 9195

Attix, F.H. 121200 8982

Audenaerde, K. 32A100 8230

Aull, J. 32A000 9380, 551110 9380

Aull, J.E. 32A100 10014 j

Auxier, J.A. 020000 9798, 220000 9798, 223000 8799, 719A00 8799, 721200 8799

Avayev, V.N. 329000 7117, 532000 7117, 861000 7117, 870082 7117

Avery, A.F. 010000 6385, 112770 6405, 223000 6405, 713000 6385, 717000 6375, 719C00 6405, 721100 6385

Azimi-Garakani, D. 122310 8991, 222000 8547, 410000 6837, 422130 6837, 511120 6837

Baard, J .H. 122100 9574 9575, 122310 6816, 123000 9574 9575, 421140 6816 6829 8638 9574, 421150 9575, 430000 8638, 511120 6816 6829, 794000 9574, 810000 6816 9574 9575, 870092 6816, 870098 6816

Babel, P.J. 722100 6672, 810000 6672

427-

Bachmann, H. 717000 6877, 870003 6877

Badger, B.(Ed.) 717000 8980

Badyayev, V.V. 421150 7120,511120 7120,861000 7120, 870013 7120, 870022 7120

Baes, C.F., III 112930 9027, 220000 9027, 222000

9027

Bair, J.K. 111220 8996

Baker, A.L. 711100 10064

Baker, C.C. 717000 7001,810000 7001

Baker, V.C. 521130 7130, 522130 7130, 531000 7130, 532000 7130, 717000 7130, 810000 7130

Bakumenko, O.D. 713000 6421

Baltar, J . 020000 9046, 220000 9046, 430000 9046

Bampton, M.C.C. 521130 8373, 717000 8373, 810000 8373

Band, I.M. 112710 8044,610000 8044

Bangart, R.L. 112710 8781, 112760 8781, 112930 8781, 222000 8781, 719A00'8781

Banham, M.F. 421200 6742, 424000 6742, 870094 6742

Bansal, R.M. 325000 8688, 540000 8149 8688, 820000 8149 8688, 882000 8688

Bapat, V.N. 423250 7081

Baptista, G.B. 122200 8822, 613000 8822

Barbier, M. 223000 6477, 719A00 6477

Barbucci, P . 32A000 6447, 719A00 6389, 721100 6389

Barefoot, E.D. 112930 8644, 719A00 8644

Bareiss, E.H. 325000 9095, 551110 9095, 810000 9095

Bargellini, M.L. 511120 6458, 713000 6458, 870011 6458

Barinov, A.L. 421130 7110, 421140 7110, 521230 7110, 710000 7110, 719A00 7110

Barish, J . 112760 9114,312000 7096,325000 7096, 510000 9028;'713000 7096, 717000 9028 9114, 750000 9028, 793000 9028

Barnes, J .M. 020000 8517, 112760 9114, 122310 8517, 210000 6247 9030, 220000 8034, 32A000 8034 8517 8563, 329000 6425, 521130 6247 7130 8563 8807 9030, 522130 6247 7130 8807, 531000 6247 70907130 8214,532000 6247 7090 7130 8214, 551110 8034 8214 8517, 552110

• 8517, 552120 8214, 552210 8034, 717000 6247 6425 7090 7130 8214 8517 8563 9030 9114 9115, 717100 8807, 721100 6425 8517, 793000 6247 7090 8034 8517 8807 9030, 794000 8517 8807, 810000 6247 7090 7130 8214 8563 8807, 820000 8034, 853100 8034 8517, 861000 6247 8034 8517 9030, 862000 9030, 870003 6247, 870023 9030, 870027 9030

Barnes, J.W. 711100 10062 10063 10064

Barnes, P.R. 220000 8513, 410000 8513, 423210 8513

Barnett, C.S. 010000 8522, 329000 8522, 430000 8522

Barr, W.L. 010000 8942, 111210 8942, 717000 8942

Barrett, R.J. 122110 9442, 122210 9442, 794000 9442, 810000 9442

Barschall, H.H. 010000 6769 9454, 111210 6769 9454, 111220 6769, 210000 6769, 717000 6769, 810000 6769

Bartholomew, G.A. 010000 9641, 717500 9641

428-

Bartine, D.E. 010000 6430, 111220 8901, 122110 7129, 122210 7129, 220000 9532, 511110 7129, 512210 7129, 551110 9532, 552110 9532, 552210 9532, 717500 8901, 719B00 6430, 793000 9532, 810000 7129, 830000 7129, 845000 9532, 853100 7129, 870090 8901, 870092 8901, 870094 8901

Bartlett, W.T. 020000 6893 9224 9528, 113100 9528, 220000 6893 9224 9528, 430000 6893 9224, 845000 9528

Barton, T.P. 220000 9031, 223000 9031, 420000 9031, 423140 9031, 717000 9031

Bass, L.P. 321000 7102, 511110 7102, 551110 7102, 820000 7102, 861000 7102

Bass, R.B. 112120 6469 6904, 532000 6469 6904, 719A00 6469 6904

Bassini, A. 310000 9064

Basu, A.S. 423250 7080

Basu, T.K. 717000 8924, 870004 8924

Battat, M. 111210 6623, 210000 6623, 521130 6623, 717000 6623, 810000 6623

Battat, M.E. 020000 6417 6887,111210 6424 8926, 112710 9441, 122100 9441, 220000 6417 6887, 511110 8926, 610000 6887 9441, 710000 6424 6935, 717000 6935 9441, 793000 6935 9441, 810000 9441, 853100 6935

Baum, J.W. 020000 9036, 423210 9036

Baur, A. 010000 10008, 322000 9900, 329000 10008, 712000 9900, 810000 9900

Bazazyants, N.O. 122100 8113, 870001 8113

Beach, J.L. 111110 9045, 111220 9045, 422140 9045

Beat, J.W. 010000 7036, 210000 7036, 717000 7036

Beal, S.K. 112930 6637, 222000 6637

Beam, G.B. 430000 8391

Beaman, S.L. 122310 9270, 870094 9270, 870095 9270

Beck, C.L. 010000 8191, 122310 8191, 870090 8191, 870092 8191

Beck, H.L. 112710 10137, 522120 10137, 632110 10137, 810000 10137

Becker, M. 121100 6649, 122110 6454 6649 6758 6802, 122310 6880 8655 8671 8715, 312000 6456 8715, 324000 6803, 511110 6758 6803, 719A00 8655 8671 8715, 794000 6758 6880, 810000 6758 8655 8671, 861000 6803, 870011 6880, 870092 6803

Beeler, J.R.,Jr. 210000 8627, 810000 8627

Beeler, M.F. 2i0000 8627, 810000 8627

Beer, M. 010000 9994, 020000 9997, 329000 9994 9997, 521130 9997, 810000 9997

Begovich, C.L. 112930 6945, 222000 6945

Behmard, M. 410000 9051, 760000 9051

Behrens, J.W. 121100 6705, 122100 6571 6705, 887000 6571 6705

Bell, L.G. 112710 8781,112760 8781,112930 8781, 222000 8781, 719AOO 8781

; Belli, M. 020000 8635, 421140 8635, 551120 8635, 810000 8635

Bellinger, F.O. 424000 9260, 711100 9260, 870094 9260, 870095 9260 <•

Benatti, P.I.N. 210000 8622, 422110 8622, 861000 8622

Bender, D.J. 010000 7021 8942, 111210 8942, 717000 7021 8942, 810000 7021

429

15

Bendt, P.J. 112120 8502 8510, 510000 8502, 512220 8502, 532000 8510, 870092 8502 8510, 870094 8502 8510

Benenati, R. 010000 8945, 111210 8945, 531000 6592, 532000 6592, 717000 6592 8945, 870013 6592

Benjamin, R.W. 122100 8963, 887000 8963

Bennett, J.E. 711100 10064

Bennett, R.A. 010000 8585, 210000 8585, 421140 8585, 430000 8585, 713000 8585, 717000 8585, 719A00 8585, 719B00 8585, 810000 8585

Benoist, P. 310000 8550, 321000 8144, 422110 8250

Bensch, F. 421110 8619,540000 8619

Bentley, J. 210000 7007, 870042 7007

Benzi, V. 010000 8848,112500 8848,121100 8848

Beranek, F. 121100 9128, 122110 9065, 210000 9637, 32AOOO 9128, 510000 9065 9128 9325, 521130 9128 9325, 717000 9128 9325 9637, 810000 9128

Berger, M.J. 020000 9034, 220000 9034, 430000 9034

Berman, B.L. 111600 9124, 810000 9124

Bernard, S.R. 112760 9376, 220000 8213 8974 9376, 610000 9376, 711100 9376, 845000 8213 8974 9376

Bertini, H.W. 112930 6945^ 222000 6945

Bertolini, E. 010000 7040 8939, 111210 8939, 717000 7040 8939

Bertoncini, P.J . 717000 7000, 810000 7000

Berwald, D.H. 010000 9485, 210000 9485, 230000 8481, 717000 8481 9485, 793000 8481, 794000 8481,810000 9485

Beslu, P. 112760 6408 6411, 223000 64113927, 713000 6408, 719A00 6408 6411 8927, 719B00 6408

Bettis, E.S. 010000 7016 8943,111210 7089 8943, 32AOOO 8563, 521130 8563, 717000 7016 7089 8563 8943, 310000 7016 8563

Bevensee, R.M. 210000 9618, 851000 9618

Beyer, W.A. 329000 6520

Beyerlein, A.L. 711100 10064

Bhat, M.R. 010000 9789, 122100 6588 9789, 122200 9789, 717000 9789, 717100 9789, 810000 9789, 870092 6588

Bhati, S. 220000 9330, 845000 9330

Bhatia, D.P. 121100 7067, 329000 7067, 810000 7067

Bickford, W.E. 010000 9935,112760 8459,112930 8459, 220000 8459, 223000 8459, 521130 8459, 531000 8459, 532000 8459, 717000 8459, 717100 9935, 810000 8459

Bihy, L. 111220 9291, 220000 9291, 760000 9291

Billings, M.P. 719A00 6374

Binney, S.E. 010000 8140, 111120 8140, 420000 8140, 424000 8140

Bishop, B.L. lt 121100 6479,210000 6479 9029 9030, 521130 9030, 717000 9029 9030, 793000 9029 9030, 794000 6479, 810000 9029, 861000 6479 9030, 862000 9030, 870023 9030, 870027 9030

Bishop, G.B. 430000 8545

Bisht, J.S. 220000 6870 8379 8993, 511110 8993, 551110 6870, 552210 6870, 632110 8379, 820000 8993, 842000 8993, 845000 6870, 853100 8993

Biswas, M. 423230 8831, 522210 8992, 841000 8992, 853100 8992, 861000 8992, 870013 8992, 870082 8992

430-

Bjarngard, B.E. 0200009220,220000 9220,430000 Bohn, T.S. 122110 9442, 122210 9442, 794000 9220 9442, 810000 9442

Bjerke, M.A. 010000 6343, 112120 6343, 330000 Boicourt, R.M. 122110 9442,122210 9442,794000 9763,532000 6343,719A00 8120,719B00 9763, 9442, 810000 9442 794000 9763

Blachot, J. 010000 8419 8845, 112120 8419, 112710 8845, 122200 8845, 810000 8845, 870092 8419, 870094 8419

Blackburn, L.D. 210000 6392, 713000 6392

Blackstock, A.W. 220000 6856, 423135 6856, 521210 6856

Block, R.C. 511120 8916, 861000 891%

Boegli, J.S. 112710 8781, 112760 8781, 112930 8781, 222000 8781, 719A00 8781

Boehme, R. .8880

Boffi, V.C. 422110 8250

Bogart, S.L. (Ed.) 010000 8406 8407

Bohm, J. 020000 9199, 220000 9199, 430000 9199

Bohm, J.K. 760000 9285, 845000 9285

Bohn, E.M. 122310 6584, 713000 6584, 870092 6584, 870094 6584

Boioli, A. 312000 6381,713000 6381

Bolta, C.C. 717000 7004, 810000 7004

Bolyatko, V.V. 112500 7114, 421140 7112,423250 7114, 511110 7114, 512210 7114, 512220 7114, 719A00 7112, 721100 7112, 721200 7112, 853800 7112 7114, 861000 7112 7114

O

Bomar, E.S. 222000 6982, 230000 6982

Bunzon, L.L. 112930 6940, 610000 6940

Boot, S.J. 010000 6658, 220000 9289, 421140 6658, 430000 6658, 511120 6658 9289, 810000 6658,820000 9289

Booth, L.A. 010000 7013, 717000 7013, 810000 7013

Booth, T.E. 010000 10005 9978, 329000 10005 8773 9067 9978, 521130 9978, 721100 10005, 810000 9978, 853100 10005, 870011 10005

'o

Borak" T.B. 220000 9061

Borchers, R.R. 717000 10156 tj

Borst, F J . 112930 9926, 220000 9926, 222000 9-926 ",„

Bosler, G.E. 122110 6691, 32A000 9744, 521130 6691 8278, 522130 6691 8278, 551110 9744, 717000 6691, 793000 6691, 810000 6691 8278

Botts, T. „ 230000 9083, 717000 9083 WT __

Bouchard, J . 421140 8605, 422130 8605, 430000 8605, 870092 8605, 870094 8605

Bourdet, L. 010000 10008, 329000 10008

Blomeke, J.O. 112930 7091, 220000 7091, 222000 7091, 713000 7091, 719A00 7091, 719B00 7091

Blomquist, R.N. 010000 9987, 326000 9548, 329000 9987

«

Bluhm, H. 410000 8595, 421120 8595, 421130 8595, 430000 8595

Bobkov, Yu.G. 010000 8843, 122110 6662, 122310 6662 8843, 713000 6662 8843, 810000 6662, 887000 8843

111110 8880, 330000 8880, 713000

431-

Bourque, R. 717000 7017,810000 7017

Bowers, G.A. 329000 9562, 731100 9562, 793000 9562

Boyd, A.W. 423240 8612, 531000 8612, 532000 8612, 810000 8612

Bozzi, L. 511120 6458, 713000 6458, 870011 6458

Bracke, T.P. 112120 6469, 532000 6469, 719A00 6469

u

Breon, S.R. 9825

f J

210000 9825, 717000 9825, 870007

Briaris, D.A. 620000 9276, 717000 9276

Brindley, K. W. 010000 6461, 713000 6461

Brinkley, F.W.,Jr. 32AOOO 9744, 551110 9744

Broadhead, B.L. 122310 8661, 210000 8661, 312000 8661, 32A000 8661, 521130 8661, 794000 8661, 810000 8661

Broerse, J .J . 020000 9218 9219, 220000 9218 9219 9293, 410000 9295, 420000 9295, 421150 9293, 430000 9218 9219, 511120 9293 9295

Broerse, J .J . (Ed.) 020000 6510, 111110 6510, 111210 6510, 111220 6510, 122100 6510, 122200 6510, 810000 6510, 845000 6510

Brogli, R.H. 717100 6231, 810000 6231, 870090 6231, 870092 6231

Bromley, D.A. (Ed.) 010000 9063, 420000 9063

Bryan, D.E. 421130 6517, 430000 6517, 521230 6517, 522230 6517, 853100 6517, 861000 6517

Bryant, E.W. (Eds.) 010000 8650, 122310 8650, 312000 8650

Bryant, P.M. 020000 9179, 220000 9179, 222000 9179

Brynjolfsson, A. 020000 9039, 220000 9039, 423210 9039, 423240 9040, 430000 9039 9040

Bubinin, A.A. 512220 6472, 820000 6472, 861000 6472,870082 6472

Buchholz, F.W. 111110 9328,112110 9328,420000 9328, 421200 9328, 511120 9328, 512120 9328, 810000 9328

ir Bucholz, J.A. 32A100 9527, 330000 6452, 794000

9527

Buckel, G. 551110 6979, 713000 6979

Buckman, R.W.,Jr. 210000 8411, 717000 8411, 870023 8411

Buffa, A. 020000 9212, 220000 9212, 430000 9212

Bullock, R.E. 111210 8951, 210000 8951, 717000 8951, 870006 8951, 870014 8951

Bullough, R. 121100 6709, 210000 6709, 713000 6709, 717000 6709, 861000 6709

Bunch, W.L. 713000 6372

Brown, R.W. 512110 9634, 632110 9634, 853100 9634

Bunting, R.L. 112710 8973, 222000 8973, 223000 8973, 719A00 8973

Browne, J.C. 112500 8097, 122100 9263, 870073 8097, 870095 9263

Brudnoy, D.M. 210000 8627, 810000 8627

Burger, G. 020000 9218, 220000 9218 9284 9293, 410000 9295- 420000 9295, 421150 9293, 430000 9218, 511120 9293 9295, 551110 9284, 552210 9284, 845000 9284

Brunovsky, M. 210000 9456, 719A00 9456, 861000 9456

Burgkhardt, B. 220000 8995, 410000 9367, 420000 9367, 511120 9367, 521210 8995, 522210 8995

432-

c-Burian, J . 713000 6394, 721200 6394, 870011 6394 Caglioti, E. 020000 6420, 122110 6420

Burke, W.C. 112710 8781, 112760 8781, 112930 8781, 222000 8781, 719A00 8781

Burkhart, L.E, 711100 10064

Burkholder, H.C. 230000 9613 9886

Burns, T.J. 111220 8901, 551110 9314, 713000 9314, 717500 8901, 793000 9314, 794000 9314, 810000 9314, 870090 8901, 870092 8901, 870094 8901

Burrows, T.W. 122100 9828, 870024 9828

Burstall, R.F. 010000 6446, 112120 6412, 32F000 6446, 887000 6412

Bushong, S.C. 513120 8984, 760000 8984, 885000 8984

Buslik, A.J. 311000 8233, 325000 8233

Bussac, J . 000000 8259

Bussard, R.W. 717100 7024, 8100(50 7024 i.\

Bustraan, M. 122310 8421, 521130 8421, 810000 8421

Butler, H.M. 223000 8799, 719A00 8799, 721200 8799

Butler, J . 010000 6370 6380 6461 8838, 020000 6380, 122100 8838, 122200 8838, 312000 6380, 713000 6461, 810000 8838

Butler, M.K. 020000 9755

Byoun, T.Y. 722100 6672, 810000 6672

Caboret, J. 020000 9046, 220000 9046, 430000 9046

Cacciapouti, R.J. 424000 10000, 719A00 10000

Cacuci, D.G. 310000 6701, 324000 6701, 511110 6701

Calamand, D. 511120 6458, 713000 6458, 870011 6458

Cameron, E. 717100 9866, 810000 9866

Camplin, W.C. 222000 9849, 230000 9849, 887000 9849

Candelore, N.R. 329000 8237, 719A00 8237

Caner, M. 122100 9834, 870096 9834

Capo, M.A. 719A00 6374

Cardito, J .M. 223000 8795, 32AOOO 8795,719A00 8795, 721100 8795, 722100 8795

Carlson, C.W. 020000 6586,122100 6586, 870092 6586

Carlson, G.A. 010000 7012 8942 9483, 111210 8942, 717000 7005 7012 8942 9483, 717100 9483, 810000 7005 7012 9483

Carpenter, J .M. 111220 9894

Carpenter, S.G. 010000 8191,122310 8191,870090 8191, 870092 8191

Carruthers, R. 010000 8937, 111210 8937, 717000J

8937

Carter, L.L. 111220 9493, 210000 9493, 329000 6431 9986, 511110 9797, 713000 9986, 717000 9493, 750000 9986, 810000 9493 9986, 861000 9797

Carter, M.D. 112770 6405, 223000 6405, 719C00 6405

Cashwell, E.D. 010000 10004 9022 9978, 121200 6620 8116, 329000 10004 6436 6619 6620 6621 8116 8729 9022 9067 9978, 512110 8116, 521130 9978, 610000 8116, 632200 6619, 717000 6436 6619, 810000 6620 8729 9978, 830000 8116

Cassapakis, C. 210000 8753, 870014 8753

Castiaux, M.A: 424000 7088

Chatterjee, A. 121100 7057, 810000 7057

Chaudat, J.P. 020000 9273, 870094 9273

Caswell, R.S. 121100 9281, 220000 9281, 810000 Chaudhuri, N. 121200 7054 7059, 810000 7054 9281 7059

Cavalio, L. 020000 9200, 220000 9200, 430000 9200

Chellew, N.R. 210000 9825, 717000 9825, 870007 9825

Cavanaugh, G.P. 223000 8794, 32A000 8802, 551110 8802, 710000 8802, 719A00 8794 8802, 721100 8794 8802, 722100 8794, 810000 8794 8802

Cechak, T. 522110 8829, 861000 8829, 870006 8829, 870013 8829, 870050 8829, 870082 8829

Celnik, J . 223000 8796,511110 8565,512210 8565, 521130 8796, 522130 8796, 551110 8796, 552210 8796, 631000 6444, 719A00 8796, 721100 8796, 722100 6444 8796, 770000 8565, 793000 8565, 810000 8796, 830000 8565, 853100 8565 " S? Q

Cerkaskov, Yu.M. 223000 6406, 719A00 6406

Cermak, A.F. 711100 10064

Chamany, B.F. 719C00 6429

Chambers, J.M. 010000 6365, 329000 6365

Chang, K.S.J. 325000 9095, 551110 9095, 810000 9095

Chang, Y.Y. 112120 8925

Chao, J. 717000 8480 9146, 793000 9146

Chemtob, M. 010000 8855, 122100 8855, 210000 8855, 760000 8855, 845000 8855

Chen, l . - J . 310000 9401,321000 9401

Chen, S. 220000 89B4.>'329000 8904, 793000 8904, 845000 8904

Chen, S . -Y. 220000 9070, 845000 9070

Chen, W. 113100 6698, 210000 8887,220000 6698, 423210 6698, 423250 6698, 553120 6698, 717000 7017 8887, 810000 7017, 845000 6698, 861000 8887

Cheng, E.T. 32B000 9821, 521130 8135, 522130 8135, 532000 8135, 551110 7029 8947, 552110 7029 8947, 717000 7029 8135 8947 9821, 721100 7029, 810000 7029 8947

Cheng, E.T.C. 220000 6737

Chester, C.V. 220000 8513, 410000 8513, 423210 8513

Chestnutt, M.M. 112770 6405, 122310 8674, 223000 6405, 312000 8674, 521130 8674, 713000 8674, 717000 6375, 719A00 8674, 719C00 6405, 810000 8674, 861000 8674

Chao, Y. 122310 8667 9249

Chapin, D.L. 521130 8946 9869, 522130 8946 9869, 717100 8946 9869, 793000 8946 9869, 810000 8946

Chatterjee (DAS), J.M. 424000 7088

Chi, J.W.H. 521130 8946, 522130 8946, 717100 8946, 793000 8946, 810000 8946

Chi, J.W.H. (Ed.) 521130 9326, 522130 9326, 717000 9326, 793000 9326, 810000 9326

Childs, R.L! 312000 9929, 32A000 9929

434-

Chilton, A.B. 220000 9070, 329000 8049, 512110 Cohen, M.O. 010000 9996, 112120 6903, 329000 8690 9634 9730, 632110 8690 9634 9730, 8886 9996, 532000 6903; 719A00 6903 9996, 820000 9730, 830000 9730, 845000 9070, 721100 9996 853100 8690 9634, 861000 9730

Collings, P.J. 122110 8975, 122310 8975, 810000 Cho.N.Z. 112120 6747,532000 6747,870092 6747 8975

Choi, C.K. 717000 7006, 810000 7006

Chrien, R.E. 511120 8916, 861000 8916

Christensen, R.C. 513120 8985, 760000 8985, 885000 8985

Claiborne, H.C. 112760 10080, 230000 10080, 532000 10080, 851000 10080

Clarke, J.F. 010000 8936, 111210 8936, 717000 8936

Clarke, R.H. 020000 9179, 112930 9526, 220000 9179, 222000 9179 9526

Clarke, R.W. 020000 9214, 220000 9214, 430000 9214

Clemmer, R.G. 210000 9825, 717000 9825, 870007 9825

Cline, J.E. 112930 8644, 719A00 8644

Cloninger, M.O. 230000 9613

Goth, P. 717000 8924, 870004 8924

• Cobb, D.D. 711100 10062 10063 10064

Coffman, F.E. 010000 7036, 210000 7036, 717000 7036

Coffman, F.E.(Dir.) 111210 9427, 111220 9427, 210000 9427, 717000 9427, 810000 9427

Cohen, B.L. 112930 8048,222000 8048

Cohen, J.J. 010000 9617, 230000 9617

Cohen, M.M. 010000 8956, 111210 8956, 210000 8956, 717000 8956, 810000 8956

Collins, J.L. 112120 6858 9467, 112730 10072 6858,112930 10072 9467,532000 6858,719A00 10072 6858 9467, 870092 6858

Collins, J.T. 112710 8781, 112760 8781, 112930 8781, 222000 8781, 719A00 8781

Collins, P.J. 122310 8651, 521130 8651, 810000 8651

Collins, R. 223000 6401, 719C00 6401

Coltman, R.R.,Jr. 010000 8876, 210000 8876, 717000 8876, 810000 8876

Commission of the European Communities 010000 8584,421140 8584

Comolander, H.E. 122110 8515, 122210 8515, 32A000 8515, 521130 8515, 522130 8515, 794000 8515

Condit, W.C.,Jr. 717000 7005, 810000 7005 o

Conley, G.H. 719A00 9804

ConnfR.W. 010000 6773 701 1 8471 9388 9482, 111210 8960, 122110 9065, 122310 8818, 210000 6771 8909 9069 9482 9637, 312000 •8818, 329000 9127, 510000 9065 9325, 521130 8816 9069 9325, 711100 9388, 717000 6771 7003 7011 8909 8960 9069 9325 9482 9637, 717100 6773 8471 8816 9127 9388 9636 9820 9866, 793000 8816, 794000 8816, 810000 6771 6773 7003 7011 8816 8909 8960 9069 9127 9866, 861000 9069

Connor, J / . J 12120 9143

Constantine, G. 010000 9781,122100 9781,717000 9781, 810000 9781

435-

Constantinescu, D. 122110 8770, 521130 8770, 713000 8770, 810000 8770

Courtney, J.W. 020000 9528,113100 9528,220000 9528, 845000 9528

Constatinescu, D.A. 325000 9095, 551110 9095, 810000 9095

Cowan, C.L. 122110 8975, 122310 8975 9270, 810000 8975, 870094 9270, 870095 9270

Cook, D.L. 521130 8566, 717000 8566, 810000 8566

ft Cook, W.A. 32C000 6933, 632200 6933

Cool, W.S. 010000 6309, 112600 6309, 112710 6309, 230000 6309

Cooper, B. 717500 7026, 810000 7026

Cooper, G.W. 329000 9127, 717100 9127, 810000 9127 (/

Coppola, M. 020000 9218, 220000 9218 9293, 421150 9293, 430000 9218, 511120 9293

Coppola, M. (Eds.) 410000 9295, 420000 9295, 511120 9295

Cort, G.E. 32AOOO 9310, 521130 9310, 522130 9310, 717000 9310, 810000 9310

Cortez, J.R. 220000 6856, 423135 6856, 521210 6856

Cortner, M.W. 220000 8513, 410000 8513, 423210 8513

Corvisiero, P. 421130 9399, 430000 9399

Coyne, J.J. 121100 9281,-220000 9281, 810000 9281

Cramer, S.N. 111220 7095, 122310 7095, 511110 7095, 521130 10006, 551110 9110, 552210 9110, 719B00 9110, 810000 9110, 853100 10006, 861000 10006, 870008 7095

Cristenson, D. 111220 8994

Croff, A.G. 112120 10011 8516 8678, 112760 10011,122110 8516 9933,122210 9933,123000 8516, 532000 10011 8516, 552110 8678,711100 9933, 719A00 8120 8678, 793000 9933, 794000 9933,810000 10011 9933, 861000 8678, 887000 10011

Croney, S.T. 112710 8973, 222000 8973, 223000 8973, 719A00 8973

Cross, B. 122310 8675, 421140 8675, 430000 8675

Cross, F.T. 112930 9926, 220000 9926, 222000 9926

Cross, W.G. 010000 8857, 122100 8857, 210000 8857, 511110 9288, 760000 8857, 845000 8857, 870082 9288

Cosack, M. 220000 9382, 420000 9382, 430000 9382

Crouch, E.A.C. 010000 8844,112710 8844, 122200 8844, 810000 8844

Costa, L. 112760 6408,713000 6408,719A00 6408, 719B00 6408

Cotter, S.J. 112710 8783, 220000 8783 9611, 222000 9611, 223000 8783, 711100 8783, 845000 8783

Courtney, J.C. (Eds.) 010000 8791, 223000 8791, 719A00 8791, 721100 8791, 722100 8791

Csikai, J. 0100009791,1112109791,1221009791, 717000 9791, 810000 9791

Cuculeanu, V. 122110 8770, 521130 8770, 713000 8770, 810000 8770

Culbert, M.E. 521130 9869, 522130 9869, 717100 9869, 793000 9869

436-

Cullen, D.E. 020000 6419,121100 7048 8127 8128 8223 9230 9940, 121200 9862, 122100 8681, 122110 6419 7048 8223 8462 8682 8977,122200 8681 8812, 122210 9862, 123000 9940, 32AOOO 9862, 810000 8127 8128 8223 8681 8682 8812 9230 9862

Cuninghame, J.G. 010000 6743 8277, 112120 6743 8277, 870092 8277, 870094 8277

Cunningham, G.W. 325000 8786, 713000 8786

Cunningham, L.J. 010000 6309, 112600 6309, 112710 6309, 230000 6309

Cupini, E. 010000 9999, 329000 9999, 719A00 9999

Czirr, J.B. 020000 6586, 122100 6586, 870092 6586

D'Angelo, A. 122310 6573, 861000 6573

Daenner, W. 111210 8952, 210000 8952, 717000 8952

Dahl, E.B. 321000 8479

Dajani, A.T. 722100 6672, 810000 6672

Dalessandro, J.A. 111210 8951, 210000 8887 8951, 717000 8887 8951, 861000 8887, 870006 8951, 870014 8951

Dandl, R.A. 010000 8943, 111210 8943, 717000 8943

Danek, J.L. 112930 8436, 222000 8436, 870092 8436

Dang, V. 010000 8945, 111210 8945, 717000 8945

Darrouzet, M. 112120 8871, 122100 8871, 122200 8871

C Das, S.G.° 111220 9894

Davenport, L.C. 010000 9190, 020000 9190, 719A00 9190

David, M. 423250 7083

Davidson, J.W. 112120 7032, 230000 7032 9559, 32A000 7032, 717000 7032, 810000 7032, 870006 7032

Davies, B.S.J. 010000 8844, 112710 8844, 122200 8844, 810000 8844

Davis, H.S. 710000 6804, 740000 6804, 853100 6804, 853300 6804, 853400 6804, 853700 6804

Davis, J.C. 111220 8752

Davis, W., Jr. 112930 8436, 222000 8436, 870092 8436

Dawn, T.-Y. 310000 9401,321000 9401

Dayem, H.A. 711100 10062 10063 10064

de Beer, G.P. 329000 6439, 721100 6439

De Carli, A. 511120 6458, 713000 6458, 870011 6458

De Gangi, N. 010000 9996, 329000 9996, 719A00 9996, 721100 9996

De Gangi, N.L. 122110 9071, 328000 9071, 329000 9071, 511110 9071, 512110 9071, 830000 9071

De Leeuw-Gierts, G. 010000 6814, 020000 8592, 111110 9122, 210000 6848 8618, 421110 6814 8592 8594 9122, 421120 6814, 421130 6814, 422110 8618, 423250 8618, 430000 8594 9122, 511120 6848, 532000 8618, 713000 8592 8618 9122, 810000 8618, 861000 6848, 870092 6814 6848

De Leeuw, S. 010000 6814, 020000 8592, 111110 9122, 210000 6848 8618, 421110 6814 8592 8594 9122, 421120 6814, 421130 6814, 422110 8618, 423250 8618, 430000 8594 9122, 511120

' 6848, 532000 8618, 713000 8592 8618 9122, 810000 8618, 861000 6848, 870092 6814 6848

a 437

De Matteis, A. 010000 9999, 329000 8092 9999, Derrien, H. 122100 9264, 870095 9264 719A00 9999

de Saussure, G. 121100 6861, 122100 6317 6532, 123000 6861, 810000 6861, 870090 6532, 870092 6317

Debertin, K. 112120 6841, 421200 6841, 512220 6841, 870092 6841, 870098 6841

Debrue, J. 210000 8618, 422110 8618, 423250 8618, 532000 8618, 713000 8618, 810000 8618

Decker, T.R. 112930 8029

Defreece, D.A. 717000 7010, 810000 7010

Degtyarev, S.F. 112500 7113, 421200 7113

Dejonghe, G. 010000 10008 9989, 122310 9989, 329000 10008 9989, 521130 9989

Dekker, J.W.M. 010000 8275, 112120 6674, 122100 6674, 122110 6676, 122310 6676 8275 8872, 312000 6676, 521130 6676, 713000 6674 8872, 810000 6676 8275

del Campo, J.G. 111220 8996

Delafield, H.J. 111110 8380

delMarmol, B. 32A000 9746,551110 9746, 713000 9746

Delmore, J.E. 112120 6514, 713000 6514, 870093 6514

Demeshev, R.S. 531000 7105,532000 7105,810000

7105

Demidov, A.M. 112400 6996, 610000 6996

DeMier, W.V. 230000 9613

Denschlag, H.O.. 010000 8851, 112120 8851 Denschlag, J.O. 010000 8418,112120 8418,123000

8418, 870092 8418, 870094 8418

Desprets, A. 511120 6458, 713000 6458, 870011 6458

DeStaebler, H. 710000 9195, 750000 9195

Deutsch, O.L. 010000 10005 9978, 329000 10005 6431 9978, 521130 9978,721100 10005, 810000 9978, 853100 10005, 870011 10005

Devillers, C. 010000 8271, 112120 8271, 112760 6411, 210000 8628, 223000 6411, 532000 8271, 551120 8628, 719A00 6391 6411,721100 6391, 722100 6391, 810000 8628, 870092 8271, 870094 8271

(J

Devoto, R.S. 717000^005, 810000 7005

Dexter, W.L. 010000 8942, 111210 8942, 717000 ° 8942

Di Pasquantonio, F. 32A000 6447, 719A00 6389, 721100 6389

Dickens, J.K. 112120 6696 6941 7046 8030 8031 8917 9450 9725 9819, 221000 6696, 421200 7046, 430000 6696 7046, 532000 6696, 610000 8030 8031, 794000 6696, 870092 7046 9819, 870094 6696 8031 8917 9450 9725

Dickson, H.W. 020000 9225, 220000 9225, 222000 8121,223000 8121,430000 9225

Dierckx, L.A. 111210 8926, 511110 8926

Dierckx, R. 010000 6668 8600, 111210 6623, 210000 6623, 421140 6668 8600, 430000 8600, 521130 6623, 717000 6623 6668, 810000 6623

Dietz, R.J. 711100 10062 10063 10064

Difilippo, F.C. 122100 6317, 422130 8478, 870092 6317, 870093 8478

Diggs, B.R. 122110 8515 9933, 122210 8515 9933, 32A000 8515, 521130 8515, 522130 8515, 711100 9933, 793000 9933, 794000 8515 9933, 810000 9933

\s 0 f,f

438

DiUman, L.T. 220000 8974, 845000 8974

Dimbylow, P.J. 121100 8778,122100 8778,870001 8778, 870006 8778, 870008 8778

Disney, R.K. 010000 8710, 551110 8710, 552210 8710,713000 8710, 719B00 8710, 793000 8710, 794000 8710, 810000 8710

Dmitrev, P.P. 112710 6791, 610000 6791

Dobson, R.L. 020000 8978, 220000 8978, 845000 8978

Dodds, H.L.,Jr. 122110 9093, 210000 8248, 32AOOO 8248 9093, 717000 8248, 794000 9093, 870079 9093

DOE 010000 90} 4, 123000 9014

Doggett, J. 717000 7005, 810000 7005

Doggett, J.N. , 010000 8942, 111210 8942, "vl7000 8942

Doherty, T.J. 521130 8373, 717000 8373, 810000 8373

Dolan, P.J. 000000 8261

Dolphin, G.W. 010000 8780, 220000 8780

Doran, D.G. 121100 8888,210000 7044 8888 8957, 717000 7044, 810000 7044 8888 8957

Dore, M.A. 112930 9018, 632110 9018, 731200 ^9018

Doming, J.J. 010000 9743, 122310 6463',' 310000 9743, 32A000 9743, 325000 9743, 430000 6463 9729, 794000 6463 9729, 870041 6463, 870098 6463

Doropheev, G.A. 010000 8590, 020000 8590, 421140 8590

Douglas, J.A. 423135 8378, 430000 8378

Dove, W.F. 010000 8940, 111210 8940, 717000 8940 ,,

Dragt, J.B. 122110 6676, 122310 6676, 312000 6676, 521130 6676, 810000 6676 "

Drake, D. 521130 9542, 522130 9542, 717000 9542, 810000 9542

Draper, E.L.,Jr. 112120 7032, 230000 7032, 32A000 7032, 717000 7032, 810000 7032, 870006 7032

Drexler, G. 010000 7078, 020000 9210, 121200 7078, 220000 7078 9210, 423240 7078, 430000 9210

o 0 Drischler, J.D. 122310 6627, 312000 6627, 521130

O 6627, 719A00 6627, 810000 6627, 870001 6627, 870008 6627, 870013 6627, 870092 6627

Druke, V. 551120 8866,719B00 8866, 810000 8866

Duarte, P.W.E.P. 122200 8822, 613000 8822

Dubi, A. 310000 6647, 311000 8143 9707, 329000 6432 8021 8143 8749 8969 8997 9254 9707, 423135 8832, 423250 8833, <551110 9707, 721100 8969, 870011 8969 9707

Dubinin, A.A. 321000 7102, 511110 7102, 521110° 6473, 521210 6473, 551110 7102, 820000 7102, 861000 7-102 \ ^

Duderstadt, J.J. 230000 8481, 717000 8481, 793000 8481, 794000 8481

Dudziak, D.J. 010000 7028 8895 9787, 111210 * 6424 9787, 122110 6691 7050, 122210 7050,

122310 8895, 210000 7028, 311000 8143, 312000 7050 8895 9787, 32A000 7028 9787, 329000 7028 8143 8749,521130 6691 7028 7050 8278 8948, 5221306691 7050 8278, 531000 7028, 532000 7028, 710000 6424 6935, 717000 6691 6935 7028 7050 820I7 8895 8948 9787, 793000 6691 6935,810000 6691 7028 70508278 8948 9787, 853100 6935

t» O

Duftschmid, K.E. 020000 9209, 220000 9209, 430000 9209 C

439-

Dunn, T.A. 210000 8624, 220000 8624, 713000 8624 J '

Dunning, D.E.,Jr. 112760 9376, 220000 8213 9112 9376 9927 9928, 222000 9112 9927, 610000 9376, 711100 9376, 845000 8213 9376 9928

Dupont, C. 322000 9900, 712000 9900, 810000 9900

Dupree, S.A. 311000 10015,32A000 10015,511110 10015, 712000 9383, 713000 9383, 810000 9383, 842000 10015, 870094 10015

Dutton, L.M.C. 010000 6427, 719COO 6427

Dyer, F.F. 112120 6944 8455, 112760 10074, 210000 6944, 421200 6944, 719B00 10074 6944 8455, 810000 6944, 870006 10074

Dyer, N.C. 112710 8973, 222000 8973, 223000 8973, 719A00 8973

Easterly, C.E. 112760 6946, 112930 6946, 220000 9031, 222000 6946, 223000 9031, 420000 9031, 423140 9031, 717000 6946 9031

Eastham, J.F. 430000 8737, 794000 8737

Eastman, E.A.B. 223000 8795, 32A000 8795, 719A00 8795, 721100 8795, 722100 8795

Eaton, J.R.P. 522120 6445, 632110 6445

Eckerl, H. 020000 9210, 220000 9210, 430000 9210

Eckerman, K.F. 220000 9927, 222000 9927

Eggermont, G. 423210 9041, 423300 9048, 430000 9041 9048

Eggleston, R.L. 112120 8724, 870094 8724

Egorov, Yu.A. 000000 7097, 223000 6406, 719A00 6406 0

Ehrlich, M. 020000 9200, 220000 9200, 430000 9200

Eichholz, G.G. 020000 9798, 220000 9798

Eid, A.M. 421140 8615, 423135 8615, 423250 8615, 531000 8615, 532000 8615

i.

EisenhWr, C. 010000 6809, 111110 6809, 122200 &09, 210000 8604, 410000 6809, 421140 6809 8(Jp4, 422130 8604, 430000 6809 8604, 511120 6809, 770000 6809, 870092 8604, 870094 8604

Eisenhauer,i C.M. ' 512110 9730, 632110 9730, 820000 9730, 830000 9730, 861000 9730

Eisenlohr, H.H. 020000 9220,220000 9220,430000 9220

Eissa, H.M. 760000 9285, 845000 9285

EI-Kolaly, A.M. 421140 8615, 423135 8615, 423250 8615, 531000 8615, 532000 8615

Elkert, J. 223000 6404, 719A00 6404

Ellis, A.N. 111210 8428 , 422110 8428, 511120 8428, 870003'8428, 881000 8428

Emel, W.A. 112120 6514, 112930 8644, 713000 6514, 719A00 8644, 870093 6514

Emery, J.F. 112120 6696 6941 7046 8030 8031 9450, 221000 6696, 421200 7046, 430000 6696 7046, 532000 6696, 610000 8030 8031, 794000 6696, 870092 7046, 870094 6696 8031 9450

Emigh, C.R. 111210 6623 8926, 210000 6623, ft 511110 8926, 521130 6623, 717000 6623,

810000 6623

Emmert, G.A. 32A100 8230

Emmett? M.B. 010000 10007, 329000 10007, 713000 6373, 719BOO 6467, 721200 6467

Endres, G.W.R. 220000:8649 9609, 223000 8649 9609, 423135 8649 9609, 423250 8649 9609

Engelstad, R.L. 521130 9542, 522130 9542,717000 9542, 810000 9542 0

440-

Engholm, B.A. 111700 6466, 719B00 6388 6466, 887000 6466

England, T.R. 010000 8422 9256, 112120 8118 8206 8422 8502 9256 9450 9845, 122110 8115, 510000 8502, 512220 8502, 532000 8118 8206 8422 9845, 719AOO 9845, 793000 8115 9845, 810000 8115, 870090 8206, 870092 8118 8206 8422 8502, 870094 8118 8206 8502 9450

Engle, W.W.,Jr. 010000 8710, 311000 6455, 551110 8710, 552210 8710, 713000 6373 8710, 719B00 8710, 793000 8710, 794000 8710, 810000 8710

Engler, D.R. 711100 10064

Engstrom, G. 510000 9099, 511110 8199, 512110 8199 9099, 830000 9099, 853100 8199

Erdman, C.A. 010000 6213, 112710 6213, 112760 6213, 112930 6213, 713000 6213, 870092 6213, 870094 6213

Erdtmann, G. 112710 6883, 610000 6883

Erickson, A.L. 112120 8724, 870094 8724

"J

Erikson, A.L. 112120 6514, 713000 6514, 870093 6514

-•> „ Ermumcu, G. 329000 9990, 719A00 9990

Ertek, C. 122310 8675, 421140 8675, 430000 8675

Estiot, J.C. 122310 6459 8865, 511120 6458, 713000 6458 8865, 810000 8865, 861000 6459, 870011 6458 6459

et al. 010000 7016 9307 9324, 111210 10154 10155, 112710 9100, 121100 9128, 210000 9618, 222000 9005, 223000 9307, 230000 9005 9307, 32AOOO 9)28, 325000 10136, 329000 9306, 510000 9128, 521130 9128 9306, 551110 10136, 610000 9100, 717000 10132 10154 10155 10156 7000 7003 7004 7015 7016 7017* 9128 9306, 717100 9324, 719A00 9804, 793000 9306, 794000 9306, 810000 7000 7003 7004 7015 7016 7017 9128 9306 9307, 851000 9618

ETF Design Center Team 717000 9931

Etherington, E.W. 210000 8602, 713000 8602, 861000 8602 o

Etnier, E.L. 112710 8783, 112760 8735, 220000 8735 8783 9112, 222000 9112, 223000 8783,° 711100 8783, 845000 8783

Evans, B.D. 210000 9494, 717000 9494, 870013 9494

Evans, H.B. 010000 8413, 410000 8413 8414, 421200 8413 8414, 424000 8413 8414

Evans, J .H. 410000 8733, 712000 8733, 863000 8733

Everett, C.J. 010000 9022, 121200 6620, 329000 6436 6619 6620 6621 9022, 632200 6619, 717000 6436 6619, 810000 6620

Ewbank, W.B. 020000 9042, 112710 9042, 123000 8211, 220000 9042, 810000 8211

Eyre, B.L. 121100 6709, 210000 6709, 713000 6709, 717000 6709, 861000 6709

Fabbri, F. 112120 8871,122100 8871,122200 8871

Fabrick, A.J. 112930 6997, 222000 6997

Fabry, A. 010000 68126815, 020000 6513,122310 6812 6815, 210000 8618, 410000 6837 6843, 422110 8618, 422130 6837 6843, 423250 8618, 430000 6812, 511120 6513 6815 6837 6843, 532000 8618, 713000 8618, 810000 6815 8618, 870092 6815, 870098 6815

Fadeev, M.A. 522110 8389, 522210 8389, 861000 8389, 870004 8389, 870006 8389, 870050 8389, 870082 8389

Fair, M.F. 020000 9798, 220000 9798

Fairchild, L.L. 112120 6944 8455, 210000 6944, 421200 6944, 719B00 6944 8455, 810000 6944

441-

Fan, C - K . 112120 6747, 532000 6747. 870092 6747

Farinelli, U. 010000 8586 9131, 210000 8586, 421140 8586, 713000 8586 9131, 719AOO 8586, 810000 8586

Farley, W.E. 423110 6706, 511120 6706 6875, 512210 6875, 521230 6706, 830000 6706 6875, 861000 6706

i/

Farrar, H.,IV 010000 6668, 121100 9491, 122100 9491, 210000 8957 9491, 421140 6668, 717000 6668 9491,810000 8957 9491

Fasolo, J. 111210 9421,620000 9421,710000 9421, 717000 9421, 810000 9421

Fink, J.H. 010000 8942,111210 8942,717000 8942

Fiorini, L. 312000 6381, 713000 6381

Firmin, G.H. 522120 6445, 632110 6445

Fischer, A. 421140 8639, 430000 8639, 511120 8639

Fisher, J.C. 111110 9045, 111220 9045, 422140 9045

Flanagan, G.F. 230000 8033, 551110 8033, 713000 8033, 793000 8033, 794000 8033, 887000 8033

Fleming, D.M. 020000 6893 9224, 220000 6893 9224, 430000 6893 9224

Fenn, J.O. 111220 8986, 750000 8986

Fiarman, S. 020000 6611, 551120 6611, 870092 6611, 870094 6611, 885000 6611

Fiche, Ch. 010000 8845, 112710 8845, 122200 8845, 810000 8845

Fieg, G. 410000 8595, 421120 8595, 421130 8595, 430000 8595

Fields, D.E. 222000 8784

Filai, D. 521130 7035, 522130 7035, 717100 7035 793000 7035, 810000 7035

Fletcher, J.K. 326000 8026

Fodor, G. 421140 6844

Fogelson, S. 010000 8945, 111210 8945, 717000 8945

Foley, J.E. 711100 10064

Ford, M.R. 220000 8974, 845000 8974 o

Ford, W.E.,III 122110 8515 9442 9933, 122210 8515 9442 9933, 32A000 8515, 521130 8515, 522130 8515, 711100 9933, 793000 9933, 794000 8515 9442 9933, 810000 9442 9933

Filges, D. 717000 8924, 870004 8924

Filipy, R.E. 112930 9926, 220000 9926, 222000 9926

Fillo, J.A. 010000 8945, 111210 8945, 521130 9342, 522130 9342, 531000 6592, 532000 6592, 717000 10132 6592 8945 9342, 793000 9342, 870013 6592

Finck, R. 222000 6470, 719A00 6470

Finfgeld, C.R. 010000 8956, 111210 8956, 210000 8956, 717000 8956, 810000 8956

Fort, E. 010000 8274, 112120 8871, 122100 8871 9264, 122200 8871, 123000 8274, 810000 8274, 870095 9264

Fowler, T.B. 312000 6629, 325000 6629 6943, 5511l'0 6629 6943, 713000 6629 6943, 810000 6629 6943

Fraley, S.K. 329000 6313 8750, 632200 8789

Franc, L. 719C00 6253

Francis, C.C. 710000 8803, 719A00 6390 8803, 721100 6390 8803, 810000 8803

442-

Frank, E.G. 111110 9045, 111220 9045, 422140 9045

Fuketa, T. 010000 8864, 122100 8864, 810000 8864

Frank, T.G. 010000 7013, 717000 7013, 810000 7013

Fraser, J.S. 010000 9641, 717500 9641

Fray, R.R. 222000 8088, 719A00 8088

Frazzoli, F.V. 424000 9145

Freeman, S. 423135 8832, 423250 8833

Freestone, R.M. 112120 6941

Frejaville, G. 112760 6408',6411, 223000 6411 8927, 713000 6408, 719A'6O 6408 6411 8927, 719B00 6408

Frescura, G.M. 112930 9468, 719C00 9468

Friedlein, H.P. 010000 8854,122100 8854, 122200 8854, 220000 8854, 760000 8854, 793000 8854, 845000 8854, 870006 8854, 870008 8854

Fries, H.M. 010000 8239, 112710 8239, 610000 8239

Friesenhahn, S.J. 112120 9503, 421130 6517, 430000 6517, 521230 6517, 522230 6517, 853100 6517, 861000 6517, 870092 9503, 870094 9503

Fritscher, U. 717000 6877, 870003 6877

Frohner, F.H. 010000 8847, 122100 8847, 861000 8847, 862000 8847

Fu, C.Y. 111220 8808, 122100 6700 8808 8823, 122310 9853, 123000 9853, 810000 8808, 870006 8823, 870090 6700

Fuess, D.A. 410000 8225, 421130 6954, 421150 6954, 430000 6954 8225, 511120 6954, 870098 6954

Fuja, R. 111210 9421, 620000 9421, 710000 9421, 717000 9421, 810000 9421

Fuller, G.M. 717000 7010, 810000 7010

Furetta, C. 423250 9292, 713000 9292

Furuhashi, A. 760000 9822

Furuta, K. 551120 6464,718000 6387 6464,721100 6387, 721200 6464, 731300 6464

Furuta, Y. 020000 9839,423135 7079 8613,423250 8613, 531000 8613, 532000 8613

Fuse, T. 551120 6464, 718000 6387 6464, 721100 6387, 721200 6464, 731300 6464

Gabriel, T.A. 121100 6479, 210000 6479 9029 9030, 510000 9028, 521130 9030, 717000 9028 9029 9030, 750000 9028, 793000 9028 9029 9030, 794000 6479, 810000 9029, 861000 6479 9030, 862000 9030, 870023 9030, 870027 9030

Gado, J. 323000 6854, 324000 8500, 326000 8500, 327000 8500, 511110 8500, 521130 8500, 540000 6854, 719A00 6854, 820000 8500, 861000 8500, 870013 8500, 870092 8500

Gago, C.B. 325000 8474

Galbreth, T.M. 710000 8803,719A00 8803,721100 8803, 810000 8803

Galliani, M. 210000 8622, 422110 8622, 861000 8622

Ganapol, B.D. 310000 9749, 510000 9749, 511110 9749

Gandini, A. 122310 8673, 312000 6878 8098 8673

Ganesan, S. 122310 9733

Ganguly, A.K. 423230 7070, 423250 7080 7083, 522130 7070

Ganguly, K. 326000 97^1 SN

443-

Garcia, R.D.M. 310000 8146

Gardner, M.A. 121100 8906, 122100 8906, 810000 8906

Gardner, R.P. 430000 8391

Garg, S.B. 121100 6499, 122110 6499 7061 9155 9156, 810000 6499, 870090 7061, 870092 7061

Garlea, I. 410000 6843,421140 6844,422130 6843, 511120 6843

Garrett, P.M. 223000 8928

Garsou, J.L. 423300 9053, 430000 9053

Garvey, P.M. 010000 9641, 717500 9641

Gasnikov, N.K. 512220 6472, 820000 6472, 861000 6472, 870082 6472

Gast, R.C. 329000 8237, 719A00 8237

Gaviri, A. 222000 8547

Gelbard, E.M. 010000 7030 9987, 329000 9506 9759 9987, 531000 7030, 532000 7030, 717000 7030, 719B00 9759, 810000 7030

Gentry, J.C. 010000 6630, 122100 6630, 810000 6630

George, D.C. 112120 8206 9979, 122210 9979, 410000 8414, 421200 8414, 424000 8414, 532000 8206, 793000 9979, 810000 9979, 870090 8206, 870092 8206, 870094 8206

Gerdin, G.A. 717000 7006, 810000 7006

Gerhard, M.A. 632200 9023

Germogenova, T.A. 122110 7100, 321000 7101 7102, 323000 7101, 511110 7100 7101 7102, 512220 6472, 521110 6473, 521210 6473, 551110 7102, 810000 7100, 820000 6472 7102, 861000 6472 7101 7102, 870006 7101, 870082 6472

Gerstl, S.A.W. 111210 8950, 122110 7050, 122210 7050, 122310 10146 8664 8950, 311000 8143 9707, 312000 6378 7050 8664, 32A000 8664 8950, 329000 8143 8969 9707, 521130 10146 7050 8950, 522130 7050 8950, 551110 9707, 620000 8950, 717000 10146 7050 8664 8950, 721100 8969, 810000 10146 7050 8664, 870011 8969 9707

Ghoniem, N.M. 010000 9386, 210000 9386,717000 9386, 810000 9386

Ghose, A.M. 000000 7051, 010000 7051, 121100 7057 7058, 121200 7053 7058, 423230 8831, 632200 7058, 810000 7053 7057

Giacomelli, E.J. 410000 8523, 424000 8523, 870006 8523

Gilai, D. 122310 8665, 312000 6450 8141 8665, 32A000 8665, 521130 8665, 620000 6450, 717000 6450, 883000 6450

Gillett, T.C. 329000 8804, 719A00 8804, 721100 8804, 810000 8804

Gilley, L.W. 020000 9225, 220000 9225, 430000 9225

Gilliam, D.M. 010000 6815, 020000 6513, 122310 6815, 511120 6513 6815, 810000 6815, 870092 6815, 870098 6815

Gilligan, J.G. 32A100 6765, 717000 6765

Gimm, H.A. 121200 6937, 122200 6936, 810000 6936 6937

Girzikowsky, R. f)20000 9220, 220000 9220, 430000 9220

Gittus, J.H. 210000 9497, 717000 9497, 810000 9497

Glasstone, S. 000000 8261

Glaze, S.A. 513120 8984, 760000 8984, 885000 8984

444 O

Glushchenko, A.I. 421130 7110-7111, 421140 7110, 421200 7111, 521230 7110'"7111, 522230 7111, 710000 7110 7111, 719A00 7110 7111, 810000 7111

Grnur, K. 020000 6799, 511120 6799, 861000 6799

Goans, R.E. 220000 9044 9394, 329000 9044, 845000 9044

Gober, W.E. 421130 6517, 430000 6517, 521230 6517, 522230 6517, 853100 6517, 861000 6517

Godfrey, T.N.K. 010000 10003 9978,329000 10003 9978, 521130 9978, 810000 9978

Godwal, B.K. 310000 7066, 511110 7066, 713000 7066, 870092 7066, 870094 7066

Goel, B. 121100 6677, 122100 9266 9705, 210000 6677 8477, 810000 9705,^861000 6677 8477, 870094 9266

Goel, B. (Comp,) 122100 6757, 810000 6757

Gogolak/C.V. 421200 6900

Gogotova, L.G. 322000 7099,330000 7099,521130 7099, 522130 7099, 820000 7099

Gohar, Y. 121100 8401,121200 8401,122110 8401 8403 9442, 122210 8401 8403 9442, 123000 8955, 210000 8955, 220000 8401 8403, 521130 9897, 531000 8401 8403 8955, 532000 8401 8403 8955, 551110 7029, 552110 7029, 717000 7029, 717100 9897, 721100 7029, 793000 8403 8955 9897, 794000 8401 8403 8955 9442, 810000 7029 8401 8403 8955 9442 9897

Gohar, Y.M. 329000 8228, 521130 8228, 717000 8228, 810000 8228

Goland, A.N. 121100 9487, 210000 8957 9487, 717000 9487, 810000 8957 9487

Gold, R. 010000 6668 6679 6812, 122310 6812, 421140 6668, 430000 6812, 531000 6679, 532000 6679, 713000 6679, 717000 6668

Gold, R.E. 210000 8411, 717000 8411, 870023 8411

Goldberg, E. 111210 9252, 112400 9252, 112500 9252, 122310 9252, 423110 6706, 511120 6706, O 521230 6706, 830000 6706, 861000 6706

Goldsmith, M. 329000 8235 8236, 719A00 8235 8236, 870092 8235 8236

Goldstein, H. 010000 6376, 121100 6383, 312000 6376

Goldstein, M. 010000 9998, 312000 9998, 329000 9998, 717000 9998, 810000 9998

Goldstone, J.A. 121100 8429, 210000 8429,870029 8429

Gomaa, M.A. 421140 8615, 423135 8615, 423250 8615, 531000 8615, 532000 8615

Gonnord, J. 010000 10008 9989, 122310 9989, 329000 10008 9989 9990, 521130 9989, 719A00 9990

Good, W.M. 220000 9044, 329000 9044, 845000 9044

Goosman, D.R. 421130 8744, 430000 8744

Gopala, K. 112200 7060,810000 7060

'Gopinath, D.V. 000000 7051, 010000 7051, 330000 7063 7065, 551110 7065, 632120 7076, 810000 7076, 870092 7065, 870094 7065

Gorbatov, V.S. 112500 7114, 423250 7114, 511110 7114, 512210 7114, 512220 7114, 853800 7114, 861000 7114

Gordinier, M. 32A100 8230

Gore, B.F. 230000 8036,717000 8036,810000 8036

Gorrell, T.C. 230000 9015, 887000 9015

Goryachev, I.V. 010000 8257, 521120 8257,522120 8257, 731200 8257

445-

Goryavhev, I.V. 620000 7107

Gotoh, H. 010000 6842, 020000 6842, 421140 6842, 511120 6842

Gough, W.C. 010000 7041 8941, 111210 8941, 717000 7041 8941

Gove, N.B. 112120 8516, 122110 8516, 123000 8516, 532000 8516

Gowda, R. 121200 7056, 810000 7056

Graham, C.L. 423250 9055

Graham, ,R.F. 112760 10080, 230000 10080, 532000 10080, 851000 10080

Grahan, C.L. 423250 6707

Gralnick, S.L. 32A100 6765, 717000 6765

Grandjean, P. 020000 8754, 310000 8551 8754, 422110 8250

Grant, W.H. 111220 9287, 511120 8530, 760000 9287, 842000 8530, 843000 8530, 861000 8530

Graves, R.G. 511120 8530, 842000 8530, 843000 8530, 861000 8530

Gray, S.A. 010000 8780, 220000 8780

Gray, W.J. 210000 7034, 717000 7034, 870006

Green, L. 122310 6976,422120 6710, 511120 6710 6976, 521130 8819 9869, 522130 9869, 717100 9869, 793000 8819 9869, 820000 6710 6976, 870090 8819, 870092 8819, 870098 6710 6976

Greenspan, E. 010000 9998, 122310 8665, 312000 6450 8141 8665 9551 9998, 32A000 8665, 329000 9998, 521130 7035 8665, 522130 7035, 620000 6450, 717000 6450 9998, 717100 7035, 793000 7035, 810000 7035 9998, 883000 6450

Greenwood, L.R. 010000 6668, 111220 8485 9490, 122100 8485 9490, 122310 8254 9400, 210000 8485 8957, 421140 6668 8485, 422110 9400, 430000 8254, 521230 9490, 717000 6668 8485 9490, 794000 8254, 810000 8485 8957 9490 Si

Gregene, A.O. 020000 9037, 423210 9037

Gregory, M.V. 122110 9000 '

Grenier, G. 111220 9286

Griffith, R.V. 111110 9045, 111220 9045, 422140 9045, 719A00 8800, 721200 8800

Grigoryev, E.I. 010000 8590, 020000 8590, 421130 8625, 421140 8590 8625, 511120 8625

Grillmaier, R. 111220 9291, 220000 9291, 760000 9291

Grimes, W.R. 010000 8790, 717100 8790, 810000 8790

Grimesey, R.A. 521130 9123, 522130 9123, 717000 9123, 810000 9123

Grimm, K.N. 122210 8004, 326000 8004 I >

Grimstone, M.J. 421140 8601, 430000 8601, 794000 8601

Grimwood, P.D. 220000 6857, 222000 6857 9849, 230000 6857 9849, 887000 9849

Gritzner, M.L. 421130 9193, 430000 9193, 511110 6746 9192, 512110 9192, 512210 6746 9192, 522130 9193, 551110 6746, 552210 6746, 719A00 6746, 793000 6746 9192 9193, 830000 9192 9193, 870007 9192, 870098 9192

Groer, P.G. 220000 8210

Grossman, L.M. 112120 6608 6747, 532000 6608 6747, 870092 6747

Grossmann, W. 010000 8944,111210 8944,717000 8944

Grundl, J. * 010000 6809, 111110 6809, 122200 6809, 210000 8604, 410000 6809, 421140 6809 8604, 422130 8604, 430000 6809 8604, 511120 6809, 770000 6809, 870092 8604, 870094 8604

V ')

446

Grundl, J.A. 010000 6815, 020000 6513 9223, 111110 9223, 122310 6815, 430000 9223, 511120 6513 6815, 810000 6815, 870092 6815, 870098 6815 9223

Gruppelaar, H. 010000 8275, 112120 6674 9832, 122100 6674 6675 9832, 122310 8275, 713000 6674, 810000 6675 8275 9832

Gruppelaar, K. 122310 8872, 713000 8872

Gnenther, P. 122100 6585, 870092 6585, 870094 6585

Guenther, P.T. 122100 6498, 870092 6498, 870094 6498

Guiho, J . - P . 020000 9196, 220000 9196, 430000 9196

Guinan, M.W. 210000 7008, 870041 7008, 870050 7008 Kf'

Gunther, E. 421140 8631, 810000 8631, 870098 " 8631

o Gupta, S.K. 513200 8919

Gupton, E.D. 220000 9378, 420000 9378

Gur, Y. 122100 6572, 122110 8201, 713000 8201, 810000 8201

Gur'yeva, N.A. 325000 7098, 521130 7098, 522130 7098, 632110 7098, 820000 7098

Gusev, N.G. 112710 6791,610000 6791

Guthrie, G.L. 122310 8659, 210000 8659, 421140 8659, 430000 8659, 719A00 8659, 861000 8659

Gutmacher, R.G. 711100 10064 f)

Gwin, R. 111110 6761, 122100 6761, 870090 6761 i'i

Hadermann, J. 230000 9558

Haese, R.L. 112120 8516, 122110 8516, 123000 8516, 532000 8516

Hagan, W.K. 421130 9193, 430000 9193, 521110 9724, 522130 9193, 793000 9193 9724, 830000 9193, 853100 9724

Hagenson, R.L. 32AOOO 9310, 521130 9310, 522130 9310, 717000 9310, 810000 9310

Hager, H. 328000 8010, 551110 8010

Haider, J . 020000 9220,220000 9220,430000 9220

Hajnal, F. 430000 8543

Hakkila, E.A. 711100 10062 10063 10064

Hall, M.C.G. 010000 9988, 312000 9988, 329000 9988, 521130 9988, 810000 9988

Hamilton, G.W. 010000 8942, 111210 8942, 717000 8942

Hamm, R.N. 112B00 8215, 112720 9185, 121200 8215, 329000 8215 9185, 512110 9185, 820OOO 8215 9185

Hammer, Ph. 020000 9273, 870094 9273

Hampel, V.E. 010000 9231 9232, 020000 9231 9232, 410000 9231 9232, 511120 9231 9232, 551120 9231 9232

Hancox, R. 010000 7037, 717000 7037

\Handschuh, J.A. 122110 9991, 329000 9991, 711100 9991, 793000 9991, 794000 9991, 810000 9991

a Hankins, D.E. 719A00 8800, 721200 8800

Hannan, A.H.M.A. 020000 6830, 410000 6830 6837 6838, 421130 6830, 421140 6830 6838, 422130 6837, 511120 6830 6837 6838, 810000 6838 /

Hansen, G.E. 010000 6815, 020000 6513, 122310 6815, 511120 6513 6815, 810000 6815, 870092 6815,870098 6815

447-

Hansen, L.F. 111210 8860 9252, 112400 9252, 112500 9252, 122310 8859 9252, 511110 6468, 511120 6875 8859, 512210 6875, 512220 8859, 521130 7020, 522130 7020, 551110,8860, 717000 7020 8859, 717100 8860, 810000 7020 8860, 820000 6468, 830000 6875, 853100 6468, 861000 6468, 870029 8859, 870041 8859, 870090 8859, 870092 8859 8860

Hanson, D.L. 112760 9020, 719B00 9020

Hardy, J.,Jr. 010000 9129, 020000 6544 9129, 122310 9129, 511110 6543, 719AOO 6543 6544 9129, 820000 6544, 870090 9129, 870092 6543 6544 9129

Harihar, P. 122310 9400, 422110 9400

Harima, Y. 020000 9839

Harker, Y.D. 020000 6834 8636 9272, 111110 6864, 410000 6834 6864, 4211.40 6834 6864 8636, 511120 6834 8636, 713000 6864 8636, 717000 8356, 770000 6864, 810000 6864 8356 8636, 887000 9272

Harkness, S.D. 010000 8258, 210000 8258

O Harling, O.K. 210000 9492, 717000 9492, 870022

9492, 870023 9492, 870041 9492

Harms, A.A. 717100 9068

Harris, D.R. 122110 9991,122310 8655 8671 8715, 312000 8715, 329000 9991, 424000 10000, 711100 9991, 719A00 10000 8655 8671 8715, 793000 9991, 794000 9991, 810000 8655 8671 9991 ^

O

Harris, J. 710000 9195,750000 9195 h

Harris, L.,Jr. 421130 6517, 430000 6517, 511110 9192, 512110 9192, 512210 9192, 521230 6517, 522230 6517, 793000 9192, 830000 9192^ 853100 6517, 861000 6517, 870007 9192, 870098 9192

Harrison, K.G. 220000 9289 9466, 430000 9466, 511120 9289, 820000 9289

Harrison, N.T. 020000 9179, 220000 9179, 222000 9179

Harrison, R.C. 111110 9328,112110 9328, 420000 9328, 421200 9328, 511120 9328, 512120 9328, 810000 9328

Harrod, D.L. 210000 8411, 717000 8411, 870023 8411

Hartmann, G. 111220 9291, 220000 9291, 760000 9291

Harvey, J.A. 422140 8392, 430000 8392, 794000 8392

Harvey,, J.T. 421140 8096, 430000 8096, 882000 8096

Harvey, T.F. 112920 9539, 522120 9539, 731200 9539

Havel, S. 210000 9456, 719A00 9456, 861000 9456

Hayashda, Y. 112200 6868, 329000 6868, 863000 6868, 870013 6868, 870082 6868

Hayashi, Shu A. 010000 6842, 020000 6842, 421140 6842,511120 6842

Haywood, F.F. 112930 8436, 222000 8436, 870092 8436

Head, C.R. 010000 9780, 111210 9780, 122100 9780, 717000 9780, 810000 9780

Hebert, M.J. 122110 9991, 329000 9991, 711100 9991, 793000 9991, 794000 9991, 810000 9991

Hecht, G. 223000 6403, 719A00 6403

Hecker, R. 112120 9592, 719B00 9592

Hedrick, C.L. 010000 8943, 111210 8943, 717000 . 8 9 4 3 * \

Hegedus, F. 210000 8621, 422110 8621, 810000 8621, 870041 8621

448-

Hehn, G. 010000 8854, 020000 6420,122100 8854, 122110 6420, 122200 8854, 210000 6393 8588, 220000 8854, 521130 8588, 713000 8588, 719A00 6393 8588, 719D00 6398, 760000 8854 9285, 793000 8854, 845000 8854 9285, 861000 8588, 870006 6398 8854, 870008 8854

Heijboer, R.J. 122110 6676, 122310 6676, 312000 6676, 521130 6676, 810000 6676

Heimbach, C.R. 111110 9328, 112110 9328, 420000 9328, 421200 9328, 511120 9328, 512120 5328, 810000 9328

Heinrich, R.R. 010000 6668,111220 9490, 122100 9490, 122310 8254 9400, 210000 8957, 421140 6668, 422110 9400, 430000 8254, 521230 9490, 717000 6668 9490, 794000 8254, 810000 8957 9490

Heinselmann, M. 220000 8995, 521210 8995, 522210 8995

Helmbold, M. 112120 9592, 719B00 9592

Helmick, H.H. 020000 8592, 421110 8592, 713000 8592

Hemmendinger, A. 111210 8428, 422110 8428, 511120 8428, 870003 8428, 881000 8428

Hemphill, R.T. , 112930 8644, 719A00 8644

Henderson, D.L. 521130 9544, 717100 9544, 793000 9544, 810000 9544, 870094 9544

Hendricks, J.S. 511110 9797, 861000 9797

Hendrickson, H.R. 010000 8650, 122310 8650, 312000 8650

Hengclbroek, R.J. 321000 9895

Henning, C.D. 010000 7036, 210000 7036, 717000 7036

Henninger, R.J. 310000 9749,510000 9749,511110 9749,710000 6935, 717000 6935, 793000 6935, 853100 6935

Henry, H.F. 421140 9253

Hep, J. 112930 8821, 223000 8821, 719A00 8821, 810000 8821

Hermann, O.W. 112120 8678, 552110 8678, 719AOO 8678, 861000 8678

i> i •

Herring, S. 521130 8566, 717000 8566, 810000 8566

Herrnberger, V. 020000 6420, 122110 6420, 312000 6377

Hetrick, D.M. 111220 8808, 122100 8808, 222000 8784, 810000 8808

Hilditch, R.J. 210000 8623, 422110 8623, 810000 8623

Hill, G.A. 222000 8121, 223000 8121

Hill, G.S. 220000 8734, 222000 8734,793000 8734, 870090 8734, 870094 8734

Hill, M.D. 220000 6857, 222000 6857, 230000 6857

Hill, N.W. 422140 8392, 430000 8392, 794000 8392

Hill, T.R. 32A000 6448

Hiratsuka, A. 853400 9702

1 Hirayama, H. 020000 9839, 512110 6869, 512210

6869, 521220 8020, 750000° 8020, 820000 6869, 861000 6869, 870013 6869, 870082 6869 <7

Hock, R. 710000 8805,719A00 8805,721100 8805, 810000 8805

Hoffman, F.O. 010000 9140, 112930 9027, 220000 9027 9112,222000 9027 9112 9140

Hoffman, F.O. (Ch.) 010000 6666, 112930 6666

Hoffman, T:J. 122110 9093, 210000 8248, 312000 6645, 32AOOO 8248 9093, 329000 6313 6434 6645 8475 8750, 717000 8248, 794000 9093, 870079 9093

o 449

Hofmann, I. 410000 9367, 420000 9367, 511120 Homann, S.G. 423250 6707 9367

Hogan, B.T. 020000 9528, 113100 9528, 220000 9528, 845000 9528

Hogel, J . 1127108911,122200 8911,210000 9455, 421140 8911, 511120 9455, 719COO 6253, 810000 8911, 861000 9455

Hoh, J.C. 210000 9825, 717000 9825,870007 9825

Hohlfeld, K. 020000 9038 9199, 220000 9199, 430000 9199

Holdren, J.P. 010000 6704, 717100 6704

Honig, A. 853100 6471

Hood, J.T. 712000 8382, 842000 8382, 870098 8382

Hoogenboom, J.E. 329000 8921

Hooker, C.D. 020000 9224 9528, 113100 9528, 220000 9224 9528, 410000 9047, 430000 9224, 770000 9047, 845000 9528

« o

Hopkins, G.R. 111210 8951, 210000 8951, 717000 8951, 717100 6231, 810000 6231, 870006 8951, 870014 8951, 870090 6231, 870092 6231

Hollabaugh, D. 511120 6578, 820000 6578

Holland, J.A. 020000 9528, 113100 9528, 220000 9528, 845000 9528

Hopkins, W.C. 719A00 8801,721100 8801,794000 8801, 810000 8801

Hormann, S.G. 423250 9055

Holland. J.P. 020000 9224, 220000 9224, 430000 9224

Holland, L. 511120 6867, 820000 6867

Hollandsworth, C.E. 121100 6744, 210000 6744, 870019 6744

Holm, J.S. 010000 6343, 112120 6343, 532000 6343

Holman, M. 410000 8910, 421130 8910, 430000 8910, 719C00 6253

Holmes, D.K. 210000 8248, 32A000 8248, 717000 8248

Holmes, J.J. 010000 9486, 111210 9486, 111220 9486, 210000 9486, 717000 9486, 810000 9486

Holt, J.G. 020000 9212,22;0000 9212,430000 9212

Holt, P.D. 111110 8380, 220000 9289, 511120 0 9289, 820000 9289

Horowitz, Y.S. 310000 6647, 329000 6432 8021 8997, 423135 8832, 423250 8833

Houston, D.H. 112930 6940, 610000 69(40 o

Hovingh, J . 111210 8951, 210000 8465 8951, 521130 7025, 717000 7025 8465 8951, 810000 8465, 861000 8465, 870003 8465, 870006 7025 8951, 870014 8951

Howard, J.E. 329000 9127, 717100 9127, 810000 9127

Howerton, R. 122100 6659, 870090 6659

Howerton, R.J. 010000 6634,111110 6590,111210 9252, 112400 9252, 112500 9252, 121100 6590 6634 6774 7048 8906, 122100 6571 8222 8681 8906, 122110 7048 8682, 122200 8222 8681 8812, 122310 9252, 511110 9229, 521130 9229, 793000 9229,810000 8222 8681 8682 8812 8906 9229, 870092 6590, 870094 6590, 887000 6571

Hozumi, K. 521220 8020, 750000 8020

Hotter, G.D. 112120 6983 Hozumi, Y. 853400 9702

o

450 CO

Hsu, P. 423250 6566, 853100 6566 Igarasi, S. 122100 9837, 870096 9837

Hubbell, J.H. 000000 7051, 010000 7051, 020000 9034, 122200 6936, 122210 7052, 220000 9034, 430000 9034, 810000 6936 7052

Hughes, R.P. 312000 9633, 325000 9633

Humphries, L.J. 020000 9211, 220000 9211, 430000 9211

Hungerford, H.E. 632110 6442, 632300 6442

Hunter, T.O. 121100 8129 8130, 121200 8130, 210000 6767 6770 8129, 531000 8130, 532000 8130, 717000 6767 6770 8129 8130, 810000 8129 8130, 870006 6767, 870029 6770, 870042 6767

Huszar, L. 512110 8197, 512210 8197, 632110 8197,830000 8197 "

Hutchingson, J.M.R. 020000 9200, 220000 9200, 430000 9200

Huxford, T.J. 111210 7089, 32AOOO 8563, 521130 8563, 717000 7089 8563, 810000 8563

O Hwang, R.N. 32D000 9011, 551110 9011

Hyodo, T. 010000 7068,020000 6462 9839,310000 7068, 511120 9142, 512110 9142, 522110 7068, 522210 7068, 551120 6462, 610000 7068, 810000 7068, 861000 6462, 870006 9142, 870011 6462

IAEA 010000 10057 6501 6889 8494 9008 9009 9010 9569, 121100 6501 8494 9008 9009 9010 9569, 122100 10057 6889, 310000 9008 9009 9010, 810000 6501 6889 8494 9569, 887000 10057

ICRU 010000 8112, 410000 8112, 423110 8112, 423120 8112, 423130 8112, 423135 8112, 423140 8112, 511120 8112

Ide, T. 111210 85C64 8727, 329000 8564 8727, 531000 8564, 532000 8564, 717000 7009 8564 8727, 721100 7009, 794000 7009, 810000 7009 8727

Iida, H. 111210 8564, 329000 8564, 521130 9840, 531000 8564, 532000 8564, 717000 7009 8564

'fe 9840, 721100 7009, 794000 7009, 810000 7009 9840

lijima, S. 010000 8276, 122310 8276, 810000 8276

llie, P. 421140 6844

Imamura, Y. 717000 6537, 793000 6537

Ing, H. 111110 9121, 111210 9121, 511110 9288, 870082 9288

Ingeneri, S.M. 223000 6414, 719A00 6414 rs V

Ingersoll, D.T. 122310 6463, 312000 8662, 32A000 8662, 430000 6341 6463, 511110 86&2, 551110 9110, 552210 9110, 719B00 9110, 793000 8662, 794000 6463 8662, 810000 9110, 870041 6463 8662, 870098 6463

Inoue, S. „ 329000 9547, 554110 9547 vs.' i) Inoue, Y. 230000 8531

Inous, T. 713000 6397, 721200 6397 O O

Iotti, R.C. 111110 8798, 223000 8798, 329000 8798, 620000 8798, 719AOO 8798,721100 8798, 721200 8798, 722100 8798

Isaacs, H. 010000 8945,111210 8945, 717000 8945

Isayev, N.V. ' 122110 7100, 511110 7100, 810000 7100 •<

Ise, T. 551120 6464, 718000 6387 6464, 721100 6387, 721200 6464, 731300 6464

Ishiguro, Y. 310000 8146

Ishimi, K. 853400 9702 (i °

Issler, L. 210000 6393, 719A00.6393

451-

r It oh, S. 521230 8953, 870003 8953, 870006"89^3"-^Jv^asob, P. 223000 8927, 719A00 8927

Iyengar, P.K. 010000 7055, 121100 T O S M l f r t y g ^ j y ^ J.D. 122310 6570, 424000 9531, 711100 7055, 810000 70'55 , ": ' ' " / ^ P ^ , 9531, 870092;6570"-'

° * *

Jacobs, R. 423210 9041,4233009048,430000 T. 710000 9195, 750000 9195 9048 0 - ^ ^ '

c X ^ Jain, V.K. 010000 9568, 020000 9568, 220000

9568, 423250 7081 7082 ;> ' O '' "

James, C.D. 121100 6589, 122100:6589, 123000« 6589, 870092 6589

James, M.F. 010000 8844, 112710 8844, 122200 8844,810000 8844 n ;J

James, R.A. 223000 6401, 719C00 6401

Jansky, B. -713000 6394, 721200 6394, 870011 6394

Janssen, A.J. 112120 6674, 122100 6674, 122110 6676, 122310 6676 8872, 312000 6676, 521130 6676, 713000 6674 8872, 810000 6676

" •

Janssens, A. 423210 9041, 423300 9048, 430000 9041 9048

Jarina, V.P. 010000 8590, 020000 8590, 421130 8625,421140 8590 8625, 511120 8625 °

O Jarka, R. 220000 8904,329000 8904,793000 8904,

845000 8904

Jenkins, T.M. 750000 8811 9062, 810000 8811, 853100 9062 ,

Jennings, W.A. „ 020000 9203, 220000 9203, 430000 9203 "

Jenquin, U.P. ,122310 9448, 521130 7022 9448, 717000 7022, 719A00 9448, 793000 9448,

t 794000 9448, 810000 7022, 861000 9448, 870090 7022, 870092 7022, 870094 9448 0

Jensen, A.S. 010000 8849, 123000 8849 -

Jermann, M. 020000 6799, 511120 6799, 861000 6799 ^

Jiang, S.H. 112400 8881, 112500 8881, 421200 8881, 512210 6873, 512220 6873, 522230 8881, 861000 6873 8881, 870098 6873 8881

Johansson, K.-A. 420000 9050, 423210 9050

John, K. 632120 7076, 810000 7076

o

Johnson, A.B.,Jr. 870022 9965

210000 9965, l717000 9965,

Jarrett, R.D. 020000 9039, 220000 9039, 423210 9039, 430000 9039

Johnson, A.W. 210000 9069, 521130 9069, 717000 9069, 810000 9069, 861000 9069

Jarvis, O.N. 010000 8869 893^,9783,111210 8932, 121100 8932, 122100 8869, 210000 8932, 521130 8932,'717000 8869 8932 9783, 810000 8869 8932 9783

Jary^ J. 122100 9265, 122310 9265, 870094 9265

Jassby, D.L. 111210 8810, 717000 8810, 717100 9191 9937, 7930.00 9191, 794000 9191, 810000 9191 9937

Johnson, D.L. 010000 8585, 111220 9489, 210000 8585 9489, 421140 8585, 430000 8585, 713000 8111 8585, 717000 8585 9489, 719A00 8585, 719B00 8585, 810000 8585, 870008 8111,

( 870096 8111

..Johnson, L.A. 223000 8692 O

Johnson, L.O. 111110 9122, 421110 9122, 430000 9122, 713000^9122

452

o

Johnson, M.E. 329000 6523

Johnson, M.M. 329000 6523

Kammash, T. 32A100 6765, 717000 6765

t;:" *ef , Kamphoase, J.L. 63>2110 8249

Johnson, R.H. 430000 9729,794000 9729 « ^ Kanda. K) 416000 6833 9737,421160 6833,540000 " „ " ' 6833»

Johnson, W.R. 112120 6469 6904, 532000 6469 6904, 719A00 6469 6904

If

Joneja, O.P. 421110 7087

Jones, J.A. 112930 8507, 220000 8507 9525, ,, • . 222000 9525, 223000 8507, 713000 8507

U'

Jones, R.H. 210000 9965, 717000 9965, 870022 " 9965

Jones, T.D. 220000 8045

Kanda, Y. 122100 6686, 870092 6686, 870094 6686

Kantrowitz, F. 010000 9388, 711100 9388, 717100 9388 ^ "V

to Kappler, F.W. 717000 6877, 870003 6877

Kami, Y. 122310 8665,312000 8665,32A000 8665, 521130 8665 , O

v Kasai, S. 020000 6462, 551110 9632, 551120 6462

9632, 861000 6462 9632, 870011 6462

Jonzen, M. 717100 6231,810000 6231,870090 Kase, K.R. 000000 9958 6231,870092 6231

Jow, H.N. 112930 8048, 222000 8048 -Kaser, J.D. 230000 8036, 717000 8036/810000

8036 (;)

Julius, H.W. 020000 9207, 220000 9207, 430000 Kassawara, R.P. 32AOOO 8802, 551110 8802, 9207 710000 8802, 719A00 8802, 721100 8802,

810000 8802 " =

Jung, J . 111210 9421,620000 9421,710000 9421, 0

717000 8253 9421, 721100 8253,-810000 9421 Kastenberg, W.E. 222000 8090, 717000 8090

Jung, J.C. 010000 7030, 531000 7030, 532000 7030, 717000 7030, 810000 7030

Jungerman, J.A. 111220 8994

Kathuria, S.P. 423250 7081 7082 0

Kato, K. 230000 8531

Katoh, A. 020000 9035, 423210 9035

' " l ^ o o J S X S 8 5 0 2 1 5 1 2 2 2 0 —

Kahele, T.J. 230000 8036, 717000 8036, 810000 8036 " ^

o Kadotani, H. 329000 6438, 721100 6438

Kam, F.B.K. 010000 8596, 421140 6667, 430000 6667 8596 8737, 794000 8737, 810000 6667

'Kamelander, G. 310000 9732, 540000 9732

Katz, R. 423240 7077

Kaul, D. 220000 8904 8905, 329000 8904, 793000 8904 8905, 794000 8905, 845000 8904 8905 u

Kavenoky, A. ^ 310000 6574, 330000 9762, 422110 8250, 551110 9762

e

Kawai, M. 122100 6686, 329000 6438, 721100 6438,870092 6686,870094 6686'

cv -. <

« 453

Kawakita, T. 551120 6464, 718000 6387 6464, 721100 6387, 721200 6464, 731300 6464

Kazi, A.H. 111110 9328, 112110 9328, 210000 8624, 220000 8624, 420000 9328, 421200 9328, 511120 9328, 512120 9328, 713000 8624, 810000 9328

Kazimi, M.S. 112930 8025, 220000 8025, 222000 8025, 717000 8025, 810000 8025

Kearney, D. 717000 7017, 810000 7017

Kearny, C.H. 220000 8513, 410000 8513, 423210 8513

Kee, C.W. 112930 7091, 220000 7091, 222000 7091, 713000 7091, 719A00 7091, 719B00 7091

Kcenait, F. 223000 6400, 719C00 6400 ''

Keller, J.H. 223000 6477, 719A00 6477

Kellogg, L.S. 010000 6815, 020000 6513, 122310 6815, 511120 6513 6815, 810000 6815, 870092 6815,870098 6815

Kelly, G.N. 020000 6938, 112930 8507 9375, 220000 8507 9375, 222000 6938, 223000 6938 8507, 713000 8507 9375, 845000 9375

Kelly, J.L. 010000 6213, 112710 6213, 112760 6213, 112930 6213, 521130 8946 9869, 522130 8946 9869, 713000 6213, 717100 8946 9869, 793000 8946 9869, 810000 8946, 870092 6213, 870094 6213

Kemshall, C.D. 111110 8380

Kennerley, R.J. 122310 8254, 430000 8254, 794000 8254

Keresziuri, A. 324000 8500, 326000 8500, 327000 8500, 511110 8500, 521130 8500, 820000 8500, 861000 8500, 870013 8500, 870092 8500

Kern,. E. a ! 711100 10062 10063

Kerr, G.D. 010000 8212, 220000 8212, 521120 8212, 522120 8212

Kerr, H.T. 325000 8603, 719A00 8603, 793000 8603, 810000 8603

Key, B.N. 410000 8414, 421200 8414, 424000 8414

Keyworth, G.A. 010000 8846,122100 8846,870090 8846, 870092 8846, 870094 8846

Khamis, H. 551120 8866, 719B00 8866, 810000 8866

Kharizomenov, Yu.V. 421140 7112, 719A00 7112, 721100 7112, 721200 7112, 853800 7112, 8 IL000 7112

Khmylev, A.N. 321000 7102, 511110 7102, 551110 7102, 820000 7102, 861000 7102

Khokhlov, V.F. 112500 7114, 122110 7100,423250 7114, 511110 7100 7114, 512210 7114, 512220 7114, 810000 7100, 853800 7114, 861000 7114

Kidman, R.B. 020000 9107, 111110 9107, 122110 6454 6758 6802 8023, 122310 8023, 511110 6758 8023, 521130 9107, 551110 8023, 713000 8023 9107, 793000 8023 9107, 794000 6758 8023 9107, 810000 6758

Kikuchi, M. 112760 6978 8915, 719A00 6978 8915

Kikuchi, Y. 122100 6686, 870092 6686, 870094 6686

Killough, G.G. 112760 9376, 220000 8213 9376 9928, 610000 9376, 711100 9376, 845000 8213^ 9376 9928 "

Kim, J. 111220 6533 9002 9188, 113100 6533 9002, 220000 6533, 511120 9188, 632300 6533, 717000 6533 9002 9188

Kim, S . -Y . 32D000 9726

Kimlinger, J.R. 122110 8682, 810000 8682 ft

454-

Kimura, I. 010000 6842,020000 6842,421140 6842 8632, 511120 6842,713000 8632,719A00 8632, 870092 8632

Kinch, J.W. 329000 9562, 551110 9563, 552110 9563, 731100 9561 9562 9563, 793000 9561 9562 9563, 810000 9563

King, W.C. 010000 9617, 230000 9617

Kinjo, H. 631000 6443,713000 6443,721100 6443

Kinsey, R. (Comp.) 020000 9827, 122100 9827, 122200 9827, 810000 9827

Kirbiyik, M. 010000 6213, 112710 6213, 112760 6213,112930 6213, 713000 6213, 870092 6213, 870094 6213

Kirthi, K.N. 421130 7086, 421200 7086, 430000 o 7086

w i Kisynski, J. 310000 8099

P

Kitamura, M. 223000 8476, 631000 8476, 719A00 8476

u

Klabunde, C.E. 010000 8876, 210000 8876, 717000 8876, 810000 8876

Klein, A.C. 521130 8135, 522130 8135, 532000 8135, 717000 6772 8135, 793000 6772, 810000 6772

Klimanov, V.A. 329000 7109,521110 6473,521210 6473,722100 7109,810000 7109

Klippel, H.Th. 122110 6676, 122310 6676, 312000 6676, 521130 6676, 810000 6676

Klotz, R.J. 32A000 8802, 551110 8802, 710000 8802, 719A00 8802, 721100 8802, 810000 8802

Kluge, H. 220000 9382, 420000 9382,430000 9382

Knecht, R.L. 210000 6392, 713000 6392

Kneff, D.W. 121100 9491, 122100 9491, 210000 9491, 717000 9491, 810000 9491

Knight, J.R. 121100 6697, ,122110 7129, 122210 7129, 220000 9532, 511110 7129, 512210 7129, 551110 9532, 552110 9532, 552210 9532, 610000 6697, 632200 6697, 793000 9532, 794000 6697, 810000 6697 7129, 830000 7129, 845000 9532, 853100 7129

Knipe, A.D. 423250 8616, 532000 8616, 713000 8616

Knitter, H.H. 010000 6813, 11,1110 6813, 870092 6813, 870098 6813

Knoll, G.F. 010000 9003, 420000,9003

Knoll, R.W. 424000 9531,711100 9531

Koban, J . 210000 6393, 719AOO 6393

Kobayashi, K. 010000 6842, 020000 6842, 312000 9305,32A000 9305, 325000 9305,410000 6833, 421140 6842 8632, 421160 6833, 511120 6842, 540000 6833, 551110 9305, 713000 8632, 719A00 8632, 870092 8632

Koblinger, L. 220000 10001,311000 10001,329000 10001 8046, 731200 8046, 845000 10001

Koch, P. 122110 9700,330000 9700

Kochanov, V.A. 329000 7109,722100 7109,810000 7109

Kocher, D.C. " 020000 9042, 112710 8783 9042, 112760 8785, 112930 8372, 220000 8372 8783 8785 9042 9927, 222000 8372 9738 9927, 223000 8783, 631000 9738, 711100 8783, 731200 8372 9738, 810000 8785, 845000 8783 8785 ;

Klusek, C. 430000 8543 Kocicj, A. 329000 6234,511110 6234,810000 6234

Kluson, J. 522110 8829,861000 8829,870006 Koizumi, C.J. 010000 8413,410000 8413,421200 8829, 870013 8829, 870050 8829, 870082 8829 © 8413, 424000 8413

455-

Koleganov, Ju.F. 713000 6421

Kolesov, V.E. 010000 8843, 020000 6615, 122100 6615, 122310 8843, 713000 8843, 887000 8843

Kolevatov, Yu.J. 512220 6472, 820000 6472, 861000 6472, 870082 6472

Komoto, T. 122310 8859, 511110 6468, 511120 6875 8859^ 512210 6875, 512220 8859, 717000 8859, 820000 6468, 830000 6875, 853100 6468, 861000 6468, 870029 8859, 870041 8859, 870090 8859, 870092 8859

komoto, T.T. 111210 9252, 112400 9252, 112500 9252, 122310 9252

Kon'shin, V.A. 122100 8968, 870092 8968

Kondo, I. 421140 8611,430000 8611,870047 8611

Konovalov, N.V. 321000 7101, 323000 7101, 511110 7101, 861000 7101, 870006 7101

Konzek, G.J. 020000 8198, 719A00 8198, 870092 8198,870094 8198

Koponen, B.L. 010000 9231 9232, 020000 9231 9232, 410000 9231 9232, 511120 9231 9232, 551120 9231 9232

Kopp, L.I.„, 020000 9757

Korenevskiy, V.V. 210000 7125, 853100 7125

Kosako, T. 111110 6832, 410000 6832, 421130 6832, 421140 6832, 511120 6832

Kostoff, R.N. 010000 8767, 713000 8767, 717100 8767, 717500 8767

' U

Kothari, L.S. 325000 8688, 540000 7073 8688, 820000 7073 8688, 870001 7073, 870006 7073, 882000 8688

Kotov, V.V. 122310 8503, 717100 8503, 870092 8503

Kottwitz, D.A. 122310 9448,521130 9448,719A00 9448, 793000 9448, 794000 9448, 861000 9448, 870094 9448

Kouts, H. 010000 8945,111210 8945, 717000 8945

Kovalenko, V.V. 421130 7110, 421140 7110, 521230 7110, 710000 7110, 719A00 7110

Kovarik, K. 719C00 6253

Koyama, K. 020000 6462, 551110 9632, 551120 6462 6464 9632, 718000 6387 6464, 721100 6387, 721200 6464, 731300 6464, 861000 6462 9632, 870011 6462

Krakowski, R.A. 32A000 9310, 521130 9310, 522130 9310, 717000 8894 9310, 810000 8894 '' 9310

Krause, M.O. 122200 6859, 810000 6859

Krebs, J. 112120 8871, 122100 8871, 122200 8871

Krieg, B. 122100 9705, 810000 9705

Krivtsov, A.S. 010000 8843, 122110 8114, 122310 8843, 713000 8114 8843, 810000 8114, 887000 8843

Krumbein, A. 111210 8867, 122310 8867, 521130 8867, 717100 8867, 810000 8867, 870092 8867

Krumbein, A.D. 717100 9736

Ksenofontov, A.I. 329000 7108, 512110 7108, 861000 7108

Kufner, K. 32A000 9746, 551110 6979 9746, 713000 6979 9746

Kuga, H. 760000 9822

Kujawski, E. 122110 8252

a Kukhtevich, V.I. 010000 8257, 521120 8257,

522120 8257, 731200 8257

456-

Kukuchi, M. 223000 8476, 631000 8476, 719AC0 8476

Kulagin, V.A. 421150 7120, 511120 7120, 861000 7120, 870013 7120, 870022 7120

Kulakovsky, M.Ja. 713000 6421 T;

Kulcinski, G.L. 010000 6768 9386, 111210 8043 8960, 121100 6709 8129 8130, 121200 8130, 210000 6709 6767 6768 6770 8043 8129 8133 9386, 329000 9127, 521130 9542, 522130 9542, ^ 531000 8130, 532000 8130, 713000 6709, 717000 6709 6767 6768 6770 7003 8043 8129 8130 8133 8960 9386 9542, 717100 9127 9866, 810000 6768 7003 8043 8129 8130 8960 9127 9386 9542 9866, 861000 6709, 862000 8133, 870006 6767, 870029 6770, 870042 6767

Kumar, A. 122110 7061,870090 7061,870092 7061

Kurachenko, Yu.A. 512220 6472, 820000 6472, 861000 6472, 870082 6472

Kushner, M. 010000 8945, 111210 8945, 717000 8945

Kusler, L.E. 010000 8264, 223000 8264

Kusters, H. 010000 8850 9307, 122100 8850, 223000 9307, 230000 9307, 711100 8850, 712000 8850, 810000 8850 9307

Kutateladze, K.S. 740000 7126, 853200 7126, 853800 7126

Lafond, D. 122100 9264, 870095 9264

Lagrange, Ch. 122100 9265, 122310 9265, 870094 9265

Lahti, G.P. 010000 8791, 223000 8791, 719A00 8791, 721100 8791, 722100 8791

Lalet, A. 112760 6411, 223000 6411, 719A00 6411

Lalovic, M. 010000 8850, 122100 8850, 711100 8850, 712000 8850, 810000 8850

Lam-Hime, M. 330000 9762, 551110 9762

Lamaze, G.P. 020000 8247, 410000 8247, 421160 8247

Lnmmer, G. 010000 6817 8268,112120 6817 8268, a 713000 6817, 870092 8268, 870094 8268

Lammer, M. 010000 6817, 112120 6817, 713000 6817

Landers, N.F. 010000 9992, 122110 9992, 312000 6645, 329000 6645 9992, 712000 9992

Langlet, J. 112120 8871, 122100 8871, 122200 8871

Lanzl, L.H. 020000 9208, 220000 9208, 430000 9208

Larina, A.F. 122100 8113, 870001 8113

Kuznetsov, V.G. 620000 7107 <3

Kynaston, R.L. 112710 8973, 222000 8973, 223000 8973, 719A00 8973

Kypreos, S. 329000 6396, 719B00 6396

LaBauve, R.J. 112120 8206 9979, 112710 9441, 122100 9441, 122110 6802 8115, 122210 9979, 532000 8206, 610000 9441, 717000 9441, 793000 8115 9441 9979, 810000 8115 9441 9979, 870090 8206, 870092 8206, 870094 8206

LaRiviere, P.D. 513120 8983,750000 8983,853100 8983

Larkins, F.P. 121200 6775, 613000 6775

Larsen, E. 329000 9127,717100 9127,810000 9127

222000 8251, 717000 8251, 869999

o 312000 r "H. 32A000 9066, 325000

Larsen, E.M. "" 8251

Larsen, E.W. - 9633

Q

457

Larson, D.C. 111220 8808, 122100 10076 8808, 810000 8808, 870011 10076

Larson, H.V. 020000 6893, 220000 6893, 430000 6893

Lathrop, K.D. 010000 6800, 32A000 6800, 325000 6800

Laughlin, J.S. 020000 9212, 220000 9212, 430000 9212

Lauridsen, K. 222000 6320, 719A00 6320 •••>

Lazareth, O. 010000 8945, 111210 8945, 717000 8945

Lazareth, O.W. 531000 6579

Lederer, C.M. 112710 9257, 610000 9257

Lee, A.Y. 521130 9869,522130 9869,717100 9869, 793000 9869 °

0 Lee, D.M. 424000 9371, 719A00 9371

Lee, I.S. 112930 8048, 222000 8048

Lee, J.D. 010000 7021 8942, 111210 8908 8942, 329000 8908, 717000 7021 8908 8942, 717100 6865 8908, 810000 7021 8908

Lee, J.Y. 112710 8781,112760 8781,112930 8781, 222000 8781, 719A00 8781

Lee, R.R. 010000 8791, 223000 8791, 719A00 8791,721100 8791,722100 8791

Leenders, L. 210000 8618, 422110 8618, 423250 8618, 532000 8618, 713000 8618, 810000 8618

Lees, E.W. 010000 8853,111220 8853, 870095 8853

Lefevre, H.W. 111220 8752

Leggett, R.W. 220000 9927, 222000 9927

Leitz, G. 210000 6393, 719AOO 6393

Lekishvili, R.A. 740000 7126, 853200 7126,853800

7126

Lell, R.M. 010000 9987, 329000 9987

Lemanska, M. 717100 9736

Lemley, J.R. 424000 9271, 870094 9271 Leonard, B.R. 521130 8373, 717000 8373, 810000

8373

Leonard, B.R.,Jr. 010000 9935, 122100 6587, 210000 9965, 521130 7022, 717000 7022 9965, 717100 9868 9935, 810000 7022, 870022 9965, 870090 7022, 870092 7022

Lesiecki, H. 220000 9382, 420000 9382, 430000 9382

Levine, P. 312000 6450, 521130 7035, 522130 7035, 620000 6450, 717000 6450, 717100 7035, 793000 7035, 810000 7035, 883000 6450

Levitt, L. 020000 6293,329000 6293,719A00 6293

Lewallen, M.A. 632200 6625, 711100 6626

Lewis, E.E. 326000 9548

Lewis, R. 521130 9542, 522130 9542,717000 9542, 810000 9542

Lgarasi, S.I. 122100 6235, 870095 6235

Lichtenstein, H. 010000 9994, 020000 9997, 112120 6903, 329000 8886 9994 9997, 521130 9997, 532000 6903, 719A00 6903, 810000 9997

Liddell, P.J. 230000 9613 0

Liden, K. 222000 6470, 719AOO 6470

Lefve^t, T. 511110 8199, 512110 8199, 853100 8199

Lidsky, L.M. 521130 8566, 717000 8566, 810000 8566

458-

Liesem, H. 410000 9052, 750000 9052, 760000 Litzow, W. 551120 8866, 719B00 8866, 810000 9052 8866

Lillie, R.A. 112760 9114, 210000 8736, 312000 9929, 32A000 9929, 421000 6948, 510000 9856, 521130 8736, 522130 8736, 531000 8214, 532000 8214, 551110 6948 8214 8736, 552110 8736, 552120 8214, 552220 8736, 717000 8214 9114 9115, 793000 9856, 810000 8214 9856, 830000 8736, 851000 8736, 853900 8736, 861000 6948

Lindberg, L. 010000 8269, 112120 8269, 222000 8269, 870092 8269, 870094 8269

Liu, K.C. 32A000 8563,521130 8563,717000 8563, 810000 8563

Livesay, R.B. 210000 6609, 551110 6609, 719A00 6609, 810000 6609, 861000 6609

Lloret, R. 010000 6849,210000 6849 8620,421140 6849, 422110 8620, 810000 8620, 870041 8620

r<

Lloyd, D.C. 010000 8780, 220000 8780

Lindborg, L. 420000 9050, 423210 9050

Lindstrom, D.G. 329000 8687

Lineberry, M.J. 010000 8191, 122310 8191 8651, 521130 8651, 810000 8651, 870090 8191, 870092 8191 <>

Loevinger, R. 020000 9206, 220000 9206, 430000 9206

Logan, B.G. 010000 8942,, 111210 8942, 717000 8942 U

Lokan, K.H. 51112029060, 853500 9060

Lingappan, K.G. 223000 6402, 719A00 6402

Linsley, G.S. 220000 9525 9924,222000 9525 9924

Liou, H.I. 511120 8916, 861000 8916

Lippincott, E.P. 010000 6812 6815, 020000 6513, 122310 6812 6815 8659, 210000 8659, 421140 8659, 430000 6812 8659, 511120 6513 6815, 719X00 8659, 810000 6815, 861000 8659, 870092 6815, 870098 6815

Liskien, H. 010000 9790, 111210 8999, 122100 8148 9790, 717000 9790, 810000 9790, 882000 8148

Listengarten, M.A. - 112710 8044, 610000 8044

Littig, G.A:' 112120 6469, 532000 6469, 719A00 6469

Little, C.A. 220000 9112 9611, 222000 9112 9611

Littlejohn, G.J. 220000 6856, 423135 6856, 521210 6856"

Lokken, R.O. 230000 8216, 853100 8216

Lorenz, A. (Comp.) 010000 68,51, 122200 6851, 810000 6851

Lorenz, R.A. 112120 6858 9467, 112730 10072 6858,112930 10072 9467,532000 6858,719A00 10072^6858 9467, 870092 6858

Love, T.A. 112120 6696 6941 7046 8030 8031 9450 9819, 221000 6696, 421200 7046, 430000 6696 7046, 532000 6696, 610000 8030 8031., 794000 6696, 870092 7046 9819, 870094 6696 8031 9450

Lovell, E. 521130 9542,522130 9542,717000 9542, 810000 9542

Lowenthal, G.C. 210000 8623, 422110 8623, 810000i,8623> ,

Loyalka, S.K. 112120 8925 °

Lubell, M.S. 010000 8561 8562,111210 8561 8562, « 717000 8561 8562

459 0

Lubenau, J.O. 010000 6309, 112600 6309, 112710 6309, 230000 6309

Lucier, R.D. 424000 10000, 719A00 10000

Lucius, J.L. 020000 7131 8517, 122100 8032, 122310 6627 6872 7131 8517 8518,312000 6627 7131 8032, 32AOOO 7131 8032 8517 8518, 511110 8032, 512210 8032, 521130 6627 8518, 551110 8517 8518, 552110 8517, 717000 8032 8517 8518, 719A00 6627, 721100 8517, 793000 8517 8518, 794000 8517 8518, 810000 6627 '7131, 830000 8032, 842000 8032, 853100 8032 8517, 861PQ0 8032 8517, 870001 6627, 870008 6627, 870013 6627, 870092 6627, 882000 8032

Luk'yanov, M.A. 421130 7110, 421140 7110, 521230 7110, 710000 7110, 719A00 7110

Lupu, M. 421140 6844

Lurie, N.A. 112120 9503, 112930 6940, 421130 65*17, 430000 6517, 521230 6517, 522230 6517, 610000 6940, 853100 6517, 861000 6517, 870092 9503, 870094 9503

0 Lux, I. 329000 6648 6733 6879 8093 9727

O Luxat, J.C. 112930 9468, 719C00 9468

Ma, I. 020000 9212, 220000 9212, 430000 9212 o

Mac Donald, H.F. 111700 8757, 112940 8757, 223000 8757, 230000 8757

Macdonald, J.L. 329000 6436 8729, 710000 6935, 717000 6436 6935, 793000 6935, 810000 8729, 853100 6935 a „ O

MacFarlane, R.E. 122110 6454 6758 6802 9442, 122210 9442, 511110 6758, 794000 6758 9442, 810000 6758 9442

MacGregor, M.H. „121100 7048, 122100 8222 8681, 122110 7048, 122200 8222 8681, 810000 8222 8681

Macklin, R.L. : 122100 6532, 870090 6532

O I

Madhvanath, U. 220000 6870 8379 8993, 511110 8993, 551110 6870, 552210 6870, 632110 8379, 820000 8993, 842000 8993, 845000 6870, 853100 8993

Madland, D.G. 122100 9267, 870094 9267

Maeck, W.J. 010000 8273,112120 6514 7049^273 8724, 230000 8273, 713000 6514 7049, 870092 8273, 870093 6514, 870094 7049'3273 8724

Maekawa, H. 122310 6734, 422130 7033, 521130 6734, 521230 7033 8953, 717000 6734 7033, 717100 7033, 793000 7033, 861000 6734, 870003 7033 8953, 870006 6734 7033 8953, 870092 6734 7033

Maene, N. 210000 8618, 422110 8618, 423250 8618, 532000 8618, 713000 8618, 810000 8618

o

Maerker, R.E. 551110 (5460 8577, 551200 8577, 713000 6460, 793000 8577, 794000 8577, 861000 8577, 870011 8577

Magiera, E. (> 220000 9290, 760000 9290, 842000 9290, 845000 92S0

Magrini, A. 424000 9145

Magurno, B. 020000 6293, 329000 6293. 719A00 6293

Magurno, B.A. 122100 8629, 210000 8629, 421140 8629, 810000 8629

Maienschein, F.C. 010000 6369, 020000 8709, 551120 8709, 552220 8709, 713000 8709, 810000 8709

P Main, G.C. 020000 9754

Majeski, S. 010000 8945, 111210 8945, 717000 8945

u

Makai, M. > 325000 10136, 551110 10136

Makowitz, H. 010000 8945, 111210 89457531000 6592, 532000 6592, 717000 6592 8945, 870013 6592

Makra, S. 111110 9121, 111210 9121, 329000 7085, 511110 7085, 521110 7085, 810000 7085

Malik, J.S. 121200 8116, 329000 8116, 512110 8116, 610000 8116, 830000 8116

Malinauskas, A.P. 112120 6858 8578 9467,112730 10072 6858, 112930 10072 8578 9467, 532000 6858, 719A00 10072 6858 8578 9467, 870092 6858 "

O K Ma;2i, V. 223000 6402, 719A00 6402

Maniscalco, J.A. 010000 9485, 111210 8860, 210000 9485, 521/-30 7020, 522130 7020, 551110 8860, 717000 7019 7020 9485, 717100 8860, 810000 7019 7020 8860 9485, 870092 8860

Mann, F.E. 122100 9269, 870094 9269, 870095 9269

Mann, F.M. 111220 9489 9493, 122100 8498, 123000 9587, 210000 9489 9493, 717000 9489 9493, 810000 9493, 870090 8498, 870095 8498

o "

Mann, W.B. 000000 10040, 020000 9043, 112710 9043, 420000 10040

Mannhart, W- 122310 8553 8658, 210000 8658, 421140 6839 8658, 422110 8553, 430000 8658, 511120 6839, 521130 8658, 810000 8658, 870098 6839 8553 8658

Manning, G. 111220 8863, 410000 8863

Mansur, L.K. 121100 8888, 210000 8087 8888, 810000 8888

d) Mapes, J.R. 010000 6309, 112600 6309, 112710

6309, 230000 6309

Marable, J .H. 020000 7131, 122110 8975, 122310 68J2 7131 8193 8652 8661 8668 8975, 123000 8668, 210000 8661, 312000 7131 8652 8661

« 9551, 32A000 7131 8652 8661, 521130 8193 8652 8661, 713000 8193 8652, 794000 8193 8652 8661, 810000 7131 8661 8975

Marafie, A.M. 430000 8545

Marik, J . 719C00 6253

Markin, J.T. 711100 10062 10063 10064

Markovskii, D.V. 010000 8861 9786,111210 9786, 122100 9786, 122310 8503 8861, 521230 8861, 717100 8503 8861 9786, 810000 8861 9786, 870092 8503

Marshall, M. 423135 8378, 430000 8378

Marshall, N.H. 020000 9756,,

Martin-Deidier, L. 020000 9273, 112120 8871, 122100 8871, 122200 8871, 870094 9273

Martin, A. 522120 6445,632110 6445

Martin, L.C. 010000 8780, 220000 8780

Martin, M.J. 020000 9042, 112710 9042, 220000 9042

Q

jMartin, W.J. 112120 6944 8455, 210000 6944, 421200 6944, 719B00 6944 8455, 810000 6944

Martiiii, M. 020000 8635, 421140 8635, 511120 \-,6458, 551120 8635, 713000 6458, 810000 8635,

870011 6458 ?

Mas, M. 010000 6849, 210000 6849, 421140 6849

Mas, P. 210000 8608, 421150 8608

Mashkovich, V.P. 000000 7097, 329000 7109, 421200 7115, 512220 6472, 521110 6473, 521210 6473, 522210 7115, 610000 7115, 722100 7109, 810000 7109, 820000 6472 7115, 861000 6472 7115, 870013 7115, 870082 6472 7115

o 0

Maskewitz, B.F. 'OOOOOO 7075, 010000 6415 7075, 223000 6415 <> O

<5> Massoud, E. 423240 3040, 430000 9040

o 461 o

Masulli, F. 421130 9399, 430000 9399

Mathews, D. 122110 9700, 330000 9700

Mathews, M.A. 010000 8413, 410000 8413 8414, 421200 8413 8414, 424000 8413 8414

Matschoss, V. 112120 9593, 112930 9469, 719AOO 9469 9593

Mafsumoto, T. 410000 9737

Matsunobu, H. 122100 6686, 870092 6686; 870094 6686

Matsushima, Y. 223000 8476, 631000 8476, 719A00 8476

Matsuura, S. 112940 9638, 423250 9638

Mattes, M. 010000 8854, 020000 6420, 122100 8854, 122110 6420, 122200 8854, 220000 8854, 760000 8854, 793000 8854, 845000 8854, 870006 8854, 870008 8854

Matthes, W. 121100 10054, 122110 9098, 122310 9098, 123000 10054

Matthews, S.D. , 010000 6322, 329000 6322

Mattsson, L.O. 420000 9050, 423210 9050

Matzke, M. 421140 8631, 810000 8631, 870098 8631

Maximon, L.C. 121200 6937, 810000 6937

Mayer, J.A. 122110 9991" 329000 9991, 711100 9991, 793000 9991, 794000 9991, 810000 9991

Maynard, C.W. 111210 8960,122310 8663,312000 (8663, 32A000 8663, 329000 8228 8231 9127

9760, 521130 8135 8228 8231 8663 9057, 522130 8135, 532000 8135, 551110 7029 8663 8947, 552110 7029 8947, 711100 9760, 717000 6772 7003 7029 8135 8228 8663 8947 8960 9057, 717100 8231 8467° 9057 9127 9760, 721100 7029, 793000 6772 9057, 810000 6772 "003 7029 8228 8231 8467 8663 8947 8960 9057 V \ ? ~ <»

Maynard, Ch.W. 122310 8503, 717100 8503, 870092 8503

McAdoo, J.W. 230000 8033, 551110 8033, 713000 8033, 793000 8033, 794000 8033, 887000 8033

Q McAfee, W.J. 111210 7089, 717000 7089

u 0

McAlees, D.G. 010000 7016, 717000 7016,810000 7016

McCall, R.C. 750000 8811, 810000 8811

McCann, R.A. 521130 8373, 717000 8373, 810000 8373

- l '

McCarville, T. 521130 9542, 522130 9542, 717000 9542, 810000 9542

McCombie, C. 020000 6799, 511120 6799,861000 6799

McConnell, J.W. 112120 6696 6941 7046 8030 8031 9450 9725'9819, 221000 6696, 421200 7046, 430000 6696 7046, 532000 6696, 610000 8030 8031, 794000 6696, 870092 7046 9819, 870094 6696 8031 9450 9725

McCormick, N.J. 010000 9935, 717100 9935

McCoy, H.E. 111210 7089, 717000 7089

McCracken, A.K. 010000 6824 8841,122100 8841, 122310 8841, 421140 6824 8601, 430000 6824 8601, 794000 8601, 810000 6824 8841

McCracken, R.T. 422200 8971, 424000 8971, 719A00 8971, 810000 8971

McDaniel, P.J. 312000 8654 8670, 329000 8654 8670, 430000 8654 8670, 551110 8654, 810000 8654

o McDonald, J.C. 020000 9212, 220000 9212,

430000 9212 O A

McDowell-Boyer, L.M. 112930 9027, 220000 9027, 222000 9027

462-

McElroy, W.N. 010000 6812 6815 8585, 020000 6513, 122310 6812 6815, 210000 8585, 421140 8585, 430000 681-2-^585, 511120 6513 6815, 713000 8585, 717000 8585, 719A00 8585, 719B00 8585, 810000 6815 8585, 870092 6815, 870098 6815

McGill, B.L. (Eds.) 010000 9985, 329000 9985

McGinley, P.H. 111220 8986, 750000 8986

McTaggart, M.H. (Ed.) 111110 6831,410000 6831, 421130 6831, 421140 6831, 511120 6831

Meadows, J. 122100 6659, 870090 6659

Meason, J.L. 421140 8096, 430000 8096, 882000 8096

Medrzychowski, R. 122310 8254, 430000 8254, 794000 8254

McGrath, R.T. 010000 9935, 717100 9935

McGregor, B.J. 521130 6657,551110 6657,810000 6657, 870090 6657, 870092 6657, 870093 6657

Mclsaac, C.V. 112710 8973, 222000 8973, 223000 8973, 719A00 8973

McKay, H.A.C. 010000 8272, 112120 8272, 230000 8272, 870092 8272, 870094 8272

McKinnon, M.A. 32A000 8190, 521130 8190, 717100 8190,810000 8190

McKnight, R. 010000 6661, 122100 6661, 122110 6661, 713000 6661, 810000 6661

McKnight, R.D. 122310 6584 8192, 521130 8192, 713000 6584 8192, 870090 8192, 870092 6584 8192, 870094 6584

McKone, T.E. 222000 8090, 717000 8090

McLaughlin, D.J. 32A000 8802, 551110 8802, 710000 8802, 719A00 8802, 721100 8802, 810000 8802

McLaughlin, W.L. 020000 9201, 220000 9201, 430000 9201

Mehta, S.C. 122200 8828, 423250 8828, 845000 8828

Meier, K.L. 111220 9443, 210000 9443, 717000 9443, 810000 9443

Meier, W.R. 010000 9485, 210000 8463 9485,., 521130 8463, 71700U 8463 9485, 810000 9485, 870003 8463

Meldner, H. 111210 8979, 230000 8691, 717000 8691 8979, 887000 8691 8979 .

Menapace, E. 112120 8871, 122100 8871 9268, 122200 8871,870094 9268

Mendez, A. 410000 9051, 760000 9051

Meneghetti, D. 122210 8004, 326000 8004

Menessier, P. 421140 8605, 422130 8605, 430000 8605, 870092 8605, 870094 8605

Menil, R. 210000 8618, 422110 8618, 423250 8618, 532000 8618, 713000 8618, 810000 8618

Menlove, H.O. 711100 10064

Mense, A.T. 111210 7089,717000 7089

McNaughton, M.W. 111220 8994

McNeany, S.R. 122310 6570,424000 9531, 711100 9531,870092 6570 A

MCracken, A.K. 122310 8674, 312000 8674, 521130 8674, 713000 8674, 719A00 8674,

° 810000 8674, 861000 8674

Menzel, H.G. 111220 9291, 220000 9291, 760000 9291

Meteer, J.W. 112120 6514, 713000 6514, 870093 6514

Q Metghalchi, M. 512110 8095 8920, 632110 8095

8920, 820000 8920, 853100 8095, 870013 8920

463-

Meyer, H.R. 220000 9112, 222000 9112

Meyer, W. 511120 6578, 820000 6578

Meyers, R.E^ 222000 8404, 329000 8404

Michelini, M. 325000 6575

Mihalczo, J.T. 111220 9188, 511120 9188, 717000 9188

Mika, J . 310000 8099

Mikic, B. 521130 9765,522130 9765,717000 9765, 793000 9765, 810000 9765, 870003 9765

Mikic, B.B. 717000 8480 9146, 793000 9146

Miley, G.H. 210000 8433, 717000 7006 8433, 810000 7006, 841000 8433, 842000 8433, 844000 8433

Milgram, M.S. 310000 8094, 330000 8394

Miller, C.W. 010000 9140, 112930 9027, 220000 9027 9112, 222000 9027 9112 9140

Miller, K.M. 421200 6900

Miller, P. 210000 8887, 717000 8887, 861000 8887

Miller, P.C. 112770 6405, 223000 6405, 719C00 6405 ^

Miller, R.L. 717000 8894, 81000'd 8894 0

Miller, W.F.,Jr. 32A000 9066 9744, 32A100 8755, 551110 9744

Miller, W.H. 511120 6578, 820000 6578 e

Miller, W.R.,Jr. 32A100 6242, 514110 6242, 717000 6242

Millsap, D.A. 020000 6834 8636, 111110 6864, 410000 6834 6864, 421140 6834 6864 8636, 511120 6834 8636, 713000 6864 8636, 717000 8356, 770000 6864, 810000 6864 8356 8636

o Ca o

Milosevicj, M. 329000 6234, 511110 6234, 810000 6234

Milton, L.J. 010000 7030, 329000 8965, 531000 7030, 532000 7030, 717000 7030, 810000 7030

Minns, J.L. 112710 8781, 112760 8781, 112930 8781, 222000 8781, 719A00 8781

Minsart, G. 32A000 9746, 551110 9746, 713000 9746

Miodownik, A.P. 210000 9497, 717000 9497, 810000 9497

Miron, C. 421140 6844

Mironov, V.N. 310000 7103, 632200 7103

Misra, B. 620000 9422,710000 9422,717000 9422, 810000 9422

Mitchell, J.B. 111210 6635, 111220 6635, 210000 6635, 717000 6635, 870023 6635, 870029 6635, 870041 6635

Miura, S. 521220 8020, 750000 8020

Miura, T. 020000 9839, 210000 8589, 421140 8589, 551110 8589, 551120 6464, 718000 6387 6464, 721100 6387, 721200 6464, 731300 6464, 810000 8589

Miyajima, M. 521220 8020, 750000 8020

Miyakoshi, J. 551120 6464, 718000 6386 6387 6464, 721100 6386 6387, 721200 6464, 731300

o 6464

Miyasaka, S. 020000 6462, 551110 9632, 551120 6462 6464 9632,^713000 6397, 718000 6386 6387 6464, 721100 6386 6387, 721200 6397

0 6464, 731300 6464, 861000 6462 9632, 870011 6462

Mizuho, M. 210000 8606, 421140 8606, 422130 8606, 870092 8606, 870094 8606

o 464

Mladjenovic, M. 613000 8912 Morisawa, S. 230000 8531

Mocioiu, D. 122110 8770, 521130 8770, 713000 Moriuchi, Y. 020000 9035 9205, 220000 9205, 8770, 810000 8770 423210 9035, 430000 9205

Modolo, J.T. 112800 8215,112720 9185,121200 Morley, F. 020000 6938 9179, 220000 9179, 8215, 329000 8215 9185, 512110 9185, 820000 8215 9185

222000 6938 9179, 223000 6938

Morrison, G.W. 719A00 8120

Morrison, J.E. 010000 9935, 717100 9935

Moioli, P. 5.11120 6458, 713000 6458,870011 6458 MORSE) L . E / 2 2 2 0 0 0 6 9 8 2 2 3 0 0 0 0 6 9 G 2

Moenich, J . 111210 9421, 620000 9421, 710000 9421, 717000 9421, 810000 9421

Moir, R.W. 010000 7012 7021 8942,111210 8942, Moscati, M. 423250 9292,713000 9292 717000 7012 7021 8942, 810000 7012 7021

Molinari, V.G. 325000 6580, 422110 8250, 540000 6580, 870017 6580

Monnier, A. 010000 10008, 329000 10008

Montaguti, A. 112120 8871, 122100 8871, 122200 8871

Montenegro, E.C. 122200 8822, 613000 8822

Moore, M.S. 010000 8846, 122100 8846, 870090 8846, 870092 8846, 870094 8846

Moore, R.E. 112930 8436 9027,, 220000 9027, 222000 8436 9027, 870092 8436

Moreau, J. 312000 6381, 713000 6381

Morel, J.E. 513200 9001

MoSel, U. 010000 6583, 111110 6583, 121100 6583, 870092 6583, 870094 6583

Moses, G. 521130 9057, 717000 9057,'717100 9057, 793000 9057, 810000 9057

Moses, G.A. 010000 6773 8471 9389,329000 9127, 521130 8816 9542 9544, 522130 9542, 717000 9542 9543, 717100 6773 8471 8816 9127,9389 9544, 793000 8816 9544, 794000 8816, 810000 6773 8816 9127 9389 9542 9543 9544, 869999 9389, 870094 9544

Moses, G.A. (Comp.) 010000 9546, 717100 9546, 810000 9546

Moses, R.W. 717000 8894, 810000 8894

Moss, O.R. 112930 9926, 220000 9926, 222000 9926

Morford, R.J. 329000 9986, 713000 9986, 750000 Moteff, J. 000000 6740 9986, 810000 9986

Morgan, G.L. 122100 6763, 422140 8392, 430000 8392, 794000 8392, 870003 6763

C <*

Morhart, A. -220000 9284, 551110 9284, 552210 9284^845000 9284 „

' J f * Mori, S. " 010000H038 8938, 111210 8938, 717000

7 0 3 8 ^ 3 ^ J g p

V

Motta,£M. 112120 8871, 122100 8871 9268, 122200 8871, 870094 9268

Mouring, R.W. 410000 8733,712000 8733,863000 ,8733

Muckenthaler, F.J.^ 551110 6460, 713000 6460 ;

Mughabghab, S.F. 122100 6821, 870079 6821

465

Muir, D.W. 010000 9432, 112710 9441, 122100 9432 9441, 122310 7031, 312000 7031, 511110 7031, 610000 9441, 717000 7031 9441, 793000 9441, 810000 9432 9441, 870003 7031

Mulhern, O.R. 020000 6893 9224, 220000 6893 9224, 410000 9047, 430000 6893 9224, 770000 9047

Mullender, M.L. 111110 8380

Murphy, M.F. 210000 8610, 421140 8610

Murphy, T.D. 010000 6407, 112760 6407, 719A00 6407

Murray, J . 710000 9195, 750000 9195

Murthy, K.P.N. 010000 7074, 322000 7072, 329000 6433, 521130 7074, 713000 7074, 722100 7072, 810000 7074

Mynatt, F.R. 010000 6602 8710, 111220 6602, 551110 8710, 552210 8710, 713000 6373 8710, 717500 6602, 719B00 8710, 793000 8710, 794000 8710, 810000 6602 8710

Naber, J.A. 112930 6940,610000 6940

Nagarajan, P.S. 121100 7067, 329000 7067, 810000 7067

Naik, S.B. 02.0000 9216, 220000 9216, 430000 9216

Nair, S. 111700 8757, 112120 8740, 112940 8757, 223000 8757, 230000 8757, 719A00 8740, 887000 8740

'' . V ° <. Najzer, M. 111110 6850, 421130 6850, 421140

6840 6850 8599, 430000 6850 8599, 511120 6840,810000 6840 T

Nakagawa, T. 122100 6686 9837,° 870092 6686, 870094 6686, 870096 9837

N a k a h a ( \ A . 329000^9547, 554110 9547©

e &

Nakamura, T. 020000 9839, 112200 6868, 329000 6868, 511120 9142, 512110 6869 9142, 512210 6869, 820000 6869, 861000 6869, 863000 6868, 870006 9142, 870013 6868 6869, 870082 6868 6869

Nakazawa, M. 020000 9839, 111110 6832, 410000 6832, 421130 6832, 421140 6832, 511120 6832

Nambi, K.S.V. 423250 7084

Napolitano, D: 424000 10000, 719A00 10000

Narayan, J. 210000 9495, 717000 9495, 870029 9495, 870079 9495

Nargundkar, V.R. 717000 8924, 870004 8924

Natume, H. 551120 6464, 718000 6387 6464, 721100 6387, 721201^6464, 731300 6464

Navalkar, M.P. 310000 7066,511110 7066,713000 7066, 870092 7066, 870094 7066

NCRP 010000 8505, 112710 8506, 220000 8505 8731, 420000 8505 8506, 610000 8506

Neef, R.D. 551120 8866, 719B00 8866, 810000 8866

Neef, W. 717000 7005, 810000 7005

Neef, W.S.,Jr. 010000 8942 9483, 111210 8942, 717000 8942 9483, 717100 9483, 810000 9483

0 /Neil, B.C.J. 112120 6410, 223000 6410, 719C00

^ .6410

Nelson, P. 32AOOO 9748, 551110 9748

Nesterov, B.V. 112120 6750, 870092 6750

Nestor, C.W.,Jr. 122200 6859, 810000 6859

Netecha, M.Ye 325000 7098, 521130 7098, 522130 7098, 632110 7098, 820000 7098

Nette, P. 020000 9210, 220000 9210, 430000 9210

-<- 0 o

466-

Newcombe, H.B. 010000 9642, 220000 9642, Nishina, K. 310000 9402 222000 9642, 223000 9642 H

Newman, B.M. 223000 6414, 719A00 6414 Nishizaki, T. 551120 6464, 718000 6387 '6464,

721100 6387, 721200 6464, 731300 6464

Newman, D.F. 521130 8373, 717000 8373, 810000 Nolfi, F.V. 210000 8957, 810000 8957 8373

Nguyen, V.D. 010000 8855, 122100 8855, 210000 8855, 760000 8855, 845000 8855

Nichols, A.L. 010000 8844, 112710 8844, 122200 8844, 810000 8844

Nichols,, F.A. 010000 8089, 210000 8089

Nichols, J.P. 112930 7091, 220000 7091, 222000 11 7091, 713000 7091, 719A00 7091, 719B00 7091

Nicks, R. 010000 9131,020000 6420,122110 6420, 713000 9131, 717000 6423

Nieschmidt, E.B. 112710 8973, 222000 8973, 223000 8973, 719^00 8973

O o

Nolthenius, H.J. 111110 8642, 122110 6847 8637 8640, 122310 6816, 421140 6816 6829 6846 6847 8637 8638 8639 8640 8642, 430000 6846 8638 8639, 511110 6846, 511120 6816 6829 8639, 810000 6816, 870092 6816, 870098 6816

Nonaka, 1. 410000 8726, 424000 8726

Norem, J. 111210 9421, 620000 9421, 710000 9421, 717000 9421, 810000 942 T

it,

Northcutt, K.J. ' 112120 6696 6941 7046 8030 8031-9450, 221000 6696, 421200 7046, 430000 6696 7046, 532000 6696, 610000 8030 8031, 794000 6696, 870092 7046, 870094 6696 8031 9450

Nozaki, "J. 410000 9737

Nigg, D.W. 521130 9123, 522130 9123, 717000 JNuh, p 1 1 2 i 2 0 6747, 532000 6747, 870092 6747 """ 1 ti * »

Nussbaumer, D.A. 010000 6309, 112600 6309,

O 112710 6309, 230000 6309

9123,,810000 9123

Nikitin, A.V. 322000 7099, 325000 7098'; 330000 7099, 521130 7098 7099, 522130 7098 7099, 632110,7098, 820000 7098 7099

Nikolaev, M.N. 020000 6615, 122100 6615 8113,« 870001 8113

Nikolajcv, A. 713000 6394, 721200 6394, 870011 ° ' D e »> 329000 7045, 421120 7045, 422140

O'Brien, E.E. 222000 8404, 329000 8404

O'Brien, K. 220000 8381 8384

6394 7045, 430000 7045

| Nikolayev, M.N. 122110 7100, 511110 7100, O'Dell.R.D. 32A000 9744 9747, 551110 9744 9747 810000 7100 " _ ' V .

b Nimal, J.C. 010000 10008 9989, 122310 9989,

329000 10008 9989 9990, 521130 9989, 719A00 9990 * •

a Ninkovic, M.M. 223000 6457

CDonnell , F.R. " 112710 8783, 220000 8456 8783, * 223000, 8456 8783, 632300 8456', 711100 8783,

845000 8783, 861000 8456

Oakes, T.W. 112760 6946, 112930 6946, 222000 6946, 717000 6946

Nishimura, T. 631000 6443,713000 6443,721100 Oberhofer, M. 000000 8930,020000 9221, 220000 6443 f 8930 9221, 430000 9221

467-

Oblow, E.M. 010000 8576,020000 6419 8517 8576, 111220 7095, 122100 8032 8576, 122110 6419, 122310 6872 7095 8517 8518 8576 8668,123000 8668, 310000 8666, 311000 8666, 312000 6382 8032 8141 8666 9316, 32AOOO 8032 8517 8518, 511110 7095 8032, 512210 8032, 521130 8518, 551110 8517 8518 8577, 551200 8577, 552110 8517, 713000 6382 8576, 717000 8032 8517,, 8518, 719A00 9316, 721100 8517, 793000 8517

•8518 8577, 794000 8517 8518 8577, 810000 8576, 830000 8032, 842000 8032, 853100 8032 8517, 861000 6382 8032 8517 8577, 870008' 7095, 870011 6382 8577, 882000 8032

Oden, D.R. 711100 6626

Odette, G.R. 010000 6668,-121100 8888, 210000 7044 8591 8888 8957, 421140 6668 8591, 430000 8591, 521130 8591, 717000 6668 7044 8591, 793000 8591, 810000 7044 8591 8888 8957

fr Oh, S.J. 112120 6747, 532000 6747, 870092 6747

Ohnesorge, W.F. 223000 8799, 719A00 8799. 721200 8799

Ohno, A. 112940 9638,423250 9638

Ohr, S.M. 210000 9495, 717000 9495, 870029 9495, 870079 9495

Ohsumi, K. 112760 6978, 223000 8476, 631000 8476, 719A00 6978 8476

Oka, Y.( 020000 6462 9839, 551110 9632, 551120 v 6462 9632, 713000 6397, 721200 6397, 760000 9822, 861000 6462 9632, 870011 6462

Okawa, K. 853400 9702

Okta, L. 112BOO 9126^121200 9126, 810000 9126

Okula, K. 210000 9069,521130 9069,717000 9069, 810000 9069, 861000 9069

Okumura, Y. 551120 6464, 718000 6387 6464, 721100 6387, 721200 6464, 731300 6464

Olhoeft, J.E. 020000 9752

Oliva, A. 122310 6573, 861000 6573

Oliver, D. % 717500 7026, 810000 7026

Olsen, D.K. 121100 6861, 122100 6317, 123000 6861, 810000 6861, 870092 <5317

f/ <> -Ombrellaro, P.A. 1 713000 8111, 870008 8111,

870096 8111 0

G; Jis, L.A.,II 329000 8237, 719A00 8237

Orlov, N.Yu. 329000 7109, 722100 7109, 810000 „ 7109

Orlov, Yu.V. 421120 7122 7123, 421130 7110 7111 7116, 421140 7110, 421200 7111, 430000 7122 7123, 511120 7122 7123, 521230 7110 7111 7116, 522230 7111, 610000 7116, 710000 7110 7111, 719A00 7110 7111, 810000 7111 7116 7122 7123

Ortman, M. <329000 9127, 717100 9127, 810000 9127

Ortman, M.S. 222000 8251, 717000 8251, 869999 8251

Osanai, M. 718000 6386, 721100 6386

Osmera, B. 713000 6394, 721200 6394, 870011 6394

Ir

Ostenak, C.A. 711100 10064

Oster, C. 122310 8659, 210000 8659, 421140 8659, 430000 8659; 719A00 8659, 861000 8659

Otopal, P. 713000 6394,721200 6394,8700116394

Otte, V.A. 111220 9287, 511120 8530, 760000 9287, 842000 8530, 843000 8530, (861000 8530

Oyamada, R. 210000 8606, 421140 8606, 422130 8606, 870092 8606, 870094 8606

0

Ozer, O. 010000 8964, 020000 9753, 112120 8964, 122100 8964, 719A00 8964

Pace, J.V.,Ill 122110 7129, 122210 7129, 220000 9532, 511110 7129, 512210 7129, 551110 9532, 552110 9532, 552210 9532, 793000 9532, 810000 7129, 830000 7129, 845000 9532, 853100 7129

Packwood, A:,, 010000 6824, 421140 6824, 430000 6824, 810000 6824

Pal, B. 121100 7057, 810000 7057

Palmiotti, G. 122310 6459 6573, 312000 6576, 531000 6576, 717000 6576, 794000 6576, 861000 6459 6573, 870011 6459

O Panchenko, A.M. 329000 7108, 512110 7108,

., 861000 7108

Panini, G.C. 112120 8871, 122100 8871, 122200 8871

Pankrat'yev, Yu.V. 000000 7097, 010000 7118, 121100 7121, 122110 7121, 420000 7118, 421150 7118 7120 7127, 511120 7118^ 7120 7127, 521230 7127, 740000 7126, 810000 7121,

« 853100 7127,853200 7126 7127,853300 7127, 853400 7127, 853500 7127, 853600 7127, 853700 7127, 853800 7126, 861000 7118 7120, 870013 7120, 870022 7120

Parish, T.A. 111210 8567, 112120 7032, 223000 8567, 230000 7032 8555 9559, 32A000 7032, 521130 8567, 522130 8567, 717000 7032 8555 8567, 793000 8567, 810000 7032 8567, 870006 7032

Park, J.F.'< 112930 9926,220000 9926,222Q00 9926

Parkin, D.M. 210000 7008 8957, 810000 8957, 870041 7008, 870050 7008

Parkinson, J.R. 010000 8844,112710 8844,122200 8844, 810000 8844

Parkinson, W.W.,Jr. 220000 9044, 329000 9044, 845000 9044

Parmentier, N. 010000 8855,122100 8855, 210000 8855, 760000 8855, 845000 8855

Parvez, A. 121100 6649, 122110 6649, 122310 6880, 312000 6456, 324000 6803, 511110 6803, 794000 6880, 861000 6803, 870011 6880, 870092 6803 ft

Passe, J. 421150 8609

Patterson, H.W. 111110 9045, 111220 9045, 422140 9045

Pauko, M. 421140 8599, 430000 8599

Pauli, H.C. 010000 8239, 112710 [>'239, 610000 8239

Paulsen, A. 122100 8629, 210000 8629, 421140 8629, 810000 8629

Payen, J.P. 719A00 6391, 7211/JO 6391, 722100 6391 '

Pearlstein, S. 010000 8964, 111210 8868, 112120 8964/ 121100 6593 8142 8145, 122100 8964, 719A00 8964, 810000 6593 8868 •>>

Pease, R.L. 210000 8753, 870014 8753

Peckover, R.S. 010000 6890, 532000 6890, 713000 6890

Peddicord, K.L. 310000 9749, 510000 9749, 511110 9749

Peek, J.M. 010000 9800, 123000 9800^ 750000 9800

Peelle, R.W. 010000 6591, 020000 6591, 112120 6696 6941 7046 8030 8031 9450 9819, 122100 6591, 122110 8975, 122310 6872 8975, 221000 6696, 421200 7046, 430000 6696 7046, 532000 6696, 610000 8030 8031, 794000 6696, 810000 8975, 870092 7046 9819, 870094 /6696 8031 9450

Peeters, E. 424000 7088

469-

Pego, R. 329000 9759, 719B00 9759

Pelletier, C.A. 112930 8644, 223000 6477, 719A00 6477 8644 „

/ Peng, W, j21100 6383

Peng, W . H / 122310 8580, 327000 8580, 511110 8565/8580, 512210 8565, 770000 8565, 793000 8565, 830000 8565, 853100 8565, 861000 8580, 870011 8580

a ti Peng, <y.K. 111120 8918, 870092 89,18

I Penkuhn, H. 020000 6420, 122110 6420 it

Pepin, P. 112760 6408,713000 6408,719A00 6408, 719B00 6408

Peranich, L. 521130 9542, 522130 9542, 717000 9542, 810000 9542

Perdreau, R. 210000 8628, 551120 8628, 810000 8628

Perdue, P.T. 222000 8121, 223000 8121

Perevalov, V.S. 210000 7125,853100 7125 tf U'

Perey, C.M. 122100 10078, 861000 10078 u

Perey, F.G. 010000 6535 6630 8576 8669 8840, 020000 8576 8669, 122100 10078 6630 8576 8823 8840, 122310 8576 8669 8840, 421140 6535 7133, <'430000 6535 7133, 713000 8576, 794000 7133, 810000 6630 8576 8669, 861000 10078, 870006 8823 8840, 870092 8840

Perez, R.B. 121100 6861, 122*00 6317, 123000 6861, 810000 6861, 870092 6J17

Pergamenshchik, B.K. 210000 7125, 853100 7125 <j

Perkins, S.T. 121100 7048, 122100 8681, 122110 7048, 122200 8681, 717100 8548 8549, 810000 8681

Perry, D. 020000 9212, 220000 9212, 430000 9212

Perry, R.B. 424000 9260, 711100 9260, 870094 9260, 870095 9260

Perry, R.T. 010000 9935, 32A000 8190, 521130 8190 8373, 717000 8373, 717100 8190,,9868 9935, 810000 8190 8373

Persson, R.B.R. 22200C 6470, 719A00 6470

Peterson, M.A. 010000 8942,111210 8942,717000 8942

Peterson, N.L. 010000 8258, 210000 8258

Peterson, R.R. 521130 9542, 522130 9542, 717000 9542 9543, 810000 9542 9543

Petitcolas, H. 421150 8609

Petr, I. 112B00 9126, 121200 9126, 810000 9126

Petrie, JL.M. 010000 9992, 122110 8515 9992, 122210 8515, 312000 6645, 32AOOO 8515, 329000 6645 9992, 521130 8515, 522130 8515, 712000 9992, 719A00 8120, 794000 8515

Petrov, E. 713000 6394,721200 6394,870011 6394

Petrov, E.Ye. 312000 7104, 552110 7104, 810000 7104

Pevey, R.E. 122110 9933, 122210 9933, 711100 9933, 793000 9933, 794000 9933, 810000 9933

o Pfister, G. 010000 8854, 122100 8854, 122200 8854, 220000 8854, 760000 8854 9285, 793000 8854, 845000 8854 9285', 870006 8854, 870008 8854

Philis, C. 122100 9265, 122310 9265, 870094 9265

Phillips, D.C. 210000 8188, 717000 8188, 841000 8188,842000 8188,844000 8188

Phillips, J.R. 711100 10064

Piesch, E. 220000 8995, 410000 9367, 420000 9367, 511120 9367, 521210 8995, 522210 8995

470-

Pilat, E.E. 122110 9991, 329000 9991, 711100 9991, 793000 9991, 794000 9991, 810000 9991

Pilver, A.B. 32A000 8802, 551110 8802, 710000 8802, 719AOO 8802, 721100 8802, 810000 8802

Piskunov, V.I. 421150 7127, 511120 7127, 521230 7127, 740000 7126, 853100 7127, 853200 7126 7127, 853300 7127, 853400 7127, 853500 7127, 853600 7127, 853700 7127, 853800 7126

Pivovarov, V.A. 122110 8114,713000 8114,810000 , 8114

Pleasant, J.C. 112760 9376,112930 9027,220000 8213 9027 9111-9376 9928, 222000 9027 9111, 610000 9376,1711100 9376, 845000 8213 9376

, 9928 Q

Plechaty, E.F. 122100 8681, 122110 8682, 122200 8681 8812, 810000 8681 8682 8812

Poenitz, W. 122100 6659, 870090 6659 O

Poenitz, W.P. 122100 6498 6585, 870092 6498 I 6585, 870094 6498 6585 \ o >«••

Pohl, B. 511120 6875, 512210 6875, 830000 6875

Pohl, B.A. 111210 9252, 112400 9252, 112500 9252, 122310 8859 9252, 511120 8859, 512220 8859, 717000 8859, 870029 8859, 870041 8859, 870090 8859, 870092 8859

Poston, J.W. 020000 9798, 113100 6698, 220000 6698 8045 9798, 423210 6698,' 423250 6698, 553120 6698, 845000 6698

dPottmeyer, E.W.,Jr. 010000 9488, 111220 9488, 210000 9488, 410000 9488, 717000 9488

Powell, J. 230000 9083, 717000 9083

Powell, J.R. 010000 7043 8945, 111210 8945, 521130 9342, 522130; 9342, 531000 6592, 532000 6592^717000 6592 7043,8945 9342, '93000 9342, 810000 7043, 870013 6592

Pozdneev, D.B. 522110 8389, 522210 8389, 861000 8389, 870004 8389, 870006 8389, 870050 8389,

•„,. '870082 8389

Pozdneyev, D.B. 522110 7071, 522210 7071, 810000 7071 i''

Praeg, W. 111210 9421, 620000 9421, 71C000 9421, 717000 9421, 810000 9421

Prael, R.E. \ 11220 9894 •J

Prasad, M.AI' 329000 8922 9734, 513200 8919

Premuda, F! 310000 9064

i Price, 111210 8951, 210000 8951, 717000

8951,870006 8951,870014 8951

Price, W.G.,Jr. 312000 6450,32A100 6765,620000 6450, 717000 6450 6765, 883000 6450

Pohlit, W. 410000 9052, 750000 9052, 760000 9052 ? '

Polushkin, K.K. 223000 6406, 719A00 6406

Pomerantsev, G.V. 713000 6421 O -y

Pomraning, G.C. ! 321000 8473, 325000 8473, 717000 8473

Ponti, C. 717000 6423 u

Popa, F. 421140 6844

w

<•' Primak, W. 210000 8875 9723, 717000 8875, 810000 8875, 852000 8875, 870006 9723, 870014 9723

Prince, A. 122i00 9274 9828,870024 9828,870036 9274

Priseman, S.J. 010000 8780, 220000 8780 (J

Profio, A.E. 000000 9959

Project Staff - Argonne National Lab. 32A000 8496, 329000 8496, 551110 8496, 552110 8496, 717000 8496, 793000 8496, 810000 8496

471-

Prosperi, M. 713000 6428

W s s e r , J.S. 010000 8780, 220000 8780

Protsik, R. 122110 8252

Prussin, S.G. 112120 6747, 532000 6747, 870092 6747

Przibram, E. 710000 8805, 7J9A00 8805, 721100 8805, 810000 8805 o

Pugh, I.G. 223000 6400, 719C00 6400 I,

Puite, K.J. 020000 9219, 220000 9219, 430000 9219

Puliandri, P.I.A. 210000 8622, 422110 8622, 861000 8622

Purrott, R.J. 010000 8780, 220000 8780

Pushpandpangadan, K.D. 020000 9216, 220000

Ragan, C.E. 111210 8428, 422110 8428, 511120 8428, 870003 8428, 881000 8428

a 9216, 430000 9216

Putz, V. 310000 9732, 540000 9732

Ragan, G.L. 422130 8478, 870093 8478

Raghavendran, C.P, 121100 7067, 329000 7067, 810000 7067

Ragheb, M.M.H. 112760 9114, 329000 8228 8231 9127 9760, 521130 8228 823l"8807 9057 9542, '

,, 522130 8807 9542, 711100 9760, 717000 677.2 8228 9057 9114 9542, 717100 8231 8467 8807 • 9057 9127 9541 9760, 793000 6772 8807 9057, 794000 8807,810000 6772 8228 8231 8467 8807 9057 9127 9541 9542

Rahn, F. 010000 8792, 223000 8792, 521110 8792, 522110 8792, 610000 8792, 719AOO 8792, 722100 8792, 853100 8792, 861000 8792

Rahn, F.J. 010000 6810, 210000 6810, 421130 6810, 421140 6810, 511120 6810, 719A00 6810,

,861000 6810 O

Rainis, A.E. 329000 9562, 551110 9563, 552110 9563, 731100 8263 9561 9562 9563, 793000 9561 9562 9563, 810000 95635-

Pychlau, P. 020000 9210, 220000 9210, 430000 9210

Qaim, S.M. 010000 8858 9784, 121100 8870, 122100 8858 9784, 210000 8858,9784, 410000 8870, 717000 9784, 760000 8858, 810000 8870 9784, 845000 8858

Quan, B. 122310 8655, 719A00 8655, 810000^655

Quimby, D.C. 521130 7027, 717100 7027, 793000 7027, 810000 7027

Rancurel, H. 511120 6458, 713000 6458, 870011 6458 "

Randolph, M.L. 220000 8456, 223000 8456, 632300 8456, 861000 8456

Rant, J. 421140 6840, 511120 6840, 810000 6840 "i S;

RassI, G. 421140 8631, 810000 8631, 870098 8631

Rataj, J . 713000 C394, 721200 6394, 870011 6394

Rado, V. 122310 8865, 511120 6458, 713000 6458 8865, 810000 8865, 870011 6458

Rawls, J .M. 210000 8887, 717000 8887, 861000 8887

Raeder, J . 111210^8952,210000 8952, 717000 8952

Raedt, Ch. de 210000 861g?*22l£f i 8618, 423250 8618, 532000 8618, 713000 8618, 810000 8618

Razumovskiy, M.V. 42*1130 7110, 421140 7110, 521230 7110, 710000 7110, 719AOO 7110 '

Realini, G. 717000 6423

472

Reddy, A.R. 122200 8828, 423250 8828, 845000 Reynolds, A.B. 010000 6213,112710 6213,112760 8828

Reeder, E.J. 010000 8780, 220000 8780

Reffo, G. 112120 8871, 122100 8871,122200 8871

Regulla, D.F. 010000 7078, 121200 7078, 220000 7078, 423240 7078 O

Reich, H. 020000 9038 9198 9199, 220000 9198 9199,430000 9198 9199

Reid, R.L. 111210 7089,717000 7089

Reilly, T.D. 711100 10064

6213, 112930 6213, 713000 6213, 870092 6213, 870094 6213

u Reytblat, V.L. 112500 7114, 423250 7114, 511110

7114, 512210 7114, 512220 7114, 853800 7114, 861000 7114

Rhoades, W.A. 32A000 6449 9745, 551110 9745

Ribe, F.L. 010000 9935, 717100 9935

Ribon, P. 112120 8871,122100 8871,122200 8871

Ricci, E. 122200 6859, 810000 6859

Ricco, G. 421130 9399, 430000 9399

Reis, D. 020000 9210,220000 9210,430000 92100 u

lf Richardson, B.L. 010000 6446, 32F000 6446 O ' <

Reis, U. 112710 9100,610000 9100 . . Richings, L.D.G. 020000 6938, 222000 6938,

J 223000 6938 Rekshnya, N.F. 531000 7105,532000 7105,810000

7 1 0 5 Richmond, R. 020000 6799, 511120 6799, 861000 II 6799

Renier, J.P. 111220 8901, 717500 8901, 870090 f - . f y „ 8901, 870092 8901, 870094 8901 ' ^ ^ ^ ^

532000 10080, 851000 10080

Ricourt, A. 010000 U8855, 122100 8855, 210000 8855, 760000 8855, 845000 8855

Rider, J.L. 112930 6637 9130, 222000 6637 9130, 719A00 9130 0

<tf

Riedel, D.W. 424000 10073, 870088 10073, 870092 10073

« <> Rief, H. 312000 6379 </

Renken, J.H. 312000 8654, 329000 8654^30000 " 8654,551110 8654,810000 8654

Renner, C. 422140 8392, 430000 c8392, 794000 8 3 9 2 XT-

Rensink, M.E. 010000 8942, 111210 8942, 717000 8942

Repin, N.N. 112500 7113,421200 7113 ©

Reupke, W.A. 122110 6522, 122310 6522 7031, 312000 7031, 511110 7031, 521130 6522, Rieffe, H.Ch. 111110 8642, 122110 6847, 122310 717000 6522 7031, 810000 6522, 870003 6522 7031

Reuss, P. 000000 8259

8872, 421140 6847 8642, 713000 8872 j>

Rinard, P.M. 552110 9919, 632120 9919, 711100 9919, 719A00 9919 '

Reuther, T.C. 010000 8956, II1210 8956, 210000 Ritchie, J.C. '423140 8047, 719A00 8047, 721200 8956 8957, 717000 8956, 810000 8956 8957 8047

473-

Ritchie, L.T. 112930 6538, 220000 6538, 222000 6538

Roberts, J.H. 010000 6812, 122310 6812, 430000 6812

Roberts, M. 717000 7002, 810000 7002

Rosinger, E.L.J. 230000 9886

Rossiter, M.J. 020000 9204, 220000 9204, 430000 3 9204

Roswell, R.L. 112930 9926, 220000 9926, 222000 9926

Robinson, F.L. 112120 6469, 532000 6469,719A00 6469

1 Robinson, M.T. 122110 9093, 210000 8248 8957, 32A000 8248 9093, 717000 8248, 794000 9093, 810000 8957, 870079 9093

Roche, C.T. 424000 9260, 711100 9260, 870094 9260, 870095 9260

Rockwood, A.D. 010000 9935, 717100 9935

Rogers, J.W. 020000 6834 8592 8636,111110 6864 " 9122, 410000 6834 6864, 421110 8592 9122,

421140 6834 6864 8636, 430000 9122, 511120 6834 8636, 713000 6864 8592 8636 9122, 717000 8356, 770000 6864, 810000 6864 8356 8636

Romero, J.B. 521130 9826, 522130 9826, 717000 9826, 844000 9826 <j

Ronen, Y. 312000 9255

Rood, P.L. 32A100 6242, 514110 6242, 717000 6242

Rose, P. 020000 6293, 329000 6293, 719A00 6293

Roussin, R. 122110 7129, 122210 7129, 511110 7129, 512210 7129, 810000>7129, 830000 7129, 853100 7129

Roussin, R.W. 000000 7075, 010000 6415 7075 8650, 020000 6418 6419, 122100 6418, 122110 6419 8514 8515, 122210 8514 8515, 122310 8(>50, 223000 6415, 312000 8650, 32A000 8515, 521130 10006 8515, 522130 8515, 794000 8515, 810000 8514, 853100 10006, 861000 10006

Rowlands, J.L. 010000 8270.8837, 112120 8270, 122100 8837, 713000 8270, 719A00 8270, 810000 8837, 870092 8270, 870094 8270

Roy, S.C. 000000 7051, 010000 6785 7051,121200 6785 7053, 423230 8831, 522210 8992, 810000 7053, 841000 8992, 853100 8992, 861000 8992, 8700i3 8992, 870082 8992

Roybal, J.A. 310000 9749, 510000 9749, 511110 9749

Rozenfeld, M. 020000 9208, 220000 9208, 430000 9208 "

kuden, B . - I . 020000 9220, 220000 92.20, 430000 9220

Rose, P.F. 010000 8964, 020000 9997, 112120 8964, 122100 8964°329000 9997, 521130 9997, 719A00 8964, 810000 9997

Rose, R.P. 717000 7023, 717100 9163 9164, 887000 7023

Rudstam, G. 010000 8420, 111120 8420, 870092 8420 °

Rueppel, D.W. 111110 9045, 111220 9045, 410000 8225, 421130 6954, 421150 6954, 422140 9045,

0 430000 6954 8225, 511120 6954, 870098 6954

Rosel, F. 010000 8239,112710 8239,610000 8239 Rummerfield, P.S. 760000 8472.

Rosenwasser, S.N. 210000 8887, 717000 8887, ~ 861000 8887 , c

0 Rupp, E.M. 112930 8436, 222000 8436, 870092

8436 ° "

474-

Rusch, D. 329000 9438, 521130 9438,717000 6877 9438, 793000 9438, 794000 9438, 810000 9438, 870003 6877

Rush, K. 422140 8392, 430000 8392, 794000 8392 i

Russo, A J . 112930 6538, 220000 6538, 222000 6538

Ryan, M.T. ^220000 9927, 222000 9927

Ryskamp, J .M. 122310 8655 8671, 719A00 8655 8671, 810000 8655 8671

Saccenti, J.C. 210000 8624, 220000 8624, 713000 8624

Salzano, F. 8945

010000 8945, 111210 8945, 717000

Sanders, J.K. 210000 8695, 421140 8695, 521230 8695, 713000 8695, 810000 8695

u1

Sanders, L.G. 010000 8856, 424000 8856, 430000 A 8856, 810000 8856

Sangiust, V. 010000 8600, 421140 8600, 430000 8600

Sanjeevaiah, B. 112200 7060,121200 7056, 810000 7056 7,060 Jf

Sahin, S. 11)130 8526

Sahni, D.C. 321000 7064 ' C

Sakata, S. 020000 6462, 551120 6462, 861000 6462, 870011 6462 ,

ff o

Sakharov, V.K. 512220 6472,820000 6472, 861000 6472, 870082 6472

•> ' o Sakharov, V.M. 112500 7113, 421140 7112,

421200 7113, 521130 7106, 522130 7106, 620000 7106, 719A00 7112, 721100 7112, , 721200 7112, 810000 7106, 853800 7112, 861000 7112

Sako, K . ' ' 717000 7015, 810000 7015

Sakovich, V.A. 112500 7113, 421200 7113, 521130 7106, 522130 7106, 620000 7106 7107, 810000 7106

Salmi, U. 122310 8653,521130 8653,713000 8653, 810000 8653

Saltmarsh, M.J. 010000 8790, 122310 9400, 422110 9400, 521130 8807, 522130 8807, 717100 8790 8807, 793000 8807, 794000 8807, 810000 8790 8807 ^

Salvatores, M. 122110 8975, 122310 6459 6573 886°5 8975, 312000 6576 6801, 531000 6576, 713000 8865, 717000 6576, 794000 6576, 810000^865 8975, 861000 6459 6573, 870011 6459

Santoro, R.T. 010000 8790 8943, 020000 8517, < ,111210 8943, 112760 9114, 122100 8032,

122310 8517 8518, 210000 6247 8736 9030, 220000 8034, 312000 8032, 32A000 8032 8034 8517 8518 8563, 329000 6425, 510000 9856, 5 1 1 ^ 0 8032, 512210 8032, 521130 6247 7130^ 8518 8563 8736 8807 9030, 522130 6247 7130 8736 8807, 531000 6247 7090 7130 8214, 532000 6247 7090 7130 8214,551110 8034 8214 8517 8518 8736, 552110 8517 8736', 552120 8214, 552210 8034, 552220 8736, 717000 6247 6425 7090 7130 8032 8214 8517 8518 8563 8943 9030 9114 9115, 717100 8790'8807, 721100 6425 8517, 793000 6247 7090 8034 8517 8518 8807 9030 9856, 794000 8517 8518 8807, 810000 6247 7090 7130 8214 8563 8790 8807 9856, 820000 8034, 830000 8032 8736, 842000 8032, 851000 8736, 853100 8032 8034 8517, 853900 8736, 861000 6247 8032 8034 8517 9030, 862000 9030, 870003 6247, 870023 9030, 870027 9030, 882000 8032

Sarkar,, P.K. 329000 8922 9734, 421130 7086, 421200 7086, 430000 7086

Sartori, E. 721100 10002, 853100 10002, 870011 10002

r.

Sasaki, K. 713000 63^7, 721200 6397

' i.." ° ' •.• • Sasamoto, N. 020000 9839, 32AOOO 9144, 421130

6853, 430000 685,-3 8086, 522120 9557, 794000 8086, 830000 9557, 870098 6853

475-

Satarin, V.Ye. 421130 7111, 421200 7111, 521230 7111, 522230 7111,710000 7111,719A00 7111, 810000 7111

Savitsky, V.I. "713000 6421 A

v j Savyuk, S.N. 522110 8389, 522210 8389, 861000

8389, 870004 8389, 870006 8389, 870050 8389, 870082 8389 if" J ^ ii

ISawdye, R.W. 112930 8025, 220000 8025, 222000 8025, 717000 8025, 810000 8025

Sayed, A.M. ,.,421140 8615, 423135 8615, 423250 8615, 531000 8615, 532000 8615

i i Sayeg, j"A. 513120 8985, 760000 8985, 885000

8985

Scarpa, G. 423250 9292, 713000 9292

Schaefer, R.W. 010000 8191,122310 8191,870090 8191, 870092 8191

Schanzler, L. 111110 9328, 112110 9328, 420000 9328, 421130 6517 9193, 421200 9328, 430000 6517 9193, 511110 9192, 511120 9328, 512110

" ( 9192, 512120 9328, 512210 9192, 521230 6517, 522130 9193, 522230 6517, 793000 9192 9193, 810000 9328, 830000 9192 9193,,853100 6517,

c 861000 6517, 870007 9192, 870098-9192 tr

Scheffel, J . 111210 10155, 717000 10155

Scheinman, L. 711100 10062 10063

Schenter, R.E. 010000 8422&112120 8118 8422, 122100 9269, 532000 8118 8422, 870092 8118 8422, 870094 8118 9269, 870095 9269

cScherpelz/R.I. 010000 8140, 111120 8140, 420000 8140,424000 8140 O

Schiffgens, J.O. 111220 9493, 210000 9493,717000 9493, 810000 9493 '

ji . " ' ,- " « Schmidt, R. 220000 9290, 760000 9290, 842000

9290, 845000 9290

a

Schmittroth, F. 010000 6748,112120 8118,122110 - 9362, 122200 9251, 122310 8659 8660 9362,

210000 8659 8660, 421140 8659, 430000 6748 8659 8660, 521130 8660, 532000 6910 8118, 713000 6910, 719A00 8659, 810000 8660, 861000 8659 8660, 870092 8118, 870094 8118

Schmocker, U. 020000 6799, 511120 6799, 861000 6799

Schneider, A. 5,71130 7035, 522130 7035, 717100 7035, 793000^035, 810000 7035

Schneider, W. 210000 8617, 422110 8 617

\ Schneiders,YjN.J. 513120 8984,t 760000 8984, 885000 8984 / f

{/

O /• Schoepf, K.F. 717100 9068

Schonbacher/1 H. 210000 9337, 841000 9337, 842000 9337, 844000 9337

Schrack, R.A. f020000 8247, 410000 8247, 421160 8247

Schrandt, R.G. 010000 10004 9978, 121200 8116, 329000 10004 8116 9978,^512110 8116, 521130 9978, 610000 8116, 810000 9978, 830000 8116

Schraube, H. 220000*3284 9293, 421150 9293. 511120 9293, 551110 9284, 552210 9284, 845000 9284

Schriever, R.L. 010000 7039, 717000 7039

Schrock, V.E. 112120 6747, 532000 6747, 870092 6747 o

G

Schulte, S.C. 0 010000 9935, 717100 9935

O Schultz, K.R. 010000 7021 9484, 717000 7021,

717100 6231 9484, 810000 6231 7021 9484, 870090 6231, 870092*6231

Schwartz, R.B. 020000 9223, 111110 9223, 430000 c9223, 870098 9223

a 476

u

Schwartz, S.A. 010000 6309,112600 6309,112710 6309, 230000 6309

Schwenk, R.M. 731100 8263

Scott, A.J. 521130 9123, 522130 9123, 717000 9123,810000 9123 *

Scott, H.L. 210000 8753, 870014 8753

Scott, J X . 111210 7089, 717000 7089 l! c '' V

Scott, J.L. (Ch.) 010000 6607,210000 6607,717000 6607, 810000 6607

Scott, L.R. 222000 8404, 329000 8404

Scott, W.H.,Jr. 312000 8654, 329000 8654,421130 9193, 430000 8654 9193, 522130 9193, 551110 8654, 793000 9193, 810000 8654, 830000 9193

Seki, Y. 010000 9782, 020000 8517,111210 8564, 122100 8032, 122310 6734 8517 8518, 210000 9782, 312000 8032,'32A000 8032 8517 8518, 329000 8564, 422130 7033, 511110 8032, 512210 8032, 521130 6734 8518 9840, 521230 7033 8953, 531000 8564, 532000 8564, 551110 8517 8518, 552110 8517, 717000 6734 7009

„ 7015 7033 8032 8517 8518 8564 9782 9840, 717100 7033, 721100 7009 8517, 793000 7033 8517 8518, 794000 7009, 8517 8518, 810000 7009 7015 9782 9840, 830000 8032, 842000 8032, 853100 8032 8517, 861000 6734 8032 8517, 870003 7033 8953, 870006 6734 7033 8953, 870092 6734 7033, 882000 8032

Sekiguchi, A. 111110 6^32, 410000 6832, 421130 6832, 421140 6832, 511120 6832

Sekimoto, H. 430000 8397

Selby, J.M. 020000 6893, 220000 6893, 430000 6893

Scudiere, M.B. 122210 6435, 329000 6435 ' o

Seamon, R.E. 122100 10066 10067, 810000 10066 10067

Selman, J. 000000 6884, 113100 6884

Seltzer, S.M. 020000 9034, 220000 9034, 430000 9034

tr

Seda, J . 522110 8829, 861000 8829, 870006 8829, Se , va- 3 1 1 0 0 0 9 750, 326900 9750, 511110 870013 8829, 870050 8829, 870082 8829 9 7 5 0

Seed, T.J. 32A000 S954, 32A100 6242 8755, 32C000 9106, 514110 6242, 717000 6242 9106

Semenov, V. 713000 6394, 721200 6394, 870011 H 6394

Seeliger, D. 010000 9788, 111210 9788, 122100, 9788,(123000 9788, 717000 9788, 810000 9788

<// Segev, M. 111210 8867, 121100 6977, 122310 0

8867, 123000 6977, 521130 8867, 717100 8867 9736, 810000 8867, 870092 6977 8867, 870094 6977

Sengupta, A. 326000 9731

Serduke, F.J.D. 112920 9539,522120 9539,731200, 9539 °

Seifferth, L. 710000 8805, 719A00 8805, 721100 8805, 810000 8805

« ' o

Sergeev, V.A. 713000 6421 / Serpan, C.Z.,Jr. 210000 8587, 421140 8587,

719A00 8587, 861000 8587

Seth, S. 020000 6799, 511120 6799, 861000 6799

477

Sethulakshmi, P. 810000 7067

Seyler, C.E. 8944

121100 7067, 329000 7067,

010000 8944, 111210 8944, 717000

Sherwood, A.C. 010000 8852,111220 8852,870006 8852, 870012 8852, 870013 8852, 870014 885*. M

Shibata, T. 410000 6833, 421160 6833, 540000 6833

Sezaki, K. 210000 8606, 421140 8606, 422130 8606, 870092 8606, 870094 8606

Sbaeffer, D.L. 112760 8735, 220000 8735 9112, 222000 9112

Shin, K. 020000 9839, 112200 6868, 329000 6868, 511120 9142, 512110 6869 9142,, 512210 6869; 820000 6869, 861000 6869, 863000 6868, 870006 9142, 870013 6868 6869, 870082 6868 6869

Shahbazi, M. 122310 8991

Shalsk, R.J. 020000 9211, 220000 9211, 430000 9211

o

Shalitin, D. 321000 8393

Shank, K.E. 112760 6946, 112930 6?46, 222000 6946, 717000 6946

Shannon, T.E. 111210 7089, 717000 7089

Sharma, R.C. 220000 9330, 845000 9330,

Sharma, S.C. 423240 7077, 712000 8382, 842000 8382, 870098 8382

Shatalov, G.E. 010000 8861 9786, 111210 9786, 122100 9786, 122310 8503 8861, 521230 8861, 717100 8503 8861 9786, 810000 8861 9786, 870092 8503

Shaw, R.A. 112760 6409, 223000 6409 8929, 719A00 6409 8929

/ / Shay^M.R. 010000 6343, 112120 6343, 532000

/ b 4 3

Sheehan, T.V. 010000 8945, 111210 8945, 717000 8945

Shemetenko, B.P. 312000 7104, 552110 7104, 810000 7104

Shinkawa, M. 310000 9402

Shiozaki, T. 853400 9702

Shipler, D.B. 220000 8649 9609, 223000 8649 9609, 423135 8649 9609, 423250 8649 9609 \

Shipley, J.lf. 711100 10062 10063 10064 it I) (>

Shirley, G.W. 717100 6231, 810000 6231, 870090 6231, 870092 6231

Shirley, V.S. 112710 9257, 610000 9257

Shirvaikar, V.V. 112930 8835, 220000 8835, 1 222000 8835,610000 8835

Shober, R.A. 325000 9006, 551110 9006, 719A00 9006, 810000 9006

o

Shore, R.A. 750000 8811, 810000 8811

Shukla, V.K. 122110 9155 IK

cShulstad, R.A. 325000 6581, 551110 6581, 552210 6581,830000 6581 'j

Shunk, E.R. 111210 8428, 422110 8428, 511120 8428, 870003 8428, 881000 8428 '

Shure, E. 112120 9143, 311000 9750,326000 9750, '511110 9750, 512110 8689, 632110 8689, 820000 8689, 861000 8689, 870082 8689

Sher, R. 020000 6611, 551120 6611, 870092 6611, 870094 6611,885000 6611

o 0

Sidhu, G.S. " 511120 6875, 512210 6875, 830000 6875 0

478

Siewert, C.E. 020000 8754, 310000 8550 8551 8754, 326000 6980, 422110 8250 "

Simmonds, J.R. 112930 8507 9375, 22000!) 8507 9375 9525 9924, 222000 9525 9924, 223000 8507, 713000 8507 9375, 845000 9375

rj

Simmons, E.L. 122110 7050,122210 7050, 312000 7050, 521130 7050, 522130 7050, 717000 7050, 810000 7050

I ' jjSimmons, G.L. 111600 8962, 210000 8962, 223000

// , 8793, 32A000 8885,'329000.8797 8885, 511110 6746, 512110 9730, 512210 6746, 521110 9724, 521230 8962, 551110 6746 8885, 552210 6746 8885, 610000 8797, 632110 9730/719A00 6746 8793 8797 8962, 721100 8793 8797, 722100 8793 8797, 793000 6746 8793 8797 8885 8962 9724, 820000^9730, 830000 9730, 853100 8797

„ 8885 9724, 861000 8797 8885 8962 9730

Simmons, L. 223000 6477, 719A00 6477,

Simnad, M.T. 010000 6612, 713000 6612, 719B00 6612, 810000 6612

Q

Simoen, J . - P . 020000 9196 9197, 220000 9196 9197, 430000 9196 9197

0 Simon, W.E. 020000 9213, 220000 9213, 410000

v 9213,430000 9213 .

Simonini, R. 010000 9999, 325000 6580, 329000 8092 9999, 540000 6580,,719A00 9999, 870017 6580 ,

Simons, R.L. 111220 9493, 121100 8888, 122310 - 8659, 210000 8659 8888 9493^421140 8659,

43G000 8659, 717000 9493, 719A00 8659, 810000 8888 9493, 861000 8659

Sinev, V.N. 329000 7108, 512110 7108, 861000 7108

Singh, D. 220000 6870 i?>379 8993, 511110 8993, 551110 6870, 552210 6870, 632110 8379,

a 820000 8993, 842000 8993, 845000 6870, 853100 8993 0

Singh, M.S. 122100 9538, 122200f 9538, 220000 9538, 531000 9538, 532000 9538, 610000 9538

Singh, R.S. 010000 7074, 322000 7072, 521130 7074, 713000 7074, 722100 7072, 810000 7074

«-• o

Singh, U.N. 511120 8916, 861000 8916

Sinh, N.Q. 310000 8099 0 <s Sinha (Goswami), B. 121200 7054 7059, 810000

7054 7059

Sinha, A.K. 522210 8992, 841000 8992, 853100 8992, 861000 8992, 870013 8992, 870082 8992

u Sirito, M.F. 020000 8635, ,421140 8635, 5 5 U 2 0

8635, 810000 8635" ^

Sjostrand, N.G. 321000 8479 o y

Sklyarov, V.P. 223000 6406, 719A00 6406 „

Slater, C.O. 010000 6430, 551110 9110 9855, i? 552210 9110 9855, 719B00 6430 6467 9110

„ 9855, 721200 6467, 810000 9110 9855

Slaughter,D.R. 1111109045,1112209045,410000 < 8225, 421130 6954, 421150 6954, 422140 9045^ 430000 6954 8225, 511120 6954, 870098 6954

Smathers, J.B. 111220 9287, 511120 8530, 760000 9287, 842000 8530, 843000 8530, 861000 8530?

Smatlak, D.Lvi 329000 9127, 717100 9127, 810000 9127 V

Smidt, F.A. 21001)0 8957, 810000 8957

Smith, A. 010000 6661, 122100 6659 6661,122110 6661, 713000 6661, 810000 6661, 870090 6659

Smith, D. 010000 6661, 122100 6659 6661,122110 6661, 713000 6661, 810000 6661 "870090 6659

o o

Smith, D.A. 010000 6309, 112600 '6309*; 112710 6309, 230000 6309

Smith, D.B. 711100 10064 Southworth, F.H. 717000 7006, 810000 7006

Smith, D.L. 010000 6818, 122310 6818, 421140 6818

Smith, H. " 112930 9375,220000 9375,713000 9375, 845000 9375

Smith, H.V.,Jr. 210000 8133,717000 8133,862000 8133 o

Smith, J.D.,III 122110 9934, 122310 9934

Smith, P.M. 122310 8675, 421140 8675, 430000 8675

Smith, R.D. 111210 8567, 223000 8567, 521130 8567, 522130 8567, 717000 8567, 793000 8567, 810000 8567

ft Smith, R.I. 020000 8198, 719A00 8198, 870092

8198, 870094 8198

Snead, C.L.,Jr. 210000 7008, 870041 7008, 870050 7008

Sobol', I.M. 329000 6885

Sockalingam, K.C. 112120 6747, 532000 6747, 870092 6747

Solari, P.A. 010000 6427, 719C00 6427

Soman, S.D. 010000 9568, 020000 9^68, 220000 9568

Somasundaram, S. 220000 9330, 845000 9330

Song, Y.T. 511110 7069, 511120 7069, 793000 7069, 842000 7069, 861000 7069, 870082 7069, 870098 7069 „

Soran, P.D. 122100 10066 10067, 810000 10066 10067 - . • '

Sordi, G.M.A.A. 112B00 8215, 112720^9185, 121200 8215, 329000 8215 9185, 512110 9185, 820000 8215 9185 °

Sowdon, T.L. 223000 6414, 719A00 6414

Sowertiy, M.G. 010000 8839,122100 8839, 810000 8839

Sparks, C.J.,Jr. 122200 6859, 810000 6859

Spencer, R. 521130 9542, 522130 9542, 717000 9542, 810000 9542

Spergel, M.S. 531000 6579

Spiga, G. 422110 8250

Spinrad, B.I. 010000 6343,112120 6343 6650 6874 8657, 122310 8657, 532000 6343 8657, 719A00 8657, 870092 8657, 870094 8657

Spraque, J.A. 210000 8957, 810000 8957 \\

Stacey, W.M.,Jr. 7004

,717000 7000 7004, 810000 7000

I Stallmann, F.W. '010000, 8596, 421140 6667, 430000 6667 8596 8737, 794000 8737, 810000 6667

Stamatelatos, M.G. 010000 9256, 112120 8206 8645 9256, 112200 6951, 532000 8206, 713000 8645, 719A00 8645, 810000 6951, 870090 8206, 870092 6951 8206 8645, 870094 8206 8645

Stanbridge, J.R. 620000 9276, 717000 9276

Stanica, N. 421140 6844

Stankovski, Z. 330000 9762, 551110 9762

Stapelbroek, M. 210000 9494, 717000 9494, 870013 9494

Stather, J.W. 112930 9375, 220000 9375, 713000 9375, 845000 9375

Staurin, N.V. 421150 7127, 511120 7127, 521230 7127, 853100 7127, 853200 7127, 853300 7127, 853400 7127, 853500 7127, 853600 7127, 853700 7127

480,

Steen, N.M. 010000 9129, 020000 9129, 122310 . 9129, 719A00 9129, 870090 9129, 870092 9129

/!' w

Stehle, B. 551110 69'??, 713000 6979

Stein, M. 112120 6608, 532000 6608

Steinberg, H. 112120 6903, 329000 8886, 532000 6903, 719A00 6903

Stewart, L. 111110 6590, 121100 6590, 122100 9369, 870004 9369, 870092 6590, 870094 6590

Stewart, L. (Ch.) 111110 8730, 870092 8730, 870094 8730, 870096 8730

< I

Stiller, P. 210000 8588,521130 8588,713000 8588, 719A00 8588, 760000 9285, 845000 9285, 861000 8588

Steinberg, H.A. 010000 9758 9995 9996, 329000 9758 9993 9995 9996, 719A00 9996, 721100 9996

o Steinberg, M. 010000 6600 8945, 111210 8945,

111220 6600, 717000 8945, 717500 6600, 810000 6600

u Steiner, D. 111210 7089, 717000 7089

Steinhauer, L. 010000 8944, 111210 8944, 717000 8944

Steinman, D.K. 421130 6517, 430000 6517, 521230 6517, 522230 6517, 853100 6517, 861000 6517

Stelts, M. 112500 8097, 870073 8097

Stepan, I.E. 717000 8356, 810000 8356

Stepanek, J. 326000 9017, 328000 8010, 521130 9017,551110 8010

Stephany, W. 521130 8566, 717000 8566, 810000 8566

Stevens, D.L. 112930 9926, 220000 9926, 222000 9926

Stevens, H. 111210 9421, 620000 9421, 710000 9421, 717000 9421, 810000 9421

S Stevens, H.C. 620000 9422, 710000 9422, 717000

9422, 810000 9422

Stevens, P.N. 329000 6434

Stewart, C.W. 521130 8373, 717000 8373, 810000 8373

Stinchcomb, T.G. 220000 9061

Stocklin, G. 010000 8858, 122100 8858, 210000 8858, 760000 8858, 845000 8858

Stoddart, P.G. 112710 8781, 112760 8781, 112930 8781, 222000 8781, 719AOO 8781

Stoddart, W.C.T. 111210 7089, 717000 7089

Stoever, D. 112120 9592, 719B00 9592

Stolarz-lzycka, A. 210000 9337, 841000 9337, 842000 9337, 844000 9337

Storm, E. 220000 6856, 423135 6856, 521210 6856

Straalsund, J.L. 010000 9486, 111210 9486, . 111220 9486, 210000 9486, 717000 9486, 810000 9486

Straker, E.A. 511110 6746 9192, 512110 8197 9192, 512210 6746 8197 9192, 551110 6746, 552210 6746, 632110 8197, 719A00 6746, 793000 6746 9192, 830000 8197 9192, 870007 9192, 870098 9192

Stroganov, A.A. 521110 6473, 521210 6473

Strohmaier, B. 121100 8902, 122100 8902, 870012 8902, 870013 8902, 870029 8902, 870040 8902

Strout, R.E. 410000 8225, 430000 8225

Stueker, S. 731100 8263

Stumbar, E.A. 000000 6901, 312000 6901

481,

Su, S. 111700 6466, 719B00 6388 6466, 887000 6466

Subrahmanian, G. 020000 9215 9216, 220000 9215 9216, 430000 9215 9216"

Sugai, I. 410000 8726, 424000 8726

Sugi, T. 122100 6702, 870009 6702

8411

Svensson, H. 420000 9050, 423210 9050

Sviatoslavsky, I. 717100 9866, 810000 9866

Sviatoslavsky, I.N. 329000 9127, 551110 8947, 552110 8947, 717000 8947, 717100 9127, 810000 8947 9127

Swaminathan, K. 540000 8149, 820000 8149

Swarup, J. 423230 7070, 522130 7070

Swedjemark, G.A. 114000 6703, 731200 6703, 810000 6703

Sweet, D.W. 210000 8610,421140 8610

Sze, D.K. 551110 8947,552110 8947,717000 8947, 810000 8947

Taczanowski, S. 717000 8924, 870004 8924

Tada, K. 020000 9839

Tagesen, S. 121100 8902, 122100 8902, 870012 8902, 870013 8902, 870029 8902, 870040 8902

Taji, Y. 329000 9547, 551120 6464, 554110:9547/ 718000 6387 6464, 721100 6387, 721200 6464, 731300 6464

Takahashi, A. 329000 9306 9438, 521130 9306 9438, 717000 9306 9438, 793000 9306 9438, 794000 9306 9438, 810000 9306 9438

Takata, N. 020009 9035, 423210 9035

Takeuchi, K. 210000 8589, 32A000 9144, 329000 6441, 421140 8589, 423135 8613, 423250 8613, 522120 9557, 531000 8613, 532000 8613, 551110 8589, 712000 6441, 810000 8589, 830000 9557

Takeuchi, M. 551120 6464, 718000 6387 6464, 721100 6387, 721200 6464, 731300 6464

Tamura, N. 020000 9035, 423210 9035

Tanaka, H. 760000 9822

Tanaka, R. 020000 9035, 423210 9035

Tanaka, S. 020000 9839, 122100 9366, 421130 6853, 423135 7079 8613, 423250 8613, 430000 6853 8086, 531000 8613, 532000 8613, 794000 8086, 810000 9366, 870098 6853

Sukhovitskij, E.Sh. 122100 8968, 870092 8968 n

Sund, R.E. 719B00 6388 fJJ

Sund, R.K. 111700 6466, 719B00 6466, 887000 6466

Sundaram, V.K. 330000 7065, 551110 7065, 870092 7065, 870094 7065

Sundararao, I.S. 020000 9215 9216, 220000 9215 9216,430000 9215 9216

Sunta, C.M. 423250 7081

Suntinger, G. 312000 6381, 713000 6381

Suvorov{ A.P. 112500 7113, 321000 7101, 323000 7101, 421140 7112, 421200 7113, 511110 7101, 719A00 7112, 721100 7112, 721200 7112,

(853800 7112, 861000 7101 7112, 870006 7101

Suvorov, Ya.P. 000000 7097

Suzuki, I. 329000 6438,713000 6397,721100 6438, 721200 6397

Suzuki, T. 329000 9547, 554110 9547

Svedberg, R.C. 210000 8411, 717000 8411, 870023

o 482

Tang, J.S. 329000 6425 6434,531000 7090,532000 7090, 717000 6425 7090, 721100 6425, 793000 7090, 810000 7090

Taormina, A. 329000 6396, 719B00 6396

Tarasov, V.V. 112500 7113, 421200 7113 n Tas, A. 410000 8641

Tasaka, K. 112120 9024, 532000 9024, 870092 9024

Taschek, R.F. 010000 8862, 717500 8862

Tavoni, R. 713000 6428

Taylor, A.J. V 220000 9289, 511120 9289, 820000 9289

0 • " n

Taylor, F.E. 010000 8434; 220000 8434, 222000 8434,223000 8434,230000 8434

Taylor, W.H. 210000 8610, 421140 8610

Teng, S. 329000 8687 t.

Tennery, V.J. 222000 6982, 230000 6982

Tenney, F.H. 010000 7018,717000 7018

Teofilo, V.L. 010000 9935, 32AOOO 8190, 521130 8190, 717100 8190 9868 9935, 810000 8190

Tewari, S.P. 325000 8688, 540000 8149 8688, 820000 8149 8688, 882000 8688

Thomas, C.C.,Jr. 711100 10064

Thomason, W.B. 210000 8463, 521130 8463, 717000 8463, 870003 8463

Thomassen, K.I. 010000 7014,810000 7014

Thompson, I.M.G. 020000 9214 9222, 220000 9214 9222, 430000 9214 9222

Thompson, J.K. 122310 8656 9448, 123000 8656, 521130 9448, 632200 6625, 711100 6626, 719A00 8656 9448, 793000 9448, 794000 9448, 861000 9448, 870094 9448

Thompson, W.L. 010000 10005 9978, 329000 10005 6437 9706 9978, 521130 9978, 717000 6437, 721100 10005, 810000 9978, 853100 10005, 870011 10005

Thornton, D.E.J. 112120 6412, 887000 6412

Thuong, T.Q. 112120 8871, 122100 8871, 122200 8871

Thurzo, A. 421140 6844

Thwaites, D.I. 121100 9282, 845000 9282

Till, H. 010000 8792, 223000 8792, 521110 8792, 522110 8792, 610000 8792, 719A00 8792, 722100 8792, 853100 8792, 861000 8792

Till, J.E. 112930 7092, 220000 7092 9112, 222000 6982 7092 9112, 230000 6982, 870092 7092, 870094 7092 s

Timmons, D.H. 112120 8925 v

Tkachenko, V.V. 112500 7114,^423250 7114, 511110 7114, 512210 7114, 512220 7114, 853800 7114, 861000 7114

Tobias, A. 010000 8844 9829,020000 9829,112120 ' 9829, 112710 8844, 112760 9829, 122200 8844, 810000 8844

Tochilin, E. 513120 8983, 750000 8983, 853100 8983

Todd, J.H. 122100 8147,870054 8147

Todd, T.E. 2230006413

Todreas, N. 521130 9765, 522130 9765, 717000 9765, 793000 9765, 810000 9765, 870003 9765

Todreas, N.E. 717000 8480 9146, 793000 9146

Toffolov, W.E. 210000 8887, 717000 8887, 861000 8887

Tolstykh, V.D. 121100 7121,122110 7121,810000 7121

483-

Tomlinson, E.T. 122310 6627, 312000 6627 9929, 32AOOO 9745 9929, 521130 6627, 551110 8435 9529 9745 9855, 552210 9855, 713000 8435 9529,719AOO 6627,719B00 9855,793000 8435, 794000 8435, 810000 6627 9855, 870001 6627, 870008 6627, 870013,6627, 870092 6627

W

Tone, T. 717000 7015, 810000 7015

Toppel, B.J. 32DOOO 9011, 551110 9011

Totth, B. 322000 9900, 712000 9900, 810000 9900

Trapp, J.P. 122310 6459 8865, 511120 6458, 713000 6458 8865, 810000 8865, 861000 6459, 870011 6458 6459

f.

Trapp, T.J. 112120 8657, 122310 8657 9448, 521130 9448, 532000 8657, 632200 6625, 711100 6626, 719A00 8657 9448, 793000 9448, 794000 9448, 861000 9448, 870092 8657, 870094 8657 9448

Trapp, T.J.,Jr. 112120 8511, 122310 8511, 532000

j j 8511, 870092 8511, 887000 85 I1

Travaglini, N. 713000 6428

Tripathi, A. 112120 6650 f Tripler, D.J. 423110 6706, 511120 6706, 521230

6706, 830000 6706, 861000 6706

Tromp, R.L. 112120 8724, 870094 8724

Troubetzkoy, E.S. 010000 9994 9995,020000 9997, 329000 8886 9993 9994 9995 9997, 521130 9997, 810000 9997

Trubey, D.K. 000000 7075,010000 6415 6416 7062 7075 9985, 020000 6416 7062, 220000 9532, 223000 6415, 329000 9985, 551110 9532, 552110 9532, 552210 9532, 793000 9532, 845000 9532

Trykov, L. 713000 6394, 721200 6394, 870011 6394

Trykov, L.A. 010000 8257, 421130 7119, 430000 7119, 521120 8257, 522120 8257, 731200 fc?57

Trzhaskovskaya, M.B. 112710 8044, 610000 8044

Tsofin, V.I. 421130 7110, 421140 7110, 521230 7110, 710000 7110, 719A00 7110

Tsubosaka, A. 551120 6464, 718000 6386 6464, 721100 638^1 721200 6464, 731300 6464

Tsurukin, Ju.P. 713000 6421

Tsutsui, T. 551120 6464, 718000 6387 6464, 721100 6387, 721200 6464, 731300 6464

Tsybulya, A.M. 020000 8424,521130 8424,713000 8424, 810000 8424 y!

Tsypin, S.G. 000000 7097, 112500 7114, 423250 7114, 511110 7114, 512210 7114, 512220 7114, 853800 7114, 861000 7114

Tubosaka, T. 718000 6387, 721100 6387

Tunnicliffe, P.R. 010000 6601, 111220 6601, 717500 6601, 810000 6601

Turk, E.H. 020000 9272, 887000 9272

Turland, B.D. 010000 6890, 532000 6890, 713000 6890

Turner, J.E. 112BOO 8215, 112720 9185, 121200 8215, 329000 8215 9185, 512110 9185, 820000 8215 9185

Turski, R.B. 122310 8192, 521130 8192, 713000 8192, 870090 8192, 870092 8192

O Tverdovsky, N.D. 713000 6421

Twining, B.G. 010000 7043, 717000 7043, 810000 7043

Uchida, S. 112760 6978 8915, 223000 8476, 631000 8476, 719A00 6978 8476 8915

Uckan, N.A. 010000 7016 8943, 111210 8943,? 717000 7016 8943, 810000 7016

484-

Ueki, K. 010000 10009, 311000 10009, 329000 10009 6441, 712000 6441, 721100 10009, 853100 10009

Uhl, D.L. 112760 6409,223000 6409,719A00 6409

Ullmaier, H. (Ed.) 010000 6731, 111210 6731, 111220 6731

Ullmann, J. 111220 9489, 210000 9489, 717000 9489 k

V

Ullo, J.J. 010000 9129, 020000 9129, 122310 6976\V 9129, 329000 8235 8236, 422120 6710, 511110 ' 6543, 511120 6710 6976, 719A00 6543 8235 8236 9129, 820000 6710 6976, 870090 9129, 870092 6543 8235 8236 9129,870098 6710 6976

Underwood, D.R. 112710 8973, 222000 8973, 223000 8973, 719AOO 8973

United Nations Scientific Committee on the Effects of Atomic Radiation 010000 6957, 220000 6957

o Uotila, I.K. 420000 9049, 423300 9049

Usachev, L.N. 010000 8843, 122310 8843, 713000 8843, 887000 8843

Usachev, P.N. 122110 6662, 122310 6662, 713000 6662, 810000 6662

Usanov, V.I. 713000 6421

Utkin, V.A. ,422140 7124, 430000 7124, 521130 7124

Uwamino, Y. 9142

Vaccari, M. 8871

Vacek, M. 9456

Vadiwala, R. 9216

Vaidyanathan, R. 010000 7074, 32AOOO 8998, 322000 7072, 330000 6453, 521130 7074, 713000 7074, 722100 7072, 810000 7074

Valenta, V. 112120 6638, 112930 8821, 121100 6638, 22300e 8821, 719A00 8821, 810000 8821, 870092 6638

Vallario, E.J. 010000 6416,020000 6416 v

O Vallis, D.G. 010000 8844, 112710 8844, 122200

8844, 810000 8844 D

Van Antwerp, W.R. 121100 6744, 210000 6744, 870019 6744

Van Atta, C.M. 010000 6599.111220 6599, 717500 6599, 810000 6599° ,

van der Lugt, G. 020000 9207,220000 9207,430000 9207 °

van Heerden, I.J. ",, 010000 8842, 112400 8842, 112500 8842, 112600 '8842, 122200 8842, 810000 8842

Van Heusden, H. 717000 6423

Van Konynenburg, R.A. > 210000 7008,870041 7008, 870050 7008

Van'kov, A.A. 020000 8424, 122110 8114, 521130 8424, 713000 8114 8424, 81GOOO 8114 8424

Vandervoort, R.R. 210000 8957, 810000 8957

Varela, D.W. 312000 8509, 521130 8509, 810000 8509

Varma, M.N. 020000 9036, 423210 9036

Vasilyev, R.D. 010000 8590, 020000 8590, 421130 8625, 421140 8590 8625, 511120 8625

Ventura, A. 112120 8871, 122100 8871 9268, 122200 8871, 870094 9268

Verbinski, V.V. 210000 8753, 870014 8753

511120 9142, 512110 9142, 870006

112120 8871, 122100 8871, 122200

/ j

210000 9456, 719A00 9456. 861000

020000 9216, 220000 9216, 430000

485,

Verdant, R. 421150 8609

Verghese, K. 430000 8391

Vergnaud, T. 010000 10008, 329000 10008

Verna, B.J. 010000 6399, 223000 6399, 719A00 6399

Verschuur, K.A. 111210 9016, 122310 9016 9654, 312000 9654, 717000 9016 9654, 810000 9654

Verspuy, C.A. 410000 8641

Veselkin, A.P. 325000 7098, 421150 7127, 511120 7127, 521130 7098, 521230 7127, 522130 7098, 632110 7098, 820000 7098, 853100 7127, 853200 7127, 8S3300 7127, 853400 7127, 853500 7127, 853600 7127, 853700 7127

Vespalec, R. 210000 9455, 511120 9455, 719C00 6253, 861000 9455

Veverka, O. 112930 8821, 223000 8821, 719A00 8821,810000 8821

Vienot, R. 511120 6458,713000 6458, 870011 6458

Vikin, V.A. 421130 7110, 421140 7110, 521230 7110, 710000 7110, 719A00 7110

Viktorov, A.A. 421200 7115, 522210 7115, 610000 7115, 820000 7115, 861000 7115, 870013 7115, 870082 7115

>1 Vogelsang, W.F. 010000 7042 9388, 112760 7042,

210000 7042, 223000 7042, 329000 9127, 521130 7042 8135, 522130 7042 8135, 531000 7042, 532000 7042 8135, 711100 9388, 717000 7042 8135, 717100 9127 9388 9636, 810000 7042 9127

Vogt, D.G. 721100 6465,722100 6465 V

Voillcque, P.G. 112930 8644, 719A00 8644

Vonach, H. 010000 6820, 121100 8902, 122100 8902, 421140 6820, 870012 8902, 870013 8902, 870029 8902, 870040 8902

Vondy, D.R. 312000 6629,325000 6629 6943 8786, 551110 6629 6943, 713000 6629 6943 8786, 810000 6629 6943

Voropaev, A.I. 020000 8424, 122110 8114, 521130 8424, 713000 8114 8424, 810000 8114 8424

Vorotyntsev, M.F. 122110 8114, 713000 8114, 810000 8114

( -

'' Voskresenskiy, Ye.V. 421150 7127, 511120 7127, 521230 7127, 740000 7126, 853100 7127, 853200 7126 7127, 853300 7127, 853400 7127, 853500 7127, 853600 7127, 853700 7127, 853800 7126

Vozyakov, V.V. 122110 8114,713000 8114,810000 8114

Vronich, J .J . 424000 9260, 711100 9260, 870094 9260, 870095 9260

613000 8912 Viragh, E. 220000 8995, 521210 8995,522210 8995 Vukanovic, R.

Vlasov, M. 010000 6819, 122100 6819, 421140 6819

Vlasov, M.F . 122310 8675, 421140 8675, 430000 8f>75

Vlasov, M.F . (Ed.) 010000 6808, 111110 6808, 122200 6808, 421140 6808, 430000 6808, 511120 6808, 810000 6808

> v C V'

Wadachi, Y. 230000 8531

w ^ d i f i r c oioooo 8191,122310 8191,325000 9072, 521130 9072, 713000 9072, 870090 8191, 870092 8191

Waganer, L.M. 717000 7010, 810000 7010

Wagner, E.B. 112930 8436, 222000 8436, 870092 8436

486-

Wagner, M.R. 310000 9751, 32AOOO 9751, 325000 9751, 551110 9751

Ward, D.L. 410000 8414, 421200 8414, 424000 8414 " D

Wagner, S. 220000 9382, 420000 9382, 430000 9382

Wagner, S.R. 010000 6811 6826 6827, 020000 6827, 111110 6827, 111220 6827, 410000 6827, 420000 6811,540000 6826 %

Wagschal, J .J . 122110 8514, 122210 8514, 122310 8653, 321000 8393, 521130 8653, 713000 8653, 717100 9736, 810000 8514 8653

Wahsweiler, H.G. 719D00 6398, 870006 6398

Wainio, K.M. 223000 8795, 32A000 8795, 719A00 8795, 721100 8795, 722100 8795

Wakabayashi, H. 111110 6832, 410000 6832, 421130 6832, 421140 6832, 511120 6832, 713000 6397, 721200 6397

Waker, A.J. 111220 9291, 220000 9291, 760000 9291

Walker, J. 511120 6867, 820000 6867

Wallace, J.M. 111210 8428, 422110 8428, 511120 8428, 870003 8428, 881000 8428

' I

Wallace, O.J. 112120 9143

Walsh, P.J. 112760 9376, 220000 9376, 610000 9376, 711100 9376, 845000 9376

Walters, W.F. 32A000 9747, 551110 9747

Waluschka, E. 010000 9996, 329000 9996,719A00 9996, 721100 9996

Wang, C.C. 551110 8947, 552110 8947, 717000 8947, 810000 8947

Wang, C.P. 020000 9039, 220000 9039, 423210 ' 9039, 423240 9040, 430000 9039 9040

Wang, H.H. 325000 6975,551110 6975

Ward, J.T.,Jr. 122210 6435, 329000 6435 H J )

Warkentin, J.K. 329000 8804, 719AOO 8804, 721100 8804, 810000 8804

Warman, E.A. 223OOO'''014, 719A00 6414

Warner, G.G. 113100 6698, 220000 6698 9394, 423210 6698, 423250 6698, 553120 6698,

^ 845000 6698

Wasastjerna, F. 310000 9250

Wassef, W.A. 310000 9064

Wasson, O.A. 020000 8247, 410000 8247, 421160 8247

Waterman, M.S. 329000 6520

Watson, A . P . 1 1 2 7 1 0 8783, 112930 9027, 220000 8456 8783 9027, 222000 9027, 223000 8456 8783, 632300 8456, 711100 8783, 845000 8783, 861000 8456

Watson, J.W. 111220 9489, 210000 9489, 717000 9489

is

Watson, R. 329000 9127, 717100 9127, 810000 9127

Watson, S.B. 220000 8974, 845000 8974

Watt, D.E. 121100 9282,845000 9282

Wattecamps, E. 122100 8148, 882000 8148

Watts, H.L. 010000 8943, 111210 7089 8943, 32A00tf,8563, 521130 8563, 717000 7089 8563 8943, 810000 8563

ii Wayland, J.R. 112930 6538, 220000 6538, 222000

6538

Weaver, H. 112120 6696 7046 8030 8031, 221000 6696, 421200 7046, 430000 6696 7046, 532000 6696, 610000 8030 8031, 794000 6696, 870092

! 7046,870094 6696 8031

487,

Webb, G.A.M. 010000 8434, 220000 8434, 222000 8434, 223000 8434, 230000 8434

Weber, C.F. 312000 9316, 719A00 9316

f v • <h, C C . 122110 9933,122210 9933,711100 Y,„. ^ / 9 9 3 3 , 793000 9933, 794000 9933, 810000 9933

ti 0

Webster, W.M. 1112109252,112400 9252,112500 9252, 122310 9252

Wehring, B.W. 122310 6463,312000 8662,32A000 8662, 430000 6341 6463 9729, 511110 8662, 793000 8662, 794000 6463 8662 9729, 870041 6463 8662, 870098 6463

Weinberg, A.M. 010000 8512, 220000 8512

Weisbin, C.R. 010000 8650, 020000 6419 7131, 122110 6419 8514 8975, 122210 8514, 122310 6695 6872 7131 8193 8650 8652 8975, 311000 6695, 312000 6382 6695 7131 8650 8652, 32A000 7131 8652, 521130 8193 8652, 713000 6382c8193 8652, 719A00 6695, 794000 8193 8652, 810000 71318514 8975, 861000 6382, 870011 6382, 870092 6695, 870094 6695

Weise, L. 210000 8186, 421140 8186, 810000 8186

Weller, R.A. 112710 8781, 112760 8781, 112930 8781, 222000 8781, 719A00 8781

Wells, A.H. 111220 8022, 220000 8022, 329000 8022, 760000 8022 '

Wells, M.B. 210000 6609, 551110 6609, 719A00 6609, 810000 6609, 861000 6609

Wells, W.M. 111210 7089, 717000 7089

Weng, P. 423250 6566, 853100 6566

Werle, H. 410000 8595, 421120 8595, 421130 8595, 430000 8595, 512210 6873, 512220 6873, 717000 6877, 861000 6873, 870003 6877, 870098 6873

Werner, R.W. 111210 7089, 717000 7089

West, D. 010000 8852,111220 8852, 870006 8852, 870012 8852, 870013 8852, 870014 8852

0 West, J.T.,III 010000 10007,32AOOO 6440,329000

10007 "6440, 532000 6440 6451, 719A00 6440 6451 " • "

Westfall, R.M. 330000 9763, 719B00 9763, 794000 9763 , ^

Weston, L.W. 122100 8147 8874, 87UU94 8147 8874 "

Whalen, J . 122100 6659, 870090 6659

Wheeler, F.J. 422200 8971, 424000 8971, 521130 9123, 522130 9123, 717000 9123, 719A00 8971, 810000 8971 9123

White, A.D. ° 010000 8780,220000 8780 0

White, I.F. 222000 9849, 230000 9849, 887000 9849 , , " 0

White? J.E. 020000 6419, 122110 6419 8514, 122210 8514, 810000 8514 (i

White, J.R. 122310 8668, 123000 8668, 551110 9314, 713000 9314, 793000 9314, 794000 9314, 810000 9314

White, T.A.,Jr. 111220 8986, 750000 8986

Whitley, J.B. 210000 8133, 717000 8133, 862000 8133

Whitmarsh, C.L. 532000 6451, 719A00 6451

Whitmire, C.,Jr. (Eds.) 010000 8561 8562^111210 8561 8562, 717000 8561 8562

Whitty, W.J. 711100 10064

Wichner, R.P. 112120 6944 8455, 112760 10074, 210000 6944, 421200 6944, 719B00 10074 6944 8455, 810000 6944, 870006 10074

Wielopolski, L. 430000 8391

488

Wienke, B.R. 121200 6725, 122110 6691, 32A000 9066, 32A100 6242 8755, 514110 6242, 521130 6691 8278, 522130 6691 8278, 717000 6242 6691, 793000 6691, 810000 6691 8278

Wiese, H.W. 717000 6877,870003 6877 i.

Wiese, W.H. 010000 8850, 122100 8850, 711100 8850, 712000 8850, 810000 8850

it / '

Wiffen, F.W. 111210 7089, 210000 7007 9029, 717000 7089 9029, 793000 9029, 810000 9029, 870042 7007

Wilcox, T.P. 010000 9231 9232, 020000 9231 9232, 410000 9231 9232, 511120 9231 9232, 551120 9231 9232

Wild, H. 112120 9593,112930 9469, 719A00 9469

Wilkes, P. 210000 8133 8957 9387, 717000 8133, 810000 8957, 862000 8133, 870029 9387, 870079 9387

Willenberg, H.J. 112760 8459, 112930 8459, 220000 8459, 223000 8459, 521130 8459, 531000 8459, 532000 8459, 717000 8459, 810000 8459

Williams, D.C. 312000 8509, 521130 8509, 810000 '8509

Williams, J.G. 020000 6830, 410000 6830 6837 6838, 421130 6830, 421140 6830 6838, 422130 6837, 511120 6830 6837 6838, 810000 6838

Williams, J.M. 010000 7036 8876, 210000 7036 8876, 717000 7036 8876, 810000 8876

Williams, L.R. 010000 6430, 551110 9855, 552210 9855, 719B00 6430 9855, 810000 9855

Williams, M.L. 122310 6695 8668, 123000 8668, 230000 8033, 311000 6455 6695, 312000 6695 8119 8751 9551, 551110 8033, 713000 6373 8033, 719A00 6695, 793000 8033, 794000 8033, 870092 6695, 870094 6695, 887000 8033

Willingham, C.E. „ 010000 9935, 717100 9935

Wilson, W.B. 112120C845, 122110 6690 8115, 421000 6690, 511120 8530, 521130 6690, 532000 9845, 551110 6690, 719A00 9845, 760000 6690, 793000 8115 9845, 810000 6690 8115, 842000 8530, 843000 8530, 861000 8530

Wolfer, W.G. 329000 9127, 717100 9127, 810000 9127

Wong, C. 111210 9252,112400 9252,112500 9252, •• 122310 8859 9252, 511110 6468, 511120 6875

8859, 512210 6875, 512220 8859, 717000 8859, 820000 6468, 830000 6875, 853100 6468, 861000 6468, 870029 8859, 870041 8859, 870090 8859, 870092 8859

Woodruff, G.L. 010000 9935, 521130 7027, 717000 8207, 717100 7027 9935, 793000 7027, 810000 7027

Woods, T.J. 551110 6678, 717000 6678

IS // Woolson, W.A. 512110 8197,512210 8197,632110 »

8197, 830000 8197

Woznicki, Z. 325000 9174

Wrazel, J. 551110 8947, 552110 8947, 717000 8947, 810000 8947

Wright, H.A. 112B00 8215, 112720 9185, 121200 8215, 329000 8215 9185, 512110 9185, 820000 8215 9185

Wright, H.L. 421140 8096, 430000 8096, 882000 8096

Wright, R.Q. 020000 6419, 121100 8401, 121200 8401, 122110 6419 8401 8514, 122210 8401 8514, 220000 8401, 531000 8401, 532000 8401, 794000 8401,810000 84018514

Wright, S.A. 312000 8654 8670,329000 8654 8670, * 430000 8654 8670, 551110 8654, 810000 8654

Wu, C.H. 112120 6874

489 \ \

Wu, T. 122310 8663, 312000 8663, 32A000 8663, 521130 8663, 551110 8663, 717000 8663, 810000 8663

Wyckoff, H.O. 010000 9166, 020000 9217,121100 9166, 121200 9166, 220000 9217, 420000 9166

Wyckoff, H.O. (Ch.) 010000 9165, 220000 9165

Wyckoff, W.G. 111220 9489, 210QQO 9489,717000 9489

Ya'arl, A. 122310 8653, 521130 8653, 713000 8653, 810000 8653

Yaari, A. 717100 9736

Yefimenko, B.A. 810000 7109

329000 7109, 722100 7109,

Yefimov, Ye.P. 329000 7117, 532000 7117, 861000 7117;; 870082 7117

Yegorov, Yu.A. 010000 7118,121100 7121,122110 7121, 420000 7118, 421120 7122 7123, 421130 7110 7116, 421140 7110, 421150 7,118 7120 7127, 430000-7122 7123, 511120 7118 7120 7122 7123 7127, 521230 7110 7116 7127, 610000 7116, 710000 7110, 719A00 7110,, 740000 7126, 810000 7116 7121 7122 7123, 853100 7127, 853200 7126 7127, 853300 7127, 853400 7127, 853500 7127, 853600 7127,

• 853700 7127, 853800 7126, 861000 7118 7120, 870013 7120, 870022 7120

Yagi, H. 010000 6842, 020000 6842, 421140 6842, 511120 6842 O

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Yamaji, A. .210000 8589, 421140 8589, 551110. 8589, 551120 6464, 718000 6464, 721200 6464, 731300 6464, 810000 8589

Yeh, H.T. 010000 8943,111210 8943,717000 8943

Yeivin, Y. 122110 8873 9098, 122310 8653 8672 8873 9098, 321000^3393, 421140 8672, 521130 8653, 713000 8653, 810000 8653, 861000 8672

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Yamaji, Y. 718000 6387, 721100 6387 Yiftah, S. 122100 6572 9834, 870096 9834

Yamakoshi, H. 329000 10010 6441, 711100 10010, 712000 6441, 810000 10010

Yoder, R.C. 020000 9528, 113100 9528, 220000 9528, 845000 9528

Yamamoto, S. 010000 6842, 020000 6842, 421140 Yoshida, M. 511120 9142, 512110 9142, 870006 6842,511120 6842 <, 9142

Yamane, Y. 310000 9402 Yoshida, T. 325000 9403, 713000 9403

Yamano, N. 020000 9839 Youell, F.P. 223000 6400, 719C00 6400

Yamauchi, M. 020000 9839, 329000 6438, 521130 9840, 717000 9840, 721100 6438, 810000 9840

Young, J.C. 421130 6517, 430000 6517, 521230 6517, 522230 6517, 853100 6517, 861000 6517

Yang, T.L. 111110 8798, 223000 8798, 329000 8798, 620000 8798, 719A00 8798, 721100 8798, 721200 8798, 722100 8798

Yarnell, J.L. 112120 8510, 532000 8510, 870092 8510,870094 8510

Yasuda, M. 853400 9702|

Young, P.G. 122100 8772 9267 9369, 122200 8772, 810000 8772, 870004 9369, 870094 9267

Youngblood, J.E. 121100 6744, 210000 6744') 870019 6744

Youngdahl, C.K. 620000 9422, 710000 9422, 717000 9422, 810000 9422

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Youssef, M.Z. 010000 9324, 122310 8818, 312000 8818, 329000 9127, 521130 8816, 717100 8467 8816 9127 9324 9636 9820, 793000 8816, 794000 8816,810000 8467 8816 9127

Yusa, H. 112760 6978 8915, 223000 8476, 631000 8476, 719A00 6978 8476 8915

Zaalishvili, G.G. 740000 7126, 853200 7126, 853800 7126

Zabrodskaya, A.S. 122100 8113, 870001 8113

Zank, G. 111210 10154, 717000 10154

Zee, R. 210000 9387, 870029 9387, 870079 9387

Zero, S. 122310 6573, 861000 6573

Zharkov, V.F. 122100 8968, V>70092 8968

Zharkov, V.P. 421120 7122 7123, 421130 7116, 430000 7122 7123, 51X120 7122 7123, 521230 7116, 610000 7116, 810000 7116 7122 7123

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Zhuravlyov, V.l. 512220 6472, 521110 6473, 521210 6473, 820000 6472, 861000 6472, 870082 6472 1,5

Zienkiewicz, O.C. 32C000 8931

Zijp, W.L. 010000 8597, 111110 8642, 122100 9574 9575, 122110 6847 8637 8640, 122310 681,6, 123000 9574 9575, 410000 8641, 421140 6816 6829 6846 6847 8412 8597 8637 8638 8639 8640 8642 9574, 421150 9575, 422110 8412, 430000 6846 8412 8597 8638 8639, 511110

V 6846, 511120 6816 6829 8639, 794000 9574,-, 810000 6816 9574 9575, 870092 6816, 870098 6816

Zill, H.W. 220000 9382, 420000 9382, 430000 9382

11 Zimmerman, M.G. 521130 6205, 522130 6205,

712000 6205, 810000 6205

Zobel, W. 7,10000 8803, 719A00 8803, 721100 8803, 810000 8803

Zoetelief, J . 020000 9219, 220000 9219 9293, 421150 9293, 430000 9219, 511120 9293 ' V

Zolotukhin, V.G. 329000 7108 7109, S12110 7108, 722100 7109, 810000 7109, 861000 7108

Zrlanszky, K. 020000 9202, 220000 9202, 430000 9202

Zsolnay, E.M. 122110 6899, 421140 6899, 430000 6899, 521230 6899, 719A00 6899, 810000 6899

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Zumach, W. 722100 6395, 853100 6395

Zupancic, M. 613000 8912

Zurkinden, A. 230000 9639

Zvonarev, A.V. 713000 6421 Zwilsky, K.M. 010000 7036 8956, 111210 8956,

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I N T E R N A L D I S T R I B U T I O N

O R N L / R S I C - 5 / V 7

1-2. Central Research Library 3. ORNL-Y-12 Technical Library

Document Reference Section 4-5. Laboratory Records Department

6. /Laboratory Records, O R N L R.C. 7. KORNL Patent Office

8-9. M S. Abbott • 10. Ryt G. Alsmiller 11. DJ E. Bartine 12. G. F. Flanagan u

13. F. C. Maicnschein 14. R'. W. Peelle

15. H. Posting, 16. M l W. Rosenthal 17. M. J. Saltmarsh 0

18. D. B. Trauger 19. C. R. Weisbin , 20. A. Zucker 21. P. W. Dickson, Jr. (Consultant) 22. J. C. Kouts (Consultant) 23. W. B. Lowenstein (Consultant) 24. R. Wilson (Consultant)

25-99. RSIC Distribution ,,

E X T E R N A L ' D I S T R I B U T I O N 0 ct ' S •

100. David L. Auton, Defense Nuclear Agency, Washington, DC 20305 101. S. Berk, Office of Fusion Energy, U.S. DOE, Washington? DC 20545 " nu a 102. A. B. Chilton, University of Illinois, Urbana, IL 61801 ' ' 103. A. Foderaro, Penn State University, University Park.iPA 1,6802 104. H. Goldstein, Columbia University, 520 W. 120thtSt?;'New^York, N Y 10027 105. P. B. Hemmig, Office of Reactor Research and Technology^U.S. DOE, Washington, DC 20545 106. R. J. Howerton, Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, CA 94550

107-108. Los Alamos National Laboratory, P.O. Box 1663, Los^lamor,, N M 87545 K. Lathrop 0

0 - " . , W. Thompson O § P"T/

I -o o O o V ,. o

109. O. Ozcr, Electric Power Research Institute, 3412 Hillview Ave.,(Palo Alto, CA 94304 110. Lester, Price, ORO, Federal Bldg., Oak Ridge, TN 37830 111. J. Renken, Sandia National Laboratories, P.O. Box 9336, Albuquerque, N M 87185 112. Yo Taik Song, Office of Military Applications, U.S. DOE, Washington, DC 20545 ( J

113. Myrna,Steele, U.S. Nuclear Regulatory Commission, Washington, DC 20545 114. Paul Stevens, Nuclear Engineering Department, University of Tennessee, Knoxville, TN 37916 115. Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC

20545, Attn-. Director ° o 116. Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington. DC 0

20545, Attn: Director 117-118. Technical Information Center, U.S. DOE, Oak Ridge, T N 37830

- 119. National Technical Information Service, Department of Commerce, Springfield, VA 22161 120. Office of the Assistant. Manager, Energy Research Development, DOE-ORO, Oak Ridge, T N 37830 121. Patent Office, U.S. DOE, Oak Ridge, T N 37830

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