Precharacterization Report for - Nuclear Regulatory Commission

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NUREG/CR-i')77 PNL-3156 R-3 . | Precharacterization Report for ; instrumented Nuclear ) Fuel Assembly IFA-513 E. R. Bradley M. E. Cunningham J. L. Daniel N. C. Davis D. D. Lanning R. E. Williford , November 1979 Prepared for The U.S. Nuclear Regulatory Commission under a Related Services Agreement with the U.S. Department of Energy Contract EY-76-C-06-1830 Fin No. B-2043 Pacific Northwest Laboratory Operated for the U.S. Department of Energy by Battelle Memorial Institute 1 ' 7 OBattelle E . . I THIS DOCUMENT CONTAINS 8000270022 . _ _ . __ _. .. .- _ _ _ . _ - _ - . .-

Transcript of Precharacterization Report for - Nuclear Regulatory Commission

NUREG/CR-i')77PNL-3156

R-3

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Precharacterization Report for ;

instrumented Nuclear )Fuel Assembly IFA-513

E. R. BradleyM. E. CunninghamJ. L. DanielN. C. DavisD. D. LanningR. E. Williford ,

November 1979

Prepared forThe U.S. Nuclear Regulatory Commissionunder a Related Services Agreementwith the U.S. Department of EnergyContract EY-76-C-06-1830Fin No. B-2043

Pacific Northwest LaboratoryOperated for the U.S. Department of Energyby Battelle Memorial Institute

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OBattelle E.

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THIS DOCUMENT CONTAINS

8000270022. _ _ . __ _. .. .- _ _ _ . _ - _ - . .-

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NOT|CE

This report was prepared as an account of work sponsored by the United States Government. Neither theUnited States nor the Department of Energy, nor any of their employees, nor any of their contractors,subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liabilityor responsibility for the accuracy, completeness or usefulness of any information, apparatus, product or processdisclosed, or represents that its use would not infringe privately owned eights.

The views, opinions and conclusions contained in this report are those of the contractor and do notnc<essarily represent those of the United States Government or the United States Department of Energy.

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! PACIFIC NORTHWEST LABORATORY'

operated byBATTELLEfor the

! UNITED STATES DEPARTMENT OF ENERGYUnder Contract EY-76-C-06-1830

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NUREG/CR-1077PNL-3156

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PRECHARACTERIZATION REPORT FOR INSTRUMENTEDNUCLEAR FUEL ASSEMBLY IFA-513

E. R. BradleyM. E. CunninghamJ. L. DanielN. C. DavisD. D. LanningR. E. Williford

November 1979

Prepared forThe U.S. Nuclear Regulatory Commissionunder a Related Services Agreementwith the U.S. Department of EnergyContract EY-76-C-06-1830Fin No. B-2043

Pacific Northwest LaboratoryRichland, Washington 99352

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ABSTRACT

This report is a resource document covering the rationale, design, fabri- ;j ,

| cation, and preirradiation characterization of instrumented fuel assembly || IFA-513. This assembly is being irradiated in the Halden Boiling Water Reac- '

' *tor in Norway as part of the Verification of Steady-State Codes Program con-ducted by Pacific Northwest Laboratory and sponsored by the Fuel Behavior.

Research Branch of the U.S. Nuclear Regulatory Commission. Data from this

i assembly will be used to better understand light water reactor fuel behaviorunder normal operating conditions.

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ACKNOWLEDGEMENT ,

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The authors wish to acknowledge the Halden Project staff for their time, ,

effort and funds expended upon the design and fabrication of IFA-513. R. W.

Miller, the NRC representative at Halden, is appreciated for his efforts in*overseeing installation and operation of assembly and providing information

for this report.

We also acknowledge the sponsorship of Dr. W. V. Johnston and H. H. Scottof the Fuel Behavior Research Branch, U.S. Nuclear Regulatory Commission.

We would like to thank the following from Pacific Northwest Laboratory:

j C. R. Hann for his initial guidance regarding this assembly, C. L. Mohr forhis ongoing review and advice, and finally C. M. Hagen for her editing'

assistance.

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CONTENTS

OABSTRACT iii. . . . . . . . . . . . .

ACKNOWLEDGEMENT iv. . . . . . . . . . .

a FIGURES vi. . . . . . . . . . . . .

TABLES viii. . . . . . . . . . . .

1.0 INTRODUCTION 1. . . . . . . . . . .

2.0 OBJECTIVES AND RATIONALE . 3. . . . . . . .

2.1 CORRELATION WITH IFA-431/432 3. . . . . . .

2.2 IFA-513 GAS MIXTURES 4. . . . . . . .

2.3 STATISTICAL ANALYSIS 5. . . . . . . .

2.4 TRANSIENT TESTING 6. . . . . . . . .

3.0 IFA-513 DESIGN AND ASSEMBLY FABRICATION . 7. . . . .

3.1 R00 DESIGN 7. . . . . . . . . .

3.2 ASSEMBLY DESIGN 11. . . . . . . . .

3.3 FUEL R0D FABRICATION 15. . . . . . . .

4.0 FUEL FABRICATION AND CHARACTERIZATION 21. . . . . .

4.1 FUEL FABRICATION 21. . . . . . . . .

4.2 FUEL CHARACTERIZATION 25. . . . . . . .

Experimental Procedure 27. . . . . . . .

Porosity Evaluation . 28. . . . . . . .

Grain Size Evaluation 35. . . . . . . .

Conclusions 39. . . . . . . . . .

5.0 ASSEMBLY OPERATION 41. . . . . . . . . .

5.1 STEADY-STATE OPERATION 41. . . . . . . .

5.2 SPECIAL OPERATIONS 42. . . . . . . . .

REFERENCES 45. . . . . . . . . . . .

APPENDIX A STACKING ARRANGEMENTS FOR IFA-513 FUEL RODS . A-1. . .

APPENDIX B CLADDING CHARACTERIZATION B-1. . . . . . .

APPENDIX C FUEL CERTIFICATION AND FABRICATION C-1. . . . .o

APPENDIX D PELLET DATA D-1. . . . . . . . . .

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FIGURES

2.1 Distribution of Responses from Single Fuel Rod Design 5. . . ,

2.2 Examples of Bias Between Modeling and Experiment 6. . . .

3.1 Schematic Arrangement of Fuel Rod for IFA-513 10 a. . . .

3.2 Schematic Design of IFA-513 12. . . . . . . .

3.3 HBWR Core Loading No. 33 from January 1979 13. . . . .

3.4 Orientation of IFA-513 Relative to Core Centerline 14. . .

3.5 Arrangement of Fuel and Instruments Relative toReference Axial Thermal Flux Profile 14. . . . . .

3.6 Photographs of Completed Assembly Showing Various Featuresand Instrumentation . 16. . . . . . . . .

3.7 Details of Plenum Spring . 18. . . . . . . .

4.1 PNL Visual Standards for U02 Fuel Pellets 25. . . . .

4.2 Microstructure of U02 Fuel Pellets for IFA-513and IFA-431/432 28. . . . . . . . . .

4.3 Pore Size and Volume Distribution for 95% TD StableU02 Fuel Used in IFA-513 and IFA-431/432 30. . . . .

4.4 Microstructure of UO2 Powder Used for FabricatingIFA-513 Pellets 32. . . . . . . . . .

4.5 General Porosity Characteristics of 95% TD Stable U02Pellets Used in IFA-513 33. . . . . . . . .

4.6 Typical Porosity Characteristics of UO2 Pellets Usedfor IFA-513 34. . . . . . . . . . .

4.7 Summary of the Radial Distribution of Pore Size and -

Volume 36. . . . . . . . . . . .

! 4.8 Radial Distribution of-the Pore Population as aFunction of Pore Size 37. . . . . . . . .

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4.9 Variation in Grain Size for 95% TD Stable U021 Pellets Used in IFA-431/432 38. . . . . . . .

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4.10 Sunnary of Radial Variation in Grain Size forIFA-513 and IFA-431/432 39. . . . . . . . .

* 5.1 Special Operational Procedures for IFA-513 43. . . . .

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TABLES,

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i 3.1 IFA-513 Rod Design Parameters . 8 -. . . . . . .

i 3.2 As-Fabricated Dimensions and Variances 9. . . . . .

4.1 IFA-513 Pellet Specifications and Required '-

Characterization 23. . . . . . . . . .;

4.2 Summary of IFA-513 Chemical Analysis 24. . . . . .,

| 4.3 Sumary of IFA-513 Fuel Pellet Specifications ,

and Inspection . 26. . . . . . . . . .,

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4.4 Sumary of Calculated Pore Distributions From all; Data for Each Halden Fuel Assembly . 29. . . . . .

4.5 Pore Distribution in 95% TD Stable U02i Fuel for Assembly IFA-513 31. . . . . . . .

4.6 Grain Size of As-Sintered Pellets 35. . . . . . .

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1.0 ,TNTRODUCTION

*If a loss-of-coolant accident (LOCA) should occur in a light water reac-

tor (LWR), the thermal stored energy (short term) and decay heat (long term)' of the fuel rods become the driving forces for fuel damage. To assess the.

amount of energy that would be present in the core of a commercial LWR should

| a LOCA occur, the U.S. Nuclear Regulatory Commission (NRC) must rely on com-puter codes. These codes are designed to account for fuel type, fuel and clad-

! ding dimensions, coolant conditions, power level, operating history, and a hostI of other considerations. However, these codes are only as reliable as the data

bases that are used to build them and to verify their results.,

The Experimental Support and Development of Single-Rod Fuel Codes Programwas established primarily to develop a well-characterized data base to assuresuch reliability. The program was begun at Pacific Northwest Laboratory(PNL)(a) in 1974 by the Fuel Behavior Research Branch of the NRC. The datagenerated under this program is used in the development and verification ofthe NRC audit codes GAPCON-THERMAL and FRAPCON (Lanning et al., January 1978;

Berna, Bohn and Coleman, November 1978).'

To date, this program has built two instrumented fuel assemblies and;

irradiated them in the Halden Boiling Water Reactor (HBWR) located in Halden,Norway. The first of these assemblies, IFA-431, was irradiated from June 1975 '

i to February 1976 and obtained an assembly average burnup of 389 GJ/kg1

(4.5 GWd/ MTM). The second assembly, IFA-432, is identical in design, and itsirradiation began in December 1975. This assembly is still in the reactor, andit is providing data at high fuel burnup.ID) The data obtained from both ofthese assemblies has been consistent, and it has been useful for verifying

' existing models, developing new models, and developing new techniques foranalysis of fuel rod data.

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To continue the work begun with IFA-431/432, and to fill in information,

gaps left by those assemblies, a third assembly has now been built and wascharged into the HBWR in November 1978. This assembly, designated IFA-513, is

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(a) PNL is operated for the Department of Energy by Battelle Memorial Institute.(b) As of May 1979, the assembly average burnup for IFA-432 was 1788 GJ/kgU

(20.7 GWd/MTM).

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a joint venture of the Halden Reactor Project and NRC/PNL. Halden is provid-ing the assembly design, assembly fabrication, and irradiation services. NRC/

PNL is providing the fuel and cladding, postirradiation examination, and anal- *

ysis of the expertinental data.

The assembly, IFA-513, is designed to meet a number of needs. First, two''

rods tre filled with gas mixtures that were not used in IFA-431/432. Theserods will provide additional data on the question of fuel temperatures andstoied energy as a function of fuel rod design. Next, since statistical dif-

ferences can occur between supposedly identical fuel rods, IFA-513 containsthree identical rods to be used in evaluating this question. Third, all rodsare equipped with continuous response gas pressure transducers to evaluate fis-sion gas release. Next, continuing de!elopment of transient temperature anal-ysis techniques will permit evaluation of the changing behavior of the fuelrods. And finally, the rods will be shipped to the Power Burst Facility atIdaho National Engineering Laboratory for additional testing.

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This report is a repository of information on the objectives, design, andfabrication of IFA-513. Since this assembly shares some design and materialswith IFA-431/432, we will reference the precharacterization repcrt forIFA-431/432 (Hann et al., 1977),(a) where appropriate, rather than repeatthe information here.(b) The information included in this report isorganized as follows:

Section 2 - Objectives and rationale for the assembly

Section 3 - Design, instrumentation, and fabrication of the assembly

Section 4 - Fabrication and characterization of the fuel used in theassembly

i Section 5 - Operation of the assembly

Appendices - Pertinent data

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(a) Hereafter referred to as BNWL-1988.(b) An example: The cladding of all three assemblies is from the same

batch. The documentation of the cladding may be found in Appendix A -

of BNWL-1988.

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2.0 OBJECTIVES AND RATIONALE

When the Experimental Support and Development of Single-Rod Fuel Codes*

Program (previously called the Verification of Steady-State Codes Program) wasbegun in 1974, several areas in the LWR steady-state data base were deficient.,

Of particular concern was a lack of the following; well-defined temperature /power data, information on temperature effects of densification, and data fromrods with extended burnup. Instrumented fuel assembly 513 is designed to com-

plement and extend the data and analysis begun by IFA-431/432 in these and

other areas. Specifically, the primary objectives of IFA-513 are to:

extend the NRC/Halden test series to include rods with known gas mixturese

between the extremes of pure helium and pure xenon,

quantify the variance possible among rods of contemporary design thate

have been fabricated and operated identically, and

provide instrumented, irradiated rads that are thoroughly characterized*

as to fabrication parameters and thermal history, for use in transienttesting under off-normal conditions.

2.1 CORRELATION WITH IFA-431/432

IFA-513 is very similar in design to IFA-431/432. All three assembliesconsist of six fuel rods in a hexagonal array, are of the same cladding stock,

and are well instrumented. However, a variety of fuel rod designs (differentfuel pellet dimensions, densities, and stabilities) were used in IFA-431/432,while the six rods in IFA-513 are identical except for fill gas compositionand pressure.

To provide a direct correlation between the three assemblies, rod 1 ofassemblies IFA-431/432 and rods 1, 3, and 5 of IFA-513 all have the same

fuel, 10% (235 ) enrichment, 100% helium atdesign:(a) 95% TD stable U0 02

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(a) Except for length: IFA-431/432 has an ac.ive fuel length of 0.57 m, whileIFA-b13 has an active fuel length of 0.80 m.

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1 atm, and 230 pm diametral gap. This design is considered to be the standardrod design for the test series and is based on the BWR-6 fuel rod design.Thus, besides providing a means to compare the assemblies, the standard rod

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design provides results that may be directly applicable to power reactoroperation.

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Several other factors also contribute to a good correlation between IFA-513and IFA-431/432. First, IFA-513 will operate at a peak linear heat rating ofapproximately 40 kW/m. This is midway between the peak powers of 33 and 49 kW/m

for IFA-431 and IFA-432, respectively. Secondly, the calibrations for all

three assemblies are done in the same manner, thus providing consistent esti-mates of power. Finally, even though the IFA-513 fuel pellets were fabricatedfrom a different powder batch, similar sintering conditions were used. The

resulting microstructure is quite similar to the fuel pellets in IFA-431/432.Therefore, IFA-513 fuel should behave in the same manner (see Section 4.2).

2.2 IFA-513 GAS MIXTURES

A variety of fill gas combinations are being used in IFA-513: four of therods use helium, while the other two rods use helium / xenon gas mixtures. The

current BWR design is used in rods 1, 3, and 5; this design includes fillingthe rods with pure helium at I atm pressure. Rod 2 is also filled with helium,but pressurized to 3 atm. This rod is included because new BWR rods may usethe higher pre-pressurization.

Rods 4 and 6 will provide data to improve the understanding of the thermaleffects of fill gas therral conductivity degradation. Both rods have an ini-tial pressure of 1 atm; rod 4 has an initial gas composition of 92% He/8% Xeand rod 6 has an initial composition of 77% He/23% Xe. These two mixtures pro-vide gas thermal conductivities that are approximately 75% and 50% of purehelium, respectively. Any differences in 80L behavior between these rods andthose that are filled with pure helium, may be directly attributable to thedifferent, and known, fill gas compositions. The well-characterized data -

obtained from these rods will further define thermal resistance behavior as afunction of power and gas mixture.

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2.3 STATISTICAL ANALYSIS

Data from IFA-513 will be benefit in the evaluatinn of variaoility in fuel.

rod performance and any current bias between fuel rod behavior and computercode predictions. There are primarily two sources of variance in performance:because of manufacturing tolerances, identically designed fuel rods will not*

be truly identical; and there will be minor variations in the operating condi-tions from rod to rod (e.g., neutron flux tilt within an assembly). The finalresult for a particular fuel rod design, as illustrated in Figure 2.1, is adistribution of responses around a mean value. The three identical rods inIFA-513 will aid the evaluation of the amount of variability to be expected.

Evaluation of the bias between fuel rod performance and code predictionis more difficult. First, the distribution of fuel rod response must be known.

Next the rod design and operating conditions must be modeled and a predictedresponse, and attendant uncertainty, obtained.("} With these two pieces ofinformaticn, the amount of bias and the significance (b) of the bias can be

(a) For-additional discussion on modeling uncertainties, see Cunningham,et al. (1978) and Peck (1978).

(b) The definition of significance must necessarily be left to the individualas the significance depends upon the circumstances.

DISTRIBUTION |'

OF RESPONSES

MEAN RESPONSEgE

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FIGURE 2.1. Distribution of .esponses from Single Fuel Rod Design

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estimated (see Figure 2.2). The well-characterized power history and behavior

of the fuel rods in IFA-513 and IFA-431/432 can be used to help make this.

evaluation..

DATA MODELING DATA

UNCERTAINTY RESPONSEISTRIBWON

* LMCERTAINTY RESPONSE,

DISTRIBUTION DISTRIBUTION ! \h - - Es* 58 8B B

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BIAS

/RESPONSE RESPONSE

al SIGNIFICANT BI AS b) INSIGNin CANT BI AS

FIGURE 2.2. Examples of Bias Between Modeling and Experiment

2.4 TRANSIENT TESTING

It is anticipated that some, or all, of the IFA-513 fuel rods will beused in the Power Burst Facility (PBF) for transient off-normal testing.These rods will be particularly useful because of their well-character _izedfabrication and operation. Since adequate instrumentation ;s an importantpart of any test, the IFA-513 rods are specially designed to allow disconnec-tion and reconnection of the thermocouple leads in order to obtain fuel temp-erature data during the PBF testing.

The PBF testing will consist of three phases: normal operation testingto evaluate the rods for effects of shipping on behavior, provide data forverification of the thermocouples, and provide general data to connect the PBFdata base and the Halden data base; off-normal testing to evaluate the effects =

of_ loss of coolant, power-cooling mismatch, reactivity insertion accidents,4

and/or other situations of interest; and finally postirradiation examination ,

to characterize the final state of the fuel rods and compare with similar' tests on unirradiated fuel rods.

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3.0 IFA-513 DESIGN AND ASSEMBLY FABRICATION

The IFA-513 design is very similar to that of IFA-431/432. It will be-

discussed in three sections: the individual rod designs, the overall assemblydesign,(a) and fuel rod fabrication. The associated instrumentation will be,

discussed where appropriate throughout the report.

3.1 R0D DESIGN

All six rods in IFA-513 are nominally identical except for fill gas com-position and pressure. The cladding is annealed, seamless Zircaloy-2. The

fuel is compacted and sintered U0 . f 95% theoretical density enriched to2

23510 wt% 0. To reduce flux peaking at the ends of the fuel columns, a poi-

2 and 5% Dy2 3 is located at eachson pellet consisting of 95% natural U0 0

end. Table 3.1 lists rod design parameters; while Table 3.2 summarizes theas-built dimensions and variations. A general rod design schematic is shownin Figure 3.1. The pellet stacking order for each rod is in Appendix A.

The instrumentation for each rod consists of two thermocouples and a bel-lows-type pressure transducer. Because the thermocouples, W-3% Re/W-25% Re

with Be0 insulators, are located in the upper end (near the neutron flux peak)and the lower end of the fuel rods (see Figure 3.1), they provide temperaturemeasurements at two power levels, with the lower level approximately 70% thatof the upper. The pressure transducer is connected to the plenum and automat-ically provides continuous pressure measurements.

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(a) Halden has supplied PNL with copies of the design drawings for the fuel.

rods, instruments, and supporting hardware.

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TABLE 3.1. IFA-513 Rod Design Parameters

Cladding (a).

Material Zry-2

~0 uter Diameter 12.789 mm'

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Inner Diameter 10.909 mm

Fueli

Material U0235

Enrichment 10 wt% 0

i Density 95% theoretical'

Diameter 10.681 mm

Pellet length 12.7 mm

Poison Pellets

Material 95% Natural UO , 5% Dy02 2

Diameter 10.2 mm

Length 7.0 mm

Fill Gas

Rods 1, 3, 5 100% He at 0.1 MPa

Rod 2 100% He at 0.3 MPa ,

Rod 4 92.3% He/7.7% Xe at 0.1 MPa'

! Rod 6 77% He/23% Xe at 0.1 MPaj.

(a) See Appendix A of BNWL-1988 for cladding certification.<

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i- TABLE 3.2. As-Fabricated Dimensions and Variances

Pellet length Pellet Diameter Theoretical Density*

| Rod No. mm 10 mm i la %. lo!

i 1 12.609 0.113 10.683 0.005 95.02 0.158j' 2- 12.642 0.115 10.683 0.005 95.05 0.166

3 12.611 0.103 10.681 0.005 95.08 0.1574 12.647 0.113 10.681 0.006 95.03 0.3475 12.593 0.119 10.681 0.005 95.09 0.2746 12.619 0.115 10.683 0.005 95.04 0.286

Fuel Column Length (a) Plenum Length (b)-Rod No. mm mm

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1 781.7 28.4! 2 783.8 26.5'

3 781.8 27.94 784.2 26.01

5 780.8 29.06 782.4 27.8

(b) Reported value is 'ength, measure (excludes poisgn pellets).d by hand caliper from end of tubing toKa) Total sum of indiv dual pellets,

! top of fuel stack minus insertion length of upper end plug (accuracy is0.1-0.2 mm).

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DIFFERENTI AL TRANSDUCER ASSEMBLY

BELLOWS PRESSUREP01 SON PELLET

TRANSDUCER ASSEMBLY UPPER BERM 0 COUPLE ASSEMBLY

,, ,/ PLENUM SPRING ADDmG( fff _f' ~ _b ",,

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UPPER mERM0 COUPLE LOWER mERM0 COUPLE P01 SON

j / / 'jFUEL PELLETS PELLET'I

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95 * 95Rouno mRoVGH GUIDE TUBE LOWER NERM0 COUPLE ASSEMBLY

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FIGURE 3.1. Schematic Arrangement of Fuel Rod for IFA-513(fabricated dimensions are in mm)

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3.2 ASSEMBLY DESIGN

The complete IFA-513 assembly consists of the six fuel rods, additional,

instrumentation, and supporting hardware. Figure 2.2 is a schematic of thecomplete assembly. Figure 3.3, a core map of HBWR as of January 1979, showsthe location of IFA-513 (core position 3-5). Figure 3.4 shows how IFA-513 is"

oriented relative to the core center; all rods have orientation marks that faceoutward from the assembly center.

The assembly instrumentation consists of the following:

Cladding elongation detectors - Linear voltage differential transducers.

(LVDT's) are used to measure cladding axial elongation. The fuel rods arefixed at the top and allowed to elongate downward.

Self-powered neutron detectors (SPNDs) - Eight vanadium SPNDs and one.

cobalt SPND are used in this assembly. The vanadium SPNDs provide steady-

state flux monitoring and are used for calculating the local linear heatrate at the thermocouple positions. To determine the neutron flux profilethrough the assembly at the thermocouple positions, three detectors areplaced in each thermocouple plane. The detector centerlines are at thesame axial position as the thermocouple tips. The remaining two detectorsare located between the thermocouple planes and are in line with detectors1 and 6 located in the lower and upper planes, respectively. The cobalt

detector is used for monitoring rapid neutron flux changes and is locatedin the center of the assembly. The relationship between the thermo-

couples, neutron detectors, and reference axial neutron flux profile isshown_in Figure 3.5.

Inlet and outlet turbine velocity meters - These meters are used to mea-e;

sure the inlet and outlet fuel channel coolant flow rate during assembly

power calibration.

Inlet and outlet thermocouples - Chromel/alumel thermocouples with insu-.,

i lated junctions are used to measure the coolant temperature rise in the

fuel channel.i oI

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ND8O OATALUMINUM FLOW TUBEy

-6 PRESSURE TRANSDUCERS 4 3_ _ g ,

i ^ ] 6 FUEL RODS,

hh- 6 FUEL CENTER THRM0 COUPLES- 21231 mm' 3 VANADIUM NEUTRON DETECTORS

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| B-B21026 mm h - 1 VANADIUM DETECTOR

j- 1 COBALT NEUTRON DETECTORF- J 932 mm C RLIN .,

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!

B 3 VANADIUM NEUTRON DETECTORS

" - 6 FUEL CENTER THERMOCOUPLES=- - J 542 mm

-6 CLADDING ELONGATION SENSORS

a 285 mmr -lNLET TERM 0 COUPLES

| | !

NATURAL CIRCULAT10N b INLET TURBINE VELOCITY METER,

NORMAL OPERATION mL M # - CAllBRATION VALVE

0mmj/| [j/

_ _

r >

~ CORE BASE PLATE

'

\*iMRM0 COUPLE HOT JUNCTl'JNS ARE FORCED CIRCULATION, CAllBRATION ONLY

WITHIN 2 mm 0F VANADIUM ND {.

FIGURE 3.2. Schematic Design of IFA-513. (Note that neutron detectors4 and 5 are in line with detectors 1 and 6.)

12

L

88 84 8 10 8-13 8 12 8 13 8 14 8 15 8 16

8-7 FF F8 74 F 10 F -ll i 12 F-13 F 14 8 'llg

041

84 74 6 -6 6-7 68 64 6 10 6 6 2 F 15 8 18

34 F4 64 54 56 5 -F 58 54 5-10 6-13 F 16 6-19

16 II001 078 021 228 051 046

84 F -4 44 5 -4 44 44 44 4F 48 5 11 6-14 T-li 8-20

32 3331053 422 413 029 032

8-3 F-3 6-3 53 4-3 3-3 34 35 36 44 5 12 6 15 F-18 8-21

066 436 043 502 31) 2322 205 019

8 -2 T2 62 5 -2 4 -2 32 2 -2 2-1 24 3-7 4 10 5 13 6-16 7 19 8 22

I067 048 437 509 237 165 414 080 022

8I F-1 6 -1 5 -1 44 3-1 21 11 1 -2 24 38 4-11 5 14 i ti F -20 8-23

047 058 148 10 201 502 12 432 515 % 40230

84 F4 64 5-0 40 10 2- 0 10 04 l1 26 14 4 12 5-15 6-18 F -21 4-24

D O0 15 055 049 416 501 510 429 512 427 040 (57

8 47 7-44 6 -n 5 29 en s ti 2-11 14 | -4 2-F 3 19 4 13 5 16 6-19 T -n 8a

# I5 I3 35062 5(5 503 2% 504 401 508 024

8 46 Fao 6-u 5-28 4 22 l io 2 10 24 2 -8 3-11 4 14 5 li 6-20 F -23 4-26

I8 26064 052 507 420 238 161 042 037

8 45 % F-39 6 13 5-27 4 21 3 15 3 14 3 13 3-12 4-15 5-18 6 21 F -24 8 2F

28 27430 050 409 518 202 Sta 035 026

8 44 7-38 6-32 5 26 4 20 4 19 4 IB 4-17 4 16 5 19 6-22 ' F -25 8-28

I 6074 072 235 5 05 435 Ob9 033

843 T 3F 6n 5a 5 24 Sn sn 5-21 5 20 en F 8 29

229 I' 028 219 16 232 075 412

8 42 F-% 6 io 6 29 6 28 6 2F 6 26 6 -a 6-24 i ri 8-10

073 076 0% 1 72

8 41 F-M -3 iL F3 i F- F 8 -31

Oto

8e 8 39 8 18 83; 8w 8 15 8w 8-n 8 32

H8WR IV CORE LOADING NO.33 'J A TE: JANUARY 19

CONTROL ROD (C5191 TOTAL: 29 -

@ INSTRUMENTED FULL ASSEMBLYllFA-202)TOTAL: 43

STANDARD THIRD CHARGE ASSEMBLY TOTAL: 48

*

g THIRD CHARGE SPIKE ASSEMBLYTOTAL: 5

| FIGURE 3.3. HBWR Core Loading No. 33 from January 1979.

13

1

.

R00 R00

'O O ","' '

$_

N00 R002 5

FIGURE 3.4. Orientation ofIFA-513 Relative to Coreenter line

ROD R001 6

O .45,6

1r

Q NEUTRON DETECTORS, 3.5 mm dia

CORE

CENTERLINEFUEL ROD 5,10,91 mm dia

,

14 - - - - -- ---- -

tREFERENCE AXI AL !

-~~~1-~~~~~12 ~~~ ~ '-~ --

THERMAL NEUTRON FLUXx

| | | |I

VANADIUM NEUTRON DETECTORS

W ::=LowtR =-: ~ 7g_ THERMOCOUPLE |

a

[ UPPER THERMOCOUPLE5 i

E COBALT NEUTRON ; ,

6 - - - - ~~ - - - - - DETECTOR ,y

" 4 -- --

FUEL

2 - - ~ - --- - - - ------

2

*0 200 400' 600 800 1000 1200 1400~ 1600 1800 2003 2200

ELEVATION ABOVE CORE BASE PLATE. mm

.

FIGURE 3.5. Arrangement of Fuel and Instruments Relative toReference Axial Thermal Flux Profile .

|

|14

. - - -

Fission product monitor - This monitor is located at the outlet of thee

fuel channel and determines fuel rod integrity by analyzing fission pro-duct activity in steam samples.'

To see how IFA-513 actually ? m s, Figure 3.6 contains four photographsthat were taken after assembly fabrication. Further information regarding the-

major featuras shown in these photographs is given here:

UPPER TURBINE - Upper turbine coolant velocity meter: the meter has been.

removed from the assembly for better viewing.

513-X - X designates which fuel rod of assembly 513 is pictured..

PXD and PXD/LVDT - Internal gas pressure bellows and linear voltage dif-.

ferential transducer.

SPLIT TUBE FOR LOWER TFs - Guide tube for leads from lower thermocouples..

NEUTRON DETECTOR - One of the eight vanadium SPNDs..

EC/LVDT - Linear voltage differential transformer for measuring cladding*

axial elongation.

3.3 FUEL R0D FABRICATION

Discussion of PNL's fabrication and characterization of the fuel pellets

used in IFA-513 appears in Section 4. Following fabrication, the fuel pelletswere shipped to Halden for assembly into completed fuel rods. Fuel rod fabri-cation and charact rization was carried out at the Institutt for Atomenergi'slaboratory in Kjel.er, Norway (Lunde, 1978).

The first step in the fuel rod fabrication process was to clean the fuel

pellets with alcohol then dry them in vacuum at 623K for 1 hr.

The Zry-2 tubing to be used as cladding was also characterized at thistime. A continuous monitoring air gauge was used to measure the inside diam-

0 Ueter of the tubes. Two linear traces at 0 and 90 and a spiral trace were,

taken. The equipment was calibrated with calibration rings and was found tohave an accuracy of 0.002 mm. Discrete measurements of the tubing outside

,

diameter were made by hand with a micrometer. The data froa both sets ofmeasurements is in Appendix B.

15

a

- . .. - - _ . . _ .

i

.

.

@ . .

p ' (a) Upper end '. ._

#- .. e of assembly,# '. ~#

turbine flow_.

.

' # ,- . *' meter i s -

?^ * ~~Y . removed for''

'' viewing

' ~

.. .4

i'

- _. -_ ._ a

.' . 613-2 PRD.- LVDi[4613 2 . .-- 513 2 PXD

,

= ^SPLIT TuSE 6 OR "- -

___ _ ._, t nWF P YF'S '513' - . --

^

o f

. . ,

hEUTRON DETECTOR

|

~~ 7 " - ~'" ~ ~ ~ ~

(c) Vanadiumneutron

..... ,._ .~.. ._ _

fuel rods

--- ' '~~

(d) Lower end a ni2 2 ac'tv

of assembly with k5. ,"i - - -

LVDT cladding - , _ _ _ _ _ . , , , . , ,_

elongationdetectors

- ,

FIGURE 3.6. Photographs of Completed AssemDly bhowing Various.

, Features and Instrumentation1

16

_______ __________ - __ _. ._ - _ _ ._. ._ _ _ _ _ _ _ - . . . _ - - - - _.. _- - - _ - . __ _|

Assembly of the fuel rods began with the loading of the fuel and thermo-couples. During loading, the thermocouple tips were positioned as follows:lower thermocouples 80 mm above the lower end plug; upper thermocouples 118 mm*

below the upper end plug. After welding the lower end plug to the cladding,the plenum length was measured (Table 3.2), followed by insertion of the plenum

,

spring (Figure 3.7) and bearing disk. The next step was to weld on the upperend plug and bcllows pressure transducer assembly. The free volume within thefuel rod was then measured by a silicon oil manometer; the following are theresults of that measurement:

3Rod Free Volume, cm

1 8.7

2 8.6

3 8.8

4 8.4

5 9.0

6 8.8

(a) The measured free volume consists ofthe fuel rod and pressure transducerinternal volumes. Its accuracy is

0.05 cm3,

The sequence involved in completing the assembly of the fuel rods was to firstevacuate the rods, to refill them with the gas mixture chosen, and finally toweld shut the vent holes in the end plugs. The nominal gas compositions (involume percent) for the helium and xenon gases are as follows:

Helium __senonHe 99.995 Xe 99.99

Ne 0.001-0.0014 Kr 0.01

N 0.0002-0.0008 N 0.002,

0 0.0001 0 & Ar 0.00032 2

H 0.0001 H 0.0001~

CO 0.0001 Hydrocarbons 0.00022

H0 0.0001-0.0002 HO 0.00022 2

17

4

|

7.9 mm

, GRIND FLAT

"Imm > )/

+ 'x.y) -

X->

1mm /-v .-

26 mm -y' }-//3mm --q

*/){ i-

ulmm ) )4 \

GRIND FLAT

TO BE HARDENED:

6500C FOR 4 HOURS

THEN COOLING IN AIR

VOLUME = 0.156 cm3

MATERIAL = INCONEL x 750, COLD DRAWN

NUMBER OFTURNS 8

FIGURE 3.7. Details of Plenum Spring

,

||

18

i

m. .

For rods 4 and 6 (92.3% He/7.7% Xe and 77%He/23%Xe), pressure was measured bymanometer to be 1.0 atm, with a maximum uncertainty of 0.1 atm. For rods 1,3, and 5 (100% He), pressure was judged to be 1 atm when glove box gloves*

showed no pressure differential (maximum uncertainty is 0.1 atm). Rod 2

(100% He, 3 atm) also has a 0.1 atm maximum pressure uncertainty.,

Electron beam welding in a vacuum ( 1.3 x 10-2 Pa) was used for all

welds except for those at the vent holes in the end plugs. The vent holeswere closed by tungsten inert gas (TIG) welding. Prior to welding, all

surfaces were cleaned with xylol (a) and alcohol.

After the fuel rod assembly was completed, the end plugs, seal welds, andthe active fuel length were x-ray inspected. No faults were found. The finalcheck of fuel rod integrity was for helium leakage. This was done using ahelium mass spectrometer with a sensitivity of 2 x 10-10 cm /s at STP; no3

leakage was found.

(a) Xylol is the Norwegian equivalent of xylene (C "10)*8

,

e

19

-

4.0 FUEL FABRICATION AND CHARACTERIZATION

This section provides a record of th'. fabrication and characterization of-

the fuel pellets used in IFA-513. Suhoection 4.1 covers the pellet fabrica-

tion process including acquisition of the U02 p wder, sinterability tests,,

pellet fabrication, pellet certification, and pellet physical measurements.Microstructural characterization of porosity and grain size is discussed insubsection 4.2. Thermal conductivity measurements are planned, but have notyet been performed.

4.1 FUEL FABRICATION

The fuel pellets for IFA-513 were fabricated from enriched UO ceramic-2

grade powder obtained from Oak Ridge National Laboratory (ORNL). This powder

was obtained under PNL purchase order 10990 AY and came from ORNL Mfg. Batch

No. 30-2785 (see Appendix C). When the powder was received, the containerswere inspected and net weights confirmed. The powder was then sampled and

analyzed, and the data provided by ORNL was confirmed. After the analytical

data was reviewed, a U0 Powder Certification of Compliance Quality Control2

Release was approved and the powder was released for pellet production(Appendix C).

Two sinterability tests were performed on the powder. The first, Test

No. 1556, was done on a 100g sample provided with the powder shipment. Pelletdensities greater than 95% TD were easily obtained and no need for specialprocedures was indicated. The second, Test No. 1559, was a pre-productionsinterability test to prcvide final parameters for pellet fabrication. Again,

the test was successful and provided the necessary information. The plans,

data, and conclusions for these two tests may be found in Appendix C. Also inAppendix C are the Pellet Fabrication Process Parameters that were used in thepellet production run.

*The specifications for the IFA-513 pellets, plus their required charac-

terization, are included in Table 4.1. The following outline is for the pro-cedure used to manufacture the fuel pellets:-

! 21

jm

powder reduced to -100 mesh,e3

powder slugged at 3.8 0.1 g/cm pressure,e

powder granulated to -20 mesh,e .

powder blended with 0.4% sterotex,e3

powder pressed to pellets to 5.15 1 0.05 g/cm density,e

pellets identified by numbering while in green condition,-

e

pellets sintered in a hydrogen atmosphere at 1973K for 8 hr,e

pellets preinspected,e

0.4205 1 0.0005 in.I")pellets ground to specified diameter ofe

Upon completion of this process, a final chemical analysis of the pellets wasPellet Certification was issued (Appendix C).

made (Table 4.2) and the UO2

Before the pellets were final cleaned and shipped to Halden, all weresubjected to inspection and dimensional measurements were taken. All pelletswere checked for the following, and the data was recorded.

Visual Defects: The PNL visual standard for UO fuel pellets (shown in2

Figure 4.1) was used to visually inspect for chips and cracks.

Diameter: Measurements to the nearast 0.0001 in, were made at three

positions; near each end, and at the center. All pellets used in IFA-513met the specified tolerance of 0.0005 in.

Length: Each pellet was measured to the nearest 0.0001 in. at two

locations.

Weight: Each pellet weighed to the nearest 0.001 g.

Density: The geometric density for all pellets was determined from themeasured weight and average length and diameter for each pellet. .Thedensity of a selected number of pellets was also determined by a liquid

water was used as the suspension medium.(b) Theimersion technique:geometric densities are lower than the immersion densities. This isbecause the measured volume is not reduced to account for surfaceroughness and chips and is therefore greater than the true volume.

*

!

(a) Di;aensions are as specified--in inches. -

(b) The immersion density technique is described on pages 7-2 and 7-4 ofBNWL-l%8.

i 22

;

,__

|

|

TABLE 4.1. IFA-513 Pellet Specifications and Required Characterization

SPECIFICATION FOR IFA-513 PELLETS.

Pellet Diameter 0.4205 1 0.0005 in.(a)Pellet length 0.500 1 0.015 in.Pellet Density 95 i 1/2 %TD (Stable Structure)ID of Thermocouple Hole 0.067 - 0.071 in.-

Pellet Geometry Flat endedEnrichment Nominal 10% U235Powder ASTM Standard Specification for

Nuclear Grade. Sinterable UraniumDioxide Powder (C753-73)

Pellet Defects and PNL visual standard, ultrasonic

Cleanliness plus forced air dry

PELLETS REQUIRED

Drilled Pellets 16 pellets per Rod X 6 Rods = 96Fuel Rod 96Archive 8Overage _16,

120

Solid Pellets 6 Rods of 47 Pellets per Rod = 282Fuel Rod 282Archive 31Overage y Drilled 120

360 Solid 375Analytical _12 Total = 495

372Microstructure ,__3_

375

PELLET CHARACTERIZATION

Dimension Technique Used Precision Frequency

Outer Diameter Cross ends & center 0.0001 in. 100%Inner Diameter Go-No Go .

- 100%Length Two-locations 1800 0.0001 in. 100%

apart

Density - Geometric

Weight- Analytical balance 0.001 g 100%Density' Calculated 10.01 g/cm3(b) 100%

Density Inunersion 0.01 g/cm3(b) 100% of.

ArchivePeljets*

RhPe$ lee!

hhttob!k$ inn $NhNs

23

j

TABLE 4.2. Sumary of IFA-513 Chemical Analysis

Sample ResultsFuel Makeug Requirement (d) 08-93 08-94 08-95 -

% 2350 10.0 1 0.2% 9.86 1 0.05 9.9020.05 9.872 0.05

%U 87.7 wt% 88.11 88.09 87.99 .

minimum

0/U ratio 1.99 - 2.02 1.999 2.001 2.001

EBC(b) 4 8.7 8.8 8.8

Gas Content 0.05 cm3/gU, 0.005 0.003 0.004 91273Kmaximum 0.009 0.007 0.008 91873K

Al 250 <50 <50 <50C 100 25 47 21Ca + Mg 200 <25 + 10 <25 + 10 < 25 + 25C1 25 <10 <10 <10Cr 250 25 25 25Co 100 <0.3 <0.3 <0.3F 15 <5 <5 <5H (including 2 1.4 1.2 1.5

Fe 500 70 65 80Ni 250 <50 <50 <50N 75 11 10 14'

Si 250 <60 <60 <60Th 10 <0.3 1 1

235 , requirements are based on ASTM Spe C753-73. Units are(a) Except for % U

maximum allowable ug/gU, except where noted.(b) Equivalent Boron Content. UO2 Pellet Certification, pg C-38 explains why

the fuel exceeds the EBC requirement.

'T

f

|

1

I

.

*

24

i

RADI AL CRACK SINGLE CHIP

* SINGLE CHlP

v CHIP DEPTH /CIRCUMfERENTIAL CHIP AREAo o

CRACK o-

V UCH P AAXl AL CRACK

SURFACE CRACKS SHALL NOT EXCEED END CHIPS SHALL NOT EXCEED THE CIRCUMFERENTI AL CHIPS SHALL NOTTHE FoltoWING LIMITS FOLLOWING LIMITS EXCEED THE Follo#1NG LIMITS

(SAME LIMITS ON NON-Dl5HEDPELLETS)

1. END RADI AL CRACKS S 2% OF DI AMETER L SINGLE CHIP < 105 0F LAND 1. SINGLE CHIPS SHALL NOT EXCEED

2. CIRCUMERENTIAL CRACKS 1800## #

2. TOTAL CHIPPING <25 0F LAND 2. TOTAL SURFACE OF CHIPS SHALL3. AXI AL CRACKS SHALL NOT EXCEED 2%A NOT ND 13 W SUNCE AB

OF PELLET LENGTH

CHW WTH SHAW ND 1 WTH aW4. MICRO CRACKING 15 ACCEPTABLE a020,

INSPECTION SHALL REJECT ANY " BORDER-l!NE" QUESTloNABli PELLET

'

FIGURE 4.1. PNL Visual Standards for U0 Fuel Pellets2

Table 4.3 sumarizes the inspection results; while Appendix D containsthe measured data for all pellets. The immersion density results are also

included.

4.2 FUEL CHARACTERIZATION

Since the experimental data to be obtained from IFA-513 is to be correla-ted with data from IFA-431/432, it is important to understand the microstruc-

tural characteristics of the fuel. The fuel for IFA-513 was specified to besimilar to the 95% TD stable U0 fuel of IFA-431/432. However, it was fab-

2ricated from a different powder and sintered in a different furnace. The

i characterization plan was therefore aimed mainly at comparing the key micro-structural characteristics (pore volume, pore size distribution, and grain

size) of the.95% TD stable UO used in IFA-513 to that used in IFA-431/432.(a),

2

* ' (a) A'densification/resintering test may be performed later.

25

L 2

TABLE 4.3. Sumary of IFA-513 Fuel Pellet Specifications and Inspection

Pellet Characteristic Quality Control Specification (a) andor Attribute Inspection Results: *

Sunsnary Pellets numerically identified 1 to 520 were fabri-cated, pellets numbering 1 to 125 were drilled. Atotal of 18 pellets were rejected during inspection. ,

Of the total, 502 fuel pellets, 120 were dr111ed and382 were solid. Reject pellets were used foranalytical samples.

Visual Inspection All pellets were inspected in accordance with theChips & Cracks applicable PNL visual standard. NOTE: Although only

two pellets were rejected as a result of chips, aminor defect on approximately 30% of the pellets wascaused by a malfunction of the centerless grinder. Aslight flat was ground near the end of these pellets:in the extreme case 0.001 in, in depth and 1/8 in.in length and width. Rejection was not required forthis defect.

Pellet Diameter All pellets were inspected for conformance to the0.4205 1 0.0005 in. specification. The fulltolerance was observed: a few pellets had up to onehalf of the tolerance in the form of a slight taper.Most of the 18 rejects were due to undersized pellets.

Pellet length All pellets were inspected for conformance to the0.500 1 0.015 in. specification. The average lengthof all of the pellets was 0.497 in.: s95% of thetotal were within a range of 0.507 in. and 0.490 in.Five percent were in the range of 0.485 to 0.490 in.The two measurements taken 1800 apart on eachpellet did not vary more than 0.001 in.

Pellet Centerline 100% attribute go/no go inspection revealed theseHole centerline holes to be within the specified rar.ge of

0.067 in. to 0.071 in. An average hole diameter of0.070 in. was used for density calculations, however,a 0.070 gage would pass the center section of about50% of the pellets.

Pellet Geometric Specification 95% 2 0.5% TDCalculated Density

100% inspected (see variable data in Appendix D).

x oTotal pellets (502) 95.06 0.177Drilled pellets (120) 94.96 0,146Solid pellets (382) 95.09 0.175

NOTE: 100% inspection confirmed that all the pelletswere within 1 0.5% tolerance and that slightly morethan 95% of them were within i 2 signa limits.

,

Pellet Water 10% of the pellets were double checked. TheInsnersion Densities average density was 95.35% TD

.

(a) Dimensions are repeated here as specified,in inches.

26

_

Experimental Procedure

The methods and procedures used to characterize the fuel pellets followed,

the same philosophy used for assemblies IFA-431/432 and reported in BNWL-1988.Measurements were taken to determine pore size and volume distribution, and

average grain size, as a function of radial location. No thermal resintering~

experiments were conducted since this fuel type was designed to be stable withregard to further densification.(a)

Based on experience with the fuel used in IFA-431/432, minor changes weremade in the testing and measurement procedures. Rather than providing a com-plete data reference base, this data is intended primarily as verification thatthe fuel pellets met their design criteria. Three pellets whose bulk densitymeasurements were approximately the average value for the pellets loaded in theassembly were selected from the assembly fuel lot. Each pellet was sectionedtransversely at its midpoint, encapsulated in epoxy resin, and polished by theprocedure described in BNWL-1988. Special care was taken to minimize physicalpullout of grains or UO particles. Light microscopy was used to examine the

2as-polished surfaces for pores larger than 2 um. Carefully controlled vacuum'

cathodic etching was then used to remove surface debris from submicron poros-ity. Smaller pores were examined by scanning electron microscopy at the samesites on the polished surfaces. Grain sizes were recorded on the same surfacesafter etching more vigorously (using H 0 -N SO ) to clearly reveal22 2 4grain boundaries.

The microscopy, porosity measurements, computation of porosity character-istics, and determination of grain size were all conducted as reported in

~

BNWL-1988. The following sites were specified for porosity study on each ofthe pellet sections: 2 peripheral, 2 mid-radius, and 1 center radial location.Data from all three pellets (15 sites total) was combined to obtain " average"properties. Grain size data was obtained from measurements made with photo-micrographs taken at a peripheral, mid-radius, and central area on each pellet.,

(a) The 95% TD stable fuel used in IFA-431/432 was found to be stable duringthermal resintering tests (BNWL-1988).*

27i

- -

Porosity Evaluation

The general pore size and volume distribution for IFA-513 (as sintered)is similar to that of IFA-431/432. The general nature of the porosity may be -

seen in the typical mictrostrutures shown in Figure 4.2. Table 4.4 and

Figure 4.3 provide an overall summary of the microstructures; the porosity,

normally varied randomly throughout the pellets within the ranges shown.

.,,

7. ,

'

wy egg. .- s> - -~ .-., , ,

:. ..

...4 4 '. j* 'i . ..-

'.e%''., gj ') .. . . , .,.,

,.

-y y.- .,, ..

I,,. . . , gs .

*g , . 4'.| T- ', -. , . . .,

. ., .. -, ,' M .. ;l ;. 8'*

. ' '. alt3. ',* * .t l.- t,..

, , - ..

. .

** tc ' , '

,

5,- . .ic. ' ' .' , ' '*, ,t .

.

/.: . 2. -'!V,g* . ,e .. ,.=*.,.),, ,;

*.,,

. '. .* .?,. ..

. , . .~t<.,. . e. ..

. ' .,

,*;t

' ' -,

*

.".', ;

' . ' ' , .i~, .- ,...yi : 50 m

*,*50pm

p . . .. ,; e --,-. . . , . y ., ,;...... .: *;

_ .. ,que ng&WM Y j,'? >|*' 's. e.. . .

. v:4.ygy, ~;e. ,, ., . , * * .e. c

. .; ., . ._ p ^ * g g. @u 4 9 ymy y

.., .g; , Yc|}) cpfw.sgy , .

1 m.s? ?,* g;c;g' qp ?.e ,g b u ,( -

m.;.

;;m, >,* ::rp g .,. p _w. u. t

.

.- , 3.-]- w ,..

;, J.g g g ; n m: ,6 .: , . . ,, 3;

m-

$ . *. h;9 s-We 9 y,} * '.,s. .' q .A.3 Q. w,.. .

-

4p,j.

!~ <

E., . . y. y .

b ,. 6 L . a de i, .., - o .~c o qss

5 pm Bl C .c m c ; 5pm i

m;.g;mf. o - - m- .w, nc W-m m. m;m m- .,

y-

p ;. ....u, 4 .;, _ ,. f ,

,. n7pw wnema,. --

.+.i

' |[. , . W ? ffn p&q.,-s

f ' :~:

Q4 e :-,

k;m g- . ,

,c 1-.

,a>

q.,

, ,

, . , ..4W e ;U i, ,q,, ju.

. ,,.p .

. . n. .,

>

. nAa . e', h -* - )%.

Y.* y.,y a c( .7 ) Q -:. '

+ , , 3.,ej ;- - 4..g (; , , . ;#

. ,#

14-

.

g Gi <y, .5 .

g. . :q|ny. % , 4 ' x c ;s -

,g -:

gw .ww 3 ay .

;Ludh.a.a '1 pm F. wt'

.3 E| ,a , . 19 1 pm i

IFA-513 IFA-431/432 .

FIGURE 4.2. Microstructure of UO2 Fuel Pellets for IFA-513and IFA-431/432

28

IFA-513 and IFA-431/432 have similar porosity distributions, particularlyin the important size range of less than 10 pm diameter. -Both contain approx-imately 0.6 volume % of submicron porosity, and 4 volume % of 1-10 pm pores.'

IFA-513 appears to have about 1.5% more pores > 10 pm than IFA-431/432;

this larger volume may be related to the much smaller grain size present inIFA-513. The smaller grain size may lead to more intergranular porosity, andpossibly to more frequent pullout during section polishing. The greater total

pore volume measured for IFA-513 is primarily due to larger pores. This isreflected in the average values shown for the various size ranges in Table 4.4.The influence of porosity on the behavior of both IFA-b13 and IFA-431/432 isexpected to be essentially identical.

TABLE 4.4. Summary of Calculated Pore Distributions from all Datafor Each Halden Fuel Assembly (95% Theoretical DensityStable Fuel)

Specimen (Fuel Assembly IFA-513 IFA-431/432

Porosity Volume, %By Density Measurement 5.0 4.4By Pore Measurement 7.9 6.7Pores < 1 pm 0.6 0.6Pores >l pm 7.3 6.1Pores > 10 pm 3.3 1.8

Pore Diameter, umMedian, All 7.3 5.1Median, < 1 pm 0.7 0.6Median, > 1 pm 7.3 5.1Median, > 10 pm 28 32

Maximum 119 101

3Pore Population, No./cmAll Pores 2.4 x 1011 2.4 x 1011Pores >l um 7.6 x 109 6.3 x 109Pores >10 pm 8.3 x 106 4.5 x 106

.

e

29

J

L0

~

IFA-513 .

a8 - (7.9% POROSITY)

5 '

y a6 - /

b - /\a4 -

\s\e a,

- e/

a2 - -

k0 - ' i

0.1 1 10 100

PORE DIAMETER, pm

1. 0

~

IFA-431 I432(6.7% POROSITY)E8 _

$ %h a6 -

)2

_g

!E

"# ~

kE / 8 m\/a2 -

/j s .

E' i0

&1 1 10 100

PORE DIAMETER, um .

FIGURE 4.3. Pore Size and Volume Distribution for 95% TD Stable UO2Fuel Used in IFA-313 and IFA-431/432 (vertical lines ,

indicate 20 confidence limits at midpoint of each sizerange)

30

- _ . _ ._ . . . _ . _

!,

$

The pellets for IFA-513 were fabricated from the powder shown inFigure 4.4. Pretreatment of the as-received powder resulted in rounded agglo-

*merated particles averaging approximately 25-50 pm in diameter (upper photos

I in Figure 4.4). Close examination of the large particle structure reveals

!. that they are composed of close-packed, randomly shaped particles approxi-mately 0.1-0.2 pm in diameter (lower photos in Figure 4.4). This combination

of agglomerated particles permitted sintering to high density with some con-trol over retained porosity. No IFA-431/432 powder samples were available forcomparison.

j Figures 4.5 and 4.6 show details of IFA-513 pellet microstructure. Com-parison of average porosity at peripheral, mideadius, and central locations(Table 4.5,- Figure 4.7 and 4.8) would indicate a lack of significant differ-ences in as-fabricated pore dimensions, either within or between the IFA-513

and IFA-431/432 95% TD stable U02 pellets.

TABLE 4.5. Pore Distributions in 95% TD Stable UO2Fuel for Assembly IFA-513

;' Radial Location Periphery Mid-Radius Centerline

Porosity Volume, %

By Pore Measurement 7.5 8.9 6.7Pores < 1 pm 0.6 0.5 0.6Pores > l um 6.9 8.4 6.1Peres >10 pm 3.1 3.6 3.4

Pore Diameter, um'

'

Median, All 7.3 7.3 13Median, < 1 pm 0.7 0.7 0.9

;

; Median, > l um 7.3 7.3 13

1 Median, > 10 pm 37 28 28Maximum 91 119 91

Pore Population, No./cm3,

1 All Pores 2.0 x 1011 3.1 x 1011 3.3 x 10 '1

Pores >l um 8.8 x 109 8.2 x 109 4.0 x 10E,

Pores > 10 pm 4.6 x 106 12 x 106 8.2 x 1r6,

i

i

31

. - . ._ _ . _ - - , ._. .

__ .__ _ .. ._ _ _ _ _ _

|

|

i

*.

.

g' '

}"?fvP;

r.

+'

,,

( - Y , ' .. .,,.. . # x.

. ,

>;, :. 1 \ ' , ., .[~ ,,

*--

g. " . - Y:fN.:r

_

{'

;:La I e w- .

- 50pm 'ge _3 10pm-

nr.- +wo. ..

fy ???$ |,

.r .-~ ~ '

~7

a, .$1.,1 d'?-, , .

'. . ' -( . irNj - f.

g * S''." w - - . . .it - 4y

'09 fm'ah *h'u

'

.iD' LJ

E ", ,1pm fm[ty

' 5pm J .

IFA-513<

I

-

FIGURE 4.4. Microstructure of UO2 Powder Used forFabricating IFA-513 Pellets

32

_ __. _ _ _ _ _ _ _ _ _ _ _ _

s

; c.. m'. :, n.

n,..g..u . . . r.o . .. c, ~

,e

.m.'w.A

<e.; ?...= ! : . w.:. .; ,,

. :':, n.

yf, . :;. ;y.s %,,'?.. ,4 / ;,yv , :..,a. -. . s... y v . . .: : . :g. . ..: . ::~ m u. : v ,

.t.A :. y y ;. . . u. : a . . ...,.;.a. ,f?c.

. .

s ,< ,w - ..,

. a.?- . s: .:. ; ...

. %n, .n.w::,..

' )u w. n .. ,-.

. . .s . . a .. : -. , , , . . :. .< , ; d;.~,. .- , w.w. . . *: 1, q< y - . ,.:..; , sy e.

; j '.,ty-* q. ;- }, . ,,,T-

:.

. . *g. .;..s. ,' . ; A:_ ; #s.

.. e . g 1. Q.. s., , .y :.

:.. . ,

.+..<n. .. .,,.1..s m,,e(:,4 ,n ,.:. ;f.;.; c.,. , . . .J: ., :,..

m ,e ~,. . c. o.. .. . . ...

... . n. . +.. , ._. .

c... ..,-.y,... ..

4 %:. . _ . ' .. . . . . , . . ,.

j M- QT W .. . , g).. . .,.,'? SQ. " a n, .y .Q.|.... .; 1Q h,::. .p. .y

..

,. , w d.7.,,,3;;./v ... :,,, m W ~

. . e .n.,,,:

,s.- .

e....~. c , , #, . .t , .r. . . p.- ..

..-.t.v.e ;q: .. nn -w; , , s. .v .

.

, . .y . .e , , .; - .y ~ n. . c . .. . . ,~ u : . . . . v ,. . ..m

: .:.y. ;. t.'~ .g

-m. . :. . , r. ,n.. w v <:*. .n

-

. .. . . . ? ,2.;; . .. ::x,m. . s

. ..n. -,4..

* ''. g d '.2,h'* *415 * i . * m . , v, . a. .. ., ..

ms~<,,t...,. .e .i .: a, n. c.w.. ;

.

.t. ,, .,. .s . n.

...% .d is,1 wy ;IS. g.. e.*"..

,.a . a1 y e m' ;;,.e,wy* , :w,3, ; w gg,y; ; '' "i

. J. ,', s ,, ,,

e9.

w- .< c w

s:g} mm y y

TRANSVERSE SECTION NEAR PELLET CENTER

4_. .y). , , .. ~, , . . ., . c. .4. . ,. . . _ ,_ . .. .c... . . _ . . ._ .~ ,

,3 . . . , , ,.. ... r.

.

.v.1. y v, x... e . s ,

..m , .t-:. A.r- . .L

. g- ; -- -s . e. t . y . .e t .- r. ;.s. ,c.

.

.<%.....

~. -.c ; .a,

,a+ q ,, ; ". ,s g ,a |

Q, g... g-. ,;b }y, 'Q.f ,'': ys y; c.. , .; ,.S|,x, s.).m);,, ,.. . -.

r .,;

e , n.' o . Q.5.,.? W W : |6.. x. . ; > .. .. a . <

i

;Jt/. e W. % ~ W?: ' :. .; '* ^ ',Tt 3.n e., ': .: .. I

s . p .~ , W,, V '. 4 . A xa%~ s n'b. .:. > )*W : . '';~

p q. 4., j . ,,: - - ~ 1: 9 jL .

T,q . , . V%,.p.g .w,, :.s . 4, i .,a, .

-.q g.r . .... .?u ,a . , ., .;

- r ; A..s y. .. . .<*,.r . . . .,. n n.

..

i,a , a..

*..

, 4** ^m :. ,,. ,

<f : '. ,y ,... , e . .. p. .n. i , T c.e* +-. n a.;3 . . L. M. . ee ?: f _2 ..A;* $rg

4, y. s. .,.r .- y 4

[, '':, v%}f:. ;%.' 'J ' , 4 L,; 0,,a . . :. ..

.se .. ~.

-.

J f;; .

- i W. w. -> f *s) Q. ~ ' 6**

.: . 7.; .y m. . ~> w . , s.c y .,. ,. , " .O Y v ? . . , ,m.p:* ,. .-

.

. . . - ~

. ,?n.. -:, . - s.,.- 4~a 4

.

y .: n %- ; e.. y

. ...;. . ,.s

yd. 3.,a & ,, s s ,,...v

. ~ ,ge ..,......,y,.,.,n,;,; ' ,, w..

. ..yx-c .

PL [ R |mmd*

.2, .. e u . i 20()p m );k. ' *fp*2* ' ' ; *

.

e. .* C.u * .. u. ~ <r-.

TYPICAL AREA 0F TRANSVERSE SECTION*

FIGURE 4.5. General Porosity Characteristics of 95% TD=

Stable U02 Pellets Used in IFA-513i

i

331

I

.

.

..w. -

. . . ... ' . ;,. .,. a. . . ,,.*, . - -

.

L t.' C . .s . .. ,. ,

, ,. . V '', ;','ht 's c't *

' k. *-*** '>: f. ( : r. , .

, , .'4.. .; ' - ^, * W..

t{-* * 's. :' , ,; , . , -e . u .; e . s v

.'.,b>ct T.'.. - ,.. . . . ,

. I. t g* -

a, ' ' .'.'

,j* A*

,,.

,. g '.,-,

,

. 3; . ' *g , , ,.'* "",3

'...>*..4'. .. f, + > . :

7, ,, -g,,

*:

' ,y , .t ,/_. ,6 . 3.| 't _ .,. 7 | '' ,? 6 . ! ::* ~

;., . .. .,

' - -

w. . : u. . ., a .: .,,... , -

,s. ., -. . ..r...- .w, , ..

.<-,.:&.**,..

',,d s. . . , ~, r.*- ..

, .n ?* >-

., ,'' ' '

.' ,. . .$. p f * . ' g, 7 ; c'. '.

,..m .. . . .

. ~ . ...

'rt i ..# - ?.c, . . ..:.s., . ,.. ,

. g.. c s ,-> i. i i 5i ,. ,. ,,

50pm , p, ., - -e ,1 50pmC 50pm 64... *

-

; g * g -.., -(.7 *., . .,.

7,,,,...n.,:....--.

, .

.e4- ;1 s ,.- . :, --.

., j . 9 . ,- ,g .:. -,

V .\ e Q*'

.-.

[n. ..

t.,

, g.n. o. .. [. . . , *. s -. .; ' .. . .*.. y3? .

.. , .. ...

e.- .e. ,. g.t. 4

. a.

g...t-, !-. .... '.z.. . .>; - r s. **. .'.j p +!

-

. -:, . ..

. ';. .., ac,

-, .,,L. *s,- . , < -. .,

-,

t. . . _..

's ..sa e

-

.

1 , -

!..W.;, , , , , , . - . o* . J ,t -

.~..

'C' :NI J. , P, j { .. ...-.'- *~_ f; ,

m'.s. . . ,. .,.. *'

q. e *di--- is ,-25pm|

' -...

p |, .

ji lj--. .,, _ ,4 -+: Sum t L. 2,. 1, , , ., pm ;

.- -,

.

, . _ . . , , ,- . . -, ._.7,, , _ , _ .

'

) .-,

x.

V. g- . ...cg._ . ~, .,

U* t .4 -I O ?g.g 1, .

.

:.

6 .*

>.. . .

'.

, e . ,

t $

[L ' e .': '1 Q.k n-, ..r e L q s1( . .

;. , >

. "q g +.>,

*- ; ( g p. ., ,.

..

g ;- 3- m,

t. . v i. :. ....'. , , . . a r ,a ,

1 A (4 ''u , , _ . .

! ;L , g ,wM 1pm E |y 1pn N-. '

1. A ;!4L J LJ A."., t-

. r:: lum i *

PERIPHERY MID-RADIUS AXIS

'

FIGURE 4.6. Typical Porosity Characteristics of UO2 Pelletsused for IFA-513. No Discernible Difference Existsas a Function of Radial Position in the Pellets

34

-. .. . _ - .

.

Grain Size Evaluation

A significant difference exists between the grain size characteristics* for'IFA-513 and IFA-431/432. As seen in Figure 4.9, the fuel pellets in

IFA-513 have a uniform grain size. These grains are approximately 12 pm in

diameter, with a maximum grain size of less than 20 pm. In contrast, IFA-431/I -

432 has a marked radial gradient in grain size, as shown in the figure. This

gradient varies from an average diameter of 22 um at the pellet periphery, toover 70 pm at the midradius and axis positions. The maximum grain diameter4

observed for the IFA-431/432 fuel was over 80 pm. The differences between

! IFA-513 and IFA-431/432 are further illustrated in Figure 4.10 and Table 4.6.The observed grain size differences can probably be explained by the variouscombinations of starting powder, furnace, and sintering conditions used forfabricating the pellets for the assemblies. The grain size for IFA-513, whilemuch smaller than IFA-431/432, is not likely to cause any densificationinstability (Freshley, et al., 1976).:

TABLE 4.6. Grain Size of As-Sintered PelletsI

Fuel Assembly (95% Theoreticmi Density Stable Fuel)

IFA-513(a) IFA-431/432(b)Position IAvg. dia, um) (Avg. Dia, um)

Peripheral 12 1 2 22

Midradius 12 1 2 73

Axial 12 1 1 72,

(a) Averages from transverse sections of three pellets.(b) /.verages of transverse and longitudinal sections on two pellets.

I

i

|

e

1

35

,

i

1. 0

-

IFA-513 ,

a8 - PERIPK RAL

g a6 -f g[}

~ -- MID-RADIUSg --- AXIAL ,

| ~, V) I ,h a, : < ,

\I g-

I \g -

I \ \a2 -

/ |\

\|-

\ l/

0-

,1-.I- ' '

0,1 I 10 100

PORE DIAMETER, pm

1. 0

1FA4311432-

4 PERIPHERAL

a8 - [ f/g - - MID-RADIUSl g- - - AXI AL

s as - '(I_

f\y

iI \g

^ / ,g ug a4 -

* f /1

--

9a2 - hh

4

} i ,a-0

a1 1 10 100

,

PORE DIAMETER, pm

FIGURE 4.7. Sumary of the Radial Distribution of Pore Size andVolume, (line segments join peak values of mid-point -

of successive size ranges)

36

1210

e

N IFA-513

- PERIPHERAL

s - - MID-RADIUS,

0 N6 10 ,, s -- AXI ALa se \2 \B

- \\

$ \h 10 - \

\_

s , , ,

0,1 1 10

PORE DI AMETER, pm

1210

~

IFA-513

--- IFA-4311432,

f 1010 _

,

e \2 \

$ ~

\5 \= N

8 -

N10

\\\

_ g\

010 ' ' '

al 1 109

PORE DIAMETER, pm

FIGURE 4.8. Radial Distribution of the Pore Population as a*

Function of Pore Size (cumulative total numberof pores larger than the corresponding pore size)

| 371

__

. t.. ,- ,

..h ~ j* I. * 'D* 3' '

f

- : 7 sf. ? . A.bf,, . ,; , g' */ .-

,

. .QL.c,

'

-.,

PERIPHERY PERIPHERY

! . ' ' 'l- % *l '.'*}7 @ *&

'+ ,

,

- t, - f. f-'

, ,. ..

N* ' . s'.*v>=y t,,- }- '

. t- ;- . . ,a /3 ,

p \. -. _\ .t

- '~ .

k. ..

*'* ' :~ , -

A 5 1 .c > .,,y. ..- _ ...

, , . . . . . . V .g . . .w. s ;I 9.

.- 5--

.,...<,i... ..

,.v . .

,. yf ^}*t**

. . . ;-.^A *'u s ;[ ;& v t *. , *. ny= - *

.. .' '.+. y * . '. % ;. " . * '

u| '.- w*T,-

.

. g W < ' b. 20pm I.

.

g :; . ,e , 20pm I. .m

MID-RADIUS MID-RADIUS

: - $. . ,. ,i b'e*U **Ea.

R ,, ,

# f.*/ , Q .. ,.

,..%g-[:f % G'Q., . y'.;,*..'.; . * :p:' s . .d.y . . - .- -- .

. '..-r

9..

, -

( pg -. :>- 3 ( 9 .. ...

. ~.A - . : g . ....

m

'f . :; }.f .h..-

'

'.:- --

._. . .

[ ' ., N;?.T} % {,

{. . . .' r %. .A . - - C : :;.'-

;g ,:. i.., ." .. R . &. ~ .' % _.'.' . %- - j..

?. ,f. ,,y . . ;.:g; 20pm t

~, . . :w. ,

.a w... .

'

.'.4 ,. 4 ' m . . . - " ' 20 pm ; g-*

-, , ,:,. .

AXlS AXI5IFA 513 IFA 4311432

.

FIGURE 4.9. Variation in Grain Size for 95% TD Stable U02Pellets Used in IFA-431/432

||

38

|

- IFA413*

80 - - - - IIA ~431 I432

g ,------

ei~

s'~60 - p

5 /w

-

/'

40 - j< /

~

/#

20 -

10 -

0 ' ' ' ' '

PERIPHERY MID-RADIUS CENTER

LOCATION OF GRAINS WITHIN PELLET

FIGURE 4.10. Summary of Radial Variation in Grain Sizefor IFA-513 and IFA-431/432

Conclusions

The fuel pellets used in IFA-513 and IFA-431/432 are similar in micro-structure. The greatest similarity is in porosity characteristics; the great-est difference is in grain size, where the grain sizes of IFA-431/432 are oftwo to five times larger than IFA-513. Based on the densification studies byFreshley et al., the combination of characteristics in both fuel batches (fewpores smaller than 1 pm diameter, total porosity of 5-7%, and grain sizegreater than 10 pm diameter) is expected to result in similar microstructuralbehavior, including densification stability.

.

$

39

5.0 ASSEMBLY OPERATIONa

During its irradiation, IFA-513 will be subjected to two operating condi-e

tions: the normal, steady-state operation of HBWR, and PNL-requested specialoperations. From the normal steady-state operation, the fuel rods are exposed

*\

to operating conditions that provide a standard data set of steady-state fuelcenterline temperatures, local linear heat rates, cladding axial elongation,and fuel rod internal gas pressure. The normal operating cycle for HBWR con-

sists of running at nearly full power for approximately two months, followed1

by shutdown for fuel assembly changes, maintenance, tad other necessary work.The special procedures are transient operations that take place within normalpower ranges. They are designed to provide additional data for the evaluationof fuel rod conditions.

5.1 STEADY-STATE OPERATION

At full reactor power, the peak local linear heat rate for IFA-513 is

approximately 40 kW/m. This is midway between the peak local linear heatrates of 33 and 49 kW/m for IFA-431 and IFA-432, respectively. An assembly

! average burnup of 690 - 1035 GJ/kgU (8 - 12 GWd/MTM) is currently planned.# In addition to being midway in power to IFA-431 and IFA-432, the selected

power level for IFA-513 is important for these reasons: First, experience at

Halden has indicated a threshold temperature for thermocouple failure. For

extended periods of operation, this threshold temperature is rpproximately1900-1950K. Therefore, it was recommended that IFA-513 temper 1tures be held

below 1775K where reasonable, to reduce the probability of th' mocouplefailure. Second, the 1775K temperature limit will prevent restr cturing ofthe fuel and corresponding changes in fuel properties.

At 40 kW/m, rods 1-5 are expected to have fuel centerline temperatures ofless than 1775K. However, rod 6 (77% He/23% Xe fill gas) may initially exceed

*1775K. Therefore, it is proposed that Halden initially limit the power in

IFA-513 (by appropriate control rod positioning) so that rod 6 will not exceedthe requested temperature limit. The power level for IFA-513 may be raiseda

after initial fuel relocation has reduced the thermal resistance of the fuelrods.

41

.

Data collection during steady-state operation occurs every 15 min and ishandled automatically by a process computer (IBM-1800). This data is storedon disk for 24 hr and then transferred to magnetic tape for permanent storage. '

5.2 SPECIAL OPERATIONS,

One result of the early analysis performed on IFA-431 and IFA-432 was

increasing needs for two types of data that had not been obtained during thenormal operation of HBWR. The first of these needs was an increase in the

amount and quality of low-power, steady-state data. Normally, low-power data,

is obtained only during rises to full power. However, only a few rises occurduring each operating cycle. In addition, the vanadium neutron detectors arenot completely stabilized under those conditions;(8) therefore the resultingpower estimates are biased in comparison to those that would be obtained undertrue steady-state conditions. The solution to this problem has been to use a" staircase" approach to power, as illustrated in Figure 5.la. By holding atthe intermediate power levels for 1-3 hours, both the amount and quality oflow-power, steady-state data is improved.

The second of these needs has arisen from efforts to better understand thebehavior of fuel rods. Theoretical considerations have shown that temperaturedata from power drops can be used to evaluate fuel rod thermal parameters andto verify thermocouple accuracy (Cunningham, Lanning and Montgomery, 1979;

Lanning, Barnes and Williford, 1979; Lanning and Cunningham, 1979). Afterreaching full power, two types of power drops are performed. The first is

called a " step" power drop: ideally an instantaneous 20% drop. Realistically,however, this cannot be obtained; therefore the requirements are a 20% drop inless than 15 sec (see Figure 5.lb). The data obtained from this operation isused to analyze fuel rod thermal parameters. After bringing the reactor backto full power, a linear power drop (20% in 30 sec) is performed. This data isused for thermocouple verification. Data from both power drops is collectedat 1 sec intervals. -

(a) The time constant for the vanadium neutron detectors is 5.4 minutes. ,

42

. . ._

.

* E

g loon -

//

!l-3 HoVRS

/TIME

a) Staircase Approach to Power

100b - -~

,

! 20s

e

es | "

8, ___'

a.~1.5%ISECOND

R R

<15 SECONOS

TIME

b) " Step" Power Drop (Actual Operation)

FIGURE 5.1. Special Operational Procedures for IFA-513

.

9

43

- .

-- , . _ _ _ . . .- . _ . . . . . _ _ - _ _--

By performing a staircase power rise just prior to the power drops, animproved correlation may be made between the steady-state data and the tran-

I sient analysis. Preferably, the combined staircase and power-drop operations .

would be carried out once per month, depending on the reactor operationsschedule. However, this sequence is particularly important during the initial

,

startup of the assembly and during subsequent startups following extendedshutdowns.

;

,

!

!

:!

I

i

ii

.

.

.

44

.. . _ . -. . . ,-

.- . _. _ . . - - - .

a

REFERENCES4

i Berna, G. A., M. P. Bohn, and D. R. Coleman. November 1978. FRAPCON-1: A*

; Com) uter Code for the Steady-State Analysis of 0xide Fuel Rods.CDA)-TR-78-032-R1, EG&G Idaho, Inc., Idaho Falls, ID.

Cunningham, M. E., et al. May 1978. Stored Energy Calculation: The State of.; the Art, PNL-2581, Pacific Northwest Laboratory, Richland, WA.

j Cunningham, M. E., D. D. Lanning and S. D. Montgomery. October 1979. AProcedure for the Qualitative Interpretation of Fuel Centerline ThermocoupleResponse to Step Power Decreases. NUREG/CR-1012, PNL-3096, Pacific NorthwestLaboratory, Richland, WA.,

Freshley, M. D., et al. 1976. " Irradiation Induced Densification of U02,

Pellet Fuel." J. Nuc. Mat. 62:138-166.,

Hann, C. R., et al. November 1977. Test Design, Precharacterization, andFuel Assembly Fabrication for Instrumented Fuel Assemblies IFA-431 and

| IFA-432. BNWL-1988, Pacific Northwest Laboratory, Richland, WA.i

Lanning, D. D., et al. January 1978. GAPCON-THERMAL-3 Code Description.PNL-2434, Pacific Northwest Laboratory, Richland, WA.

Lanning, D. D., B. O. Barnes, and R. E. Williford. January 1979. Manifestations of Nonlinearity in Fuel Center Thermocouple Steady-State andTransient Data: Implications for Data Analysis. NUREG/CR-0220, PNL-2692,Pacific Northwest Laboratory, Richland, WA.

Lanning, D. D. and M. E. Cunningham. July 1979. Startup Data Re? ort forNRC/PNL Halden Assembly IFA-513. NUREG/CR-0862, PNL-2948, Pacific North-west Laboratory, Richland, WA.

iLunde, K. September 1978. Fabrication of Fuel Rods for IFA-513. ME-145,

,

; Institutt for Atomenergi, Kjeller, Norway.,

Peck, S. O. July 1978. FRAP Uncertainty Analysis Option. CDAP-TR-78-024,EGtG Idaho, Inc., Idaho Falls, ID.

*,

i

G

45;

i. . _ __ . _ , _ __ ___ _.

4

4

9

e

i

APPENDIX A

STACKING ARRANGEMENTS FOR IFA-513 FUEL RODS

,

9i

!

e

. -

e , e e.

THERMOCOUPLES

'li

||| |P f-

' N

i A

|Ohh!!2|3|4|5|6|7|8|9 10_11121314 15 16.17 18 19_20_21 2223 24 25_26 27 28,29 3031 3233 3435 36373839,4 041 424344454647484950515253,545556!57|58!59N61!6kM1 1 1

- 96 m m 95 mm

23mm - 801 mm+

TOP BOTTOM

TOTAL NUMBER OF PELLETS IN EACH STACK - 64

NUMBER OF SOLID FUEL PELLETS - 47

NUMBER OF DRILLED FUEL PELLETS - 15

NUMBER OF POISON PELLETS -2

[ FUEL PELLET LENGTH - 12.700 t 0.381 mm (0.500 2 0.015 ini#

FUEL PELLET DI AMETER - 10.681 t 0.013 mm (0.4205 t 0.005 int

CENTRAL HOLE DI AMETER - 1. 702 - 1.803 mm (0.067 - 0.071 in)

POISON PELLET LENGTH - 7.0 mm (SUPPLIED BY HALDEN)

FIGURE A.1. Stacking Arrangement for IFA-513, Design Dimensions

.

p

.

Halden Test - Fuel Column Data: IFA-513

Rod No. 1*

Fuel Column Weight = 724.8g Exclusive of Poison PelletsFuel Column length = 781.7mm

.

Pellet Pellet Pellet PelletPosition Ident. Position Ident.

1 poison 33 3962 3 34 2203 120 35 1324 74 36 4635 54 37 4196 110 38 2707 7 39 3178(a) 5 40(a) 4499 77 41 188

10 512 42 25311 483 43 14212 412 44 50113 165 45 23314(a) 336 46 31115 450 47 478

48(a)50616 491

49 429i 17 277

18 163 50 37419 330 51 48420 329 52 12821 389 53 153

458 54 50022(a)23 357 55 24024 131 56 38225 234 57 11626 265 58 6027 510 59 2828 307 60 3129 394 61 5830 315 62 1

31 465 63 2632(a) 474 64 poison

.

(a) Density measured by immersion technique.

.

A-2

Halden Test - Fuel Column Data: IFA-513

Rod No. 2*

Fuel Column Weight = 726.9g Exclusive of Poison PelletsFuel Column Length = 783.8mm

.

Pellet Pellet Pellet PelletPosition Ident. Position Ident.

1 poison 33 3542 2 34 4703 125 35 4934 36 36 4605 40 37 2016 109

38(a)437

7 113 39 2608(a) 13 40 3889 61 41 323

10 411 42 22211 375 43 24212 331 44 51113 144 45 32614 190 46 48615 227 47 479

447 48 40116(a)17 245 49 488'

18 495 50 33919 497 51 32720 360 52 198

53(a)37921 428

54 14331622(a)23 171 55 279

37224 49056(a)57 3725 268

26 280 58 12427 515 59 7528 200 60 8329 445 61 830(a) 308 62 9431 210 63 2032 136 64 poison

.

(a) Density measured by immersion technique.

.

A-3

- _

Halden Test - Fuel Column Data: IFA-513

Rod No. 3'

Fuel Column Weight = 725.1g Exclusive of Poison PelletsFuel Column Length = 781.8m

.

Pellet Pellet Pellet PelletPosition Ident. Position Ident.

1 poison 33 23252 34 248

2(a)3 44 35 1491664 96

36(a)5 23 37 1726 64 38 2867 30 39 1558(a) 66 40 3359 24 41 395

10 256 42 17811 362 43 18612 259 44 51913 446

45(a)170

14 237 46 28815 157 47 44016 318 48 33317 297 49 400

18(a)199 50 250

19 504 51 40420 137 52 30221 466 53 43022 423 54(a) 37623 405 55 43124 223 56 40225 152 57 6826' 503 58 11527 416 59 8928(a) 266 60 10529 424 61 6730 413 62 15

'31 176 63 10432' 417 64 poison

.

(a) Density measured by immersion technique.

.

A-4

- - -, . . ..

._

Halden Test - Fuel Column Data: IFA-513

Rod No. 4*

Fuel Column Weight = 726.8g Exclusive of Poison PelletsFuel Column Length = 784.0nin

.

Pellet Pellet Pellet PelletPosition Ident. Position Ident.

1 poison 33(a) 4752 32 34 4143 11 35 332

f 4 73 36 422! 5 114 37 358

6 98 38 1747 29 39 2388 45 40 320

i 9 39 41 44310 276 42 43611 278

43(a)235

12 203 44 29813 462 45 47314 472 46 26115 187 47 29116 505 48 386

407 49 19317(a)18 392 50 25419 314 51 269

52(a)25520 217

53 45321 47622 206 54 50723 410 55 502

435 294-.

24(a) 56(a)25 208 57 1626. 312 58 12227 305 59 8228 433 60 50

10061(a)

29 21262 7930 361

31 322 63 10632 160 64 poison

.

(a) Density measured by immersion technique.

.

A-5

._ ._ --. . _ ._ . _ _ . _ _ . - _

}

j.

Halden Test - Fuel Column Data: IFA-513,

<

Rod No. 5

Fuel Column Weight = 724.3g Exclusive of Poison Pelletsi Fue4 Column Length = 780.7m1

i*

! Pellet Pellet Pellet Pellet; Position. Ident. Position Ident.j

1 poison 33(a) 3804

: 2 99 34 135i 3 63 35 138j 4 22 36 219

5 47 37 243:

! 6 80 38 126'

7 10 39 1458(a) 33 40 456

^

9 102 41 393

10(a)129 42 231:

1 11 425 43 218! 12 229

44(a)350

! 13 264 45 39814 421 46 230

J. 15 236 47 35316 154 48 480'

17 185 49 370; 18 391 50 377

19 293 5.'. 368-

162 52 15920(a)21 168

53(a)309i-

I 22 192 54 49423 246 55 34524 267 56 16725 355 57 92

j 26 ' 454 58 8427 457 59 5528 340 60 1829 239 61 8830 247 62 1731 058 63- 2732 204 64 poison

*.

,

(a). Density measured by imersion. technique.

.

|

|

A-6

- _ _.

Halden Test - Fur.1 Column Data: IFA-513

Rod No. 6,

Fuel Column Weight = 725.5g Exclusive of Poison PelletsFuel Column Length = 782.4mm

O

Pellet Pellet Pellet PelletPosition Ident. P_osition Ident.

1 poison 33 2252 90 34 1793 41 35 3814(a) 101 36 4815 118 516

37(a)38 1486 467 56 39 3378 49 40 2119 62 41 184

10 409 42 20211 304 43 51412 442 44 16413 517 45 452

14(a)285 46 350

15 485 47 47716 426 48 29217 328 49 17318 257 50 24419 482 51 16920 272 52 25221 221 53 49222 487

54(a)249

23 420 55 406444 56 469

24(a)25 181 57 6926 296 58 8527 161 59 11928 133 60 4229 441 61 70 i30 496 62 123 :

31 338 63 78 j32 182 64 poison

,

(a) Density measured by immersion technique.|

e

A-7

,

-

@

APPENDIX B

CLADDING CHARACTERIZATION

.

E

3

__. _ . . . _ _ _

i

! CLADDING CHARACTERIZATION!

Tubing for IFA-b13 is from the same batch obtained for IFA-431/432;*

specifications and certification may be found in BNWL-1988 (Hann, 1977). The,

following Zry-2 tubes were used for cladding:;e;

|

iRod Tube !

,

1 2A ,

,

2 18A [3 10A i

4 1At

5 24A

6 9B!

Internal profilometry, prior to fuel loading, was performed by Kjeller.

| The equipment used was a continuous recording air gauge. Two linear traces,at 0 and 90 , were made (middle and lower curves in Figures B.1-B.6), and'

a spiral trace (upper curve in Figures B.1-B.6). The equipment was calibrated

with calibration rings and has an accuracy of 0.002 mm. Table B.i. coiltainsdiscrete cladding outer diameter measurements that were taken by tand.

|;

I

v

1

f

.

e

B-1>

, _ _ . _ - _ . _ - - , _ _ _ , . . _ _ . ._ _ _ _ , . _ _ . _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ ,

_ . . _ . _ ._ __ _ . _ . . ._.._. _ . _ _ - _ _- . . _ _ . . __ _ ._. . _ _ . . _ . -. . - _ _ _ .

I

t

:.

t:

TABLE B.1. Cladding OD Measurements

'

Distancefrom Top Cladding Outer Diameter (a) ( )

.

of Rod, Rod 1 Rod 2 Rod 3 Rod 4 Rod 5 Rod 6

m 00 900 00 900 00 900 00 900 00 900 00 900,

i

100 12.791 12.788 12.785 '12.785 12.786 12.783 12.785 12.785 12.784 12.787 12.786 12.787 .

,

200 12.790 12.784 12.785 12.784 12.783 12.784 12.785 12.784 12.787 12.785 12.786 12.787

300 12.789 12.787 12.786 12.785 12.783 12.785 12.786 12.787 12.781 12.786 12.787 12.788

400 12.789- 12.788 12.788 12.786 12.786 12.786 12.787 12.784 12.787 12.788 12.787 12.7874

500 12.789 12.785 12.786 12.788 12.787 12.786 12.789 12.787 12.788 12.788 12.785 12.786

600 12.789' 12.786 12.788 12.786 12.786 12.789 12.787 12.787 12.789 12.787 12.787 12.787

700 12.787 12.789 12.784 12.785 12.786 12.785 12.787 12.785 12.786 12.790 12.788 12.787i

800 12.789 12.785 12.785 12.784 12.784 1E.784 12.786 12.784 12.788 12.788 12.790 12.785

cm

b'

(a) Measured by micrometer

i

i -

it

.

I

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,

|

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mfhy,6. .

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y x m.g-

J44 5 w w ^ n M4Jif a.u m,

4.i.1.1.;.a v..L.w .4 4 _-1!. F.4nt+...p.i. MJ 1 L4 4

; Q|'Hii Il $)lllY: $ISh Ag410.9295: + NHHHM =L%;I] I 1.2

7 --- -

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.

- 2 A

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u .

;.. m.

ID-MEASUREMENT WITH CONTINUOUS RECORDING AIR GAUGE

SENSITIVITY 2 pm/ SCALE DIVISION

AXI AL SCALE ~2.9 mm/ SCALE DIVISION IFA No. 513

CAllBRATION LINES 10.8384 AND 10.9205 mm R0D No. 1

UPPER CURVE SPIRAL TRACE WITH 2 mm PITCH TUBE No. 2AUMIDDLE CURVE O ORIENTATION

LOWER CURVE 90 ORIENTATION

FIGURE B.l. Cladding ID Profilometry for Rod 1

.

.

B-3

9

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T!: .a a,

ID-MEASUREMENT WITH CONTINUOUS RECORDING AIR GAUGE

SENSITIVITY 2 pm/ SCALE DIVISION

AXI AL SCALE ~2.9 mm/ SCALE DIVI SION IFA No. 513

CAllBRATION LINES 10.8384 AND 10.9205 mm ROD No. 2

UPPER CURVE SPIRAL TRACE WITH 2 mm PITCH TUBE No.18A

0MIDDLE CURVE 0 ORIENTATION

0LOWER CURVE 90 ORIENTATION

FIGURE B.?. Cladding ID Profilemetry for Rod 2

.

e

B-4

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ID-MEASUREMENT WITH CONTINUOUS RECORDING AIR GAUGE

SENSITIVITY 2 pmISCALE DIVISION

AXI AL SCALE ~2.9 mm/ SCALE DIVISION IFA No. 513

CAllBRATION LINES 10.8384 AND 10.9205 mm ROD No. 3

UPPER CURVE SPIRAL TRACE WITH 2 mm PITCH TUBE No.10A0

MIDDLE CURVE 0 ORIENTATION0

LOWER CURVE 90 ORIENTATION

FIGURE B.3. Cladding ID Profilometry for Rod 3

.

O

1|

B-5 .

1

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,

.i

ID-MEASUREMENT WITH CONTINUOUS RECORDING AIR GAUGE

SENSITIVITY 2 pm/ SCALE DIVISION

AXI AL SCALE ~2.9 mm/ SCALE OlVISION IFA No. 513

CALIBRATION LINES 10.8384 AND 10.9205 mm R0D No. 4

UPPER CURVE SPIRAL TRACE WITH 2 mm PITCH TUBE No. lA0

MIDDLE CURVE 0 ORIENTATION

LOWER CURVE 90 ORIENTATION

FIGURE 8.,4_. Cladding ID Profilometry for Rod 4

.

O

B-6

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-

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-

_: .: --

,

'1 t I is i | } /*

4.g.- ~ ,; r3.*unFva *rm' .p' % i] k r i i ( p sN r f +f Lp!'h,10.8384 M i'-= .e,a ; ;; < . v. g. u W -, .., ... . .s ;,

, r\.. ,,. m ' '. :. W .' ).yti;f'.4-t.,*,'.;p.mjl'j,,c-

'

< 4 4 4 4, e - j .-- -- - et- * * -

9. . ,% .. ;f{}{. 4

.. m..-.+m tem .-{~7.w:.y %-o-; ;w ~r- . o-r- ..r.,

-

i . ). p.4 q. . rN Q w;y.} ; :>.. m y . , u .s . y s n.y .

-> - ..;. LL

7 -t d[ l .1. ; ,+t-ff f I, ' ^ Yd t - t%,p_ p r . 4. J ., .14. s.4 L, p o i j ),. 1. .: . g.

1d}4i1 d - ,- L

h} $* td + ,- } f -j }Y, -' 4 ,?. f.$. U_.*d.ab-,$_ _4-!&(4[V0$Hf$$h_$4}d--_$ N_$_ {$?. 'g-

d

b, h 7 $j @ $g !N $l h H1+ 5 ~r Y ;. pppy|J 'y 49s.p.j-.'}n._920"5:_-_~~ - - _ _ .

a.p n ,+ + . H .t+. -~ .

. - :..:. un>

|$!T |N'x i !$r +1

. . . y y,, ., y ~s, c.<- m a.Ifit|%h?.G;

y ~ z.. y _ . ,... _ . . .> s n t . ..n s e<

\ ,, . ..

;u 4 > *1|'. ;\,,4 ; ;.../ tt| . 6 ' ti 4.y tr:.. '}e; 7.y .,\,~ .. y

.

r. | -- rm *-u.-,,s 1p,t, to.

Y $&hh,r... " | N & [& f L &p.s,yy_....$ff &p,. .,?@g;y .nw <.....y

,

.u. ..

r

V ~f:L b & H e 'k M ' 1 { i+++l& HHW |4 5 " t h i') i ^^+ :: g; ,f, Cq j;; . gn j.f p+. ;.4.7p p,Q;f..,.. t1. .,.i.W=4.$h:t M 4 -;~ m ;;r.G: $a.J..a.

--

;.j .L.-o-

n .. 4.J. . .. ,+ r-!~1+[w.,,. J ..

L n .+ .

1

tif+fr(t1[1i!ih ., 7.b. 3,it|L ]h ' ir $r T[^tf+||i.nlI||HId-l.}d+Ht ,

y* 1.

ID-MEASUREMENT WITH CONTINUOUS RECORDING AIR GAUGE

SENSITIVITY 2 pmISCALE DIVISION

AXI AL SCALE ~2.9 mm/ SCALE DIVISION IFA No. 513

CAllBRATION LINES 10.8384 AND 10.9205 mm R0D No. 5

UPPER CURVE SPIRAL TRACE WITH 2 mm PITCH TUBE No.24A0

MIDDLE CURVE 0 ORIENTATION

LOWER CURVE 90 ORIENTATION

FIGURE B.S. Cladding ID Profilometry for Rod 5

.

O

B-7

AT. .w*?h ;: t ,D,, .$. {T.iY ti ,i&.. t.s .,,y. iW${I{?..e .. '?..~ } @j,gE

5l{{p,8. 4 F ' m.q.H -Qi ga.g..

1 . . = ,.

( y,, . .y >(. vH %q,t'4 - t t r +y t.v et p. .

.o ,.. . .g.. g, .. r,p m 7 ._

i.,. ..;c

ht- '

7.' @ .T d .11 d_ii;.r; ?_ %qt't d if y{ &&r Jt r i 1T

1- ~* v7 tct m v-'M 'w

!

p+ %. , + $ r % -tr r- ., . + Q .a i S

-- --

Hp UKk.

__ - _--__

-

:_: . - - T10.9209r

ymf+y:w'r'+3FTyf|Yg:: 9jgy)j~'fgyyy@gpfy~.gu3Nir'.,ftIh . ikf, m ru n u i 1 i i i 1 i i I b: 1!7oi1!1i>

- ~

r-~mn uennen . ..> f } i 1/ ' *.t1 Fi i { ! sw ,,w. qI l'' .9 y4 k-f .v.y;,.(' ;,t ;.4~. E.r: 9' ggt;w',.,.wuw..,. 2 ,- m s ~ -,

Of4i'l 4Mf'' ?''!'11 ) .'. ' '' .c" .

,) ;l

p , ;. ,i .j' %b t.'0 fufbly/# "'.'.0!;l''A",.'. W4.E i' . &:2;I @, hp., S ing41%ywpitj ' y'%V ' .

'

: rf T r' -t W . 4 b .+ + M' P~ 4 r y H 4 M y d"- 9'Mp@-' y N, ,.mtrr-.1giphi't+t t*c

r rtt b;. ,4 .. p y 4 y 7 ; g ; ; 4 _pp.L .7.a. p _J_j j .y 9 $j.t.|J L-- , gy pp .; ., & -

'.4.k.

- .--

_h ; ._9 _ - .__ug.a - r.L. .;,

'10.920'_

-'' h'__

,e,p.~__,,.f

. n.2 .l| p .. ,- a.s...~

4537 yy.. y , f.; . ., 4.,-,a

, .--

- y ) .gh y .i%9 $| +4h riMM / ,,L|,Gil||||||| HinGk,n. ' 4j, f. }' . j-+

m . .-. m . . .. , . ,.. . y .. . -e ,_ _. m.,(. . . . . , . ' y; +,..

. . . . ..

. g . i. . ,' , , ,,. 3j ;i;p #

; 4. < + ,g , .f.r. a ,h >.

g M.t ' " v, l -.. i4 - ; . j j, ;, c .; .g 1. ..:;q

.

_h.j .W .y.y.b [g q t. emlp. .n. . ,. ....

g c, , ,,g ., ,e %. .%..

rv3= & .p e w.; ,e e- ,-.

h.h bi' . . E, i'' ' dhlhN!g

a g . ;..; _74 pg.g. gip.gp.h4 -

. 7-g.g.gpg gq.pg ..

GUMLi .X2h|TfW$5|j[d %D.MWhm055 5" 'tY f # 'M i ^i&k!iHbmuinID-MEASUREMENT WITH CONTINUOUS RECORDING AIR GAUGE

SENSITIVITY 2 pm/ SCALE DIVISION

AXI AL SCALE ~2.9 mm/ SCALE DIVISION IFA No. 513

CAllBRATION LINES 10.8384 AND 10.9205 mm R0D No. 6

UPPER CURVE SPIRAL TRACE WITH 2 mm PITCH. TUBE No. 9B0

MIDDLE CURVE 0 ORIENTATION

ULOWER CURVE 90 ORIENTATION

FIGURE B.6. Cladding ID Profilometry for Rod 6

.

O

B-8

O

O

APPENDIX C

FUEL CERTIFICATION AND FABRICATION

.

W

-. . . _ , _ . . ..

FUEL CERTIFICATION AND FABRICATION1

.

This appendix provides a record of the purchase, certification, andfabrication of the fuel. The following material may be found here:

.

PNL Purchase Order 10990 AY p. C-2

ORNL Packing List-and Powder Data p. C-6

PNL Powder-Analysis and Certificationof Compliance p. C-13

Sinterability Test No. 1556 p. C-17

Sinterability Test No. 1559 p. C-22

Pellet Fabrication Process Parameters p. C-28'

Pellet Analysis and Certification p. C-31'

The material presented in this appendix consists of reproductions of

I original documents. Therefore, no corrections have been made for

typographical errors or SI unit consistency.,

,

!

.

*%

1

b

|

i .

i

,

|. .C-1

i

-

i, , _ - - - - _ - . - . . - .. . . . -- -

-r-~~~~~~--_ _ , _ _ _ _ _ _ . ,

IM PonT ANT -~~" - ~ ~ ~ ~ ' ~

eMow PunCN As t om oER NUM B ER

3[ ou ALL PAcuacts. in m<;ss ANo

Pacific Northwest Laboratones c o m m E s Po m o t Ne t.

84stelle Boulevard co M PL ET E P AC KING LIST MUSTP.O. 8o 999 Acco.PANTcAcN . nip cNT.

{q ruchland. Washington 99332*

TO BE CO N 510 E R E D FOR FUTURE ORDERS - - - MEET YOUR D E LIV E R Y COMMITMEN T5 Iomosa Muu.an

... g . . . . .u . . . . . . . . . ...... ....-. , , _ ,

|0 l4 76 1 10990 DOE -2 o- a s c-' G914 10990 AY '

f,n %W'

s ..TTcLLp- c/o AnMco-r1TTT.Los.H' l a'c ML N o. --CAK RIDGE NAT10tal LAB i

qV'Op o..nr -

POAK RIDGE OPERATIONS OFFICE' f .".EU TAEC RESEARCH AND DEVELOPMENT DIV - M . c.o " ' ' * ' ' " " " ' ""'OAK RIDGE, TN 37830

$fa'o'cT=o=='e-I

t_ J

... .... .. ....,........ ., ,. . ... ..... 4

R ICHLA to, WA 12 17-76 OR SOONER S ROGERS (5.09-942 -0261 )...-. .,...-.,, c.u . .. ...

NET 30 DAYS 10 PREPAID.v. - | .s.,*.v. I wi- ae.e...vio= v , .. .c . | t.v.s ...e .

.....v..........v.,.. ......... ..... ,,,,,,..,,,. .....

ir c-sc s..

[THIS DOCUMENT IS NOT A CONTRACT. IT IS AMEMORAfOUM ISSUED FOR SERVICES, EQUIPMENT,,0R MATERIALS TO BE SUPPLIED UNDER GOVERMtENTCONTRACT W-7405-ENG-26 kHICH ARE NECESSARY A?Oa

O $ECUIRED IN CONNECTION WITH GOVERNMENT ' CONTRACT.

9r EY-76-C-06-1830. ACCOUNTING FOR THE COST OFj'. [THE SERVICES, EQUIPMENT OR MATERIALS WILL! BE MADE IN ACCORDANCE WITH AND AS REQUIRED BY| pECTION B, PART III, OF ERDA APPENDIX 1|1011 0F THE ERDA MANUAL, UNLESS OTHER ERDA I NSTRUC -i TIONS GOVERN.

1 30 KG NUCLEAR-GRADE , 5INTERABLE URANIUM 600.00 18000.00D IOXIDE PO'ADER.THE MATERIAL SHALL BE FURNISHED IN AC-CORDANCE WITH ASTM DESIGNATION:C753-73 WITH SPECIFICATIONS AND EXCEP-.TIONS NOTED BELOW:

3.1 URANIUM CONTENT, CHANGE 87.7 TO86.6.

.

stLING eNST9VCT10.es: RENQER INvotCES IN TRIPLICATE:

PROvlSIONS OF T>sE ATTACMED PURCMa5E OROER

SUPPLEM ENT CONSTITUTE ATTACH OptGIN AL WLL OF LADsNG ON ALL COLLECTSNeP.* E NT5 AND SUPPORT ALL PREPAsC FREIGNT gy

A P ART OF TNs5 ORDElt *" ' * * " ' ' ' * ' ' ' ' ' ' " ' ' " * ' " " * *XMh0Clt.TXXtAXAIXXXIIX '.*LL L''AUG.

I N -

.u , cm....-,o...., f .or- .|

.so.....- .... ........, ant;;, | .-....

C97979 ( RK MARSHALL PSL /1509 I %D7H6901- U

m. . , o

e" 1830m....-o

JE LESTER 306 300r

: TOT 01 NNZO iz58 ! I til i l'I'l i I

. . ... ... c ...t.c ...O

...u s b.e.) A NOR,

C -2 W

..

. PURCHASE ORDER a ' - ~ - -. sMOW PumCNASEOnoER NUMmER

O.e ALL PACKAGES. INVOICES AN oPacific Northwell LaboratoriesCo n * Es PON o E NC E.

84 telle Boulevard Cow P6 ET E P A C u i-G LesT MustP.O. Bot 999

ACCOM P ANT (ACM SMlPM ENT.F Richland. W45henglon 97332

TO B t' ' CONSID E R ED FOR FUTURE ORDERS - -- MEET YOUR O L!.IV E R Y - COMMITM EN TS !.,

o.oEn av eEn. ... .. 1 .... . . . . . . ..........

., , , , , , , , , , , , , ,

10 12+ 75 2 DOE - 10990 AYo-. a t .-i,

- p q 1 j C,os a TTELLEH aawc o - it.. e Los.( ;c L. o. .. .....

OAK RIDGE NATIONAL LAB P, ] ,,, u .

.. STREET W M. E.'RecNLamo,wa .32

3 as i=oiC aTEo eELo=g g.. .... ........ ........ ., ,. . .., . ... . .

S ROGERS, ,

..... .. ....... .... .... ...

. .. . ! . . . , . . . . i . , , . ...c...,,.- | .... ... . i ....<...c. i.. ..,...... ....., , , , , , , . , , , , , . . . . . , , .....v..........yz.

| secnacaso

2354.1 ISOTOPIC CONTENT, WEIGHT % UIN U SHALL BE WITHIN THE 9.75-10.25%RANG 33'c THE MEASUREMENT ACCURACY OFTHE U WITHIN THIS RANGE SHALL BEiO.1% OR BETTER.

14 . 2 EQUIVALENT BORON CONTENT, 4.0.

PPM SPALL BE S.CPPM.

6.1 THE 30 KG AMOUNT SHALL BE CON-SIDERED AS ONE LOT.

9.2 TEST DATA SPALL BE SUPPLIED ON -

URANIUM ISOTOPIC CONTENT URANIUMCONTENT, I?DIVIDUAL IMPUkITY LEVELS,AND MOISTURE CONTENT.

.

TABLE Al-IMPURITY ELEMENTS AfD MAXIMUMCONCENTRATION LIMITS.

.

P.CHC NOerww.S? LA.oesfC# ifsesLL)NG 4NSTRUCTIONS. RENDER INVO*CES IN TRtPLICATE:# " '"

P90VfSiONS CF TNE ATTACNED PURCNA5E ONCERNo. SMOwM A80vL ON TOUR INvosCE.

SUPPL EME NT CCN STfTtffE ATTACN OeicsNAL SILL OF LAOsNG ON ALL COLLECTA P ART OF Twes ORDEst SNsPMENTS AND SUPPORT ALL PREPAto FREIGNT av

CNARGES wtTN TNE ORtGIN AL P AIO FREIGNT sell ANOXAROMNR M XIAXf M X M su cr uo*NG-

-:,.. i =;; .. j .... Es....-,...... o,- . .sou...- .. ....

C o*v To

a.w..,.

l.),1 till |||| | | ll 1 lilt) !... g3. . ... ... . ... .... . .<s..

7-.......i....I AUTHOR- ~. _~ - , _ _. .,_ _C -3_

. , . . _--

__ _

_ _ .

.

. .

PURCHASE ORDER '"*o"''"7

* SMOW PunCM Ast om0ER NUMBERON ALL PACK AGES. jNVOICES AN o

Pacific Northwest Laboratories Co. cs.o ogNec. .

Sanelle Sc.'eurd.m P.C. 80s *99

'Cow Po rT E P A CMING Wsf MUSTACCO*PAMv EAcw sw P= rNT.

(( R.chland. wa,h.n g:on 99332

TO BE CON 5ID E R ED FOR FUTURE ORDERS - -- MEET YOUR DELIVERY COMMITMEN T5 I .

caoa= u-asa

. ... .. .... . . - . . . . . . ........, , , , , , , , , , , , , , , , ,

10 114 76 3 DOE - o -. e . -i 10990 AY*

s =^rv=L'sT- 7 1jC/o"

H an Cs_si..ecos.I ( Ric =L.= o, .a ...sa

OAK RIDGE NATIONAL LAS P

2I....Tca?,

T ...c.O t..C.L.~o... . .. n

2 as i=o.C.T eo e s ta=gi i

i...,. . . . . . . . . . . . . . . . . . . . . . , , . . ..,

15 ROGERS,

..... o , . . . . c. . .... . . . . . . .

....... ..- i o - . , . . .c . i . . . . . . . . . i.... i ...s.., t .. !.....v.... ......v.,................. .. ,,. ,.......

s,ca.c.no

THE LIMITS SHALL BE AS SPECIFIED IN TABLEi

I A1 EXCEPT AS FOLLOWS:! CARBON 150

IRON 500NITROGEN TOTAL NITROGENTHORIUM ANALYSIS NOT REQUIRED

SINTERABILITY TESTS - DRY PROCESS PERFORMANCETESTS AS SPECIFIED IN ASTMrC753-73 SHALLi

BE PERFORMED EY THE BUYER ON PATERIAL |FURNISHED BY THE SELLER FROM MATERIAL PRO-DUCED IN ACCORDANCE WITH THE SAME PROCESSAND PROCEDURES AS THE PATERIAL PRODUCED |FROM THIS ORDER OR FROM SAMPLES OF.PATERIALPRODUCED FOR THIS ORDER. PATERIAL ACCEPTANCEIS CONTINGENT UPON THE SUCCESSFUL DEMONSTRATION '

! 0F SINTERABILITY.t

.

*.

E ACIPC NCB1wwts? LA.CtalCf'E5esLLtNG ONSTRUCTIONS: RENCER eMVCeCES IN TRIPUCATE:

" "PuPOvlSuoast CF THE ATTACHED PuW MASE CRDER 's 80 Y R WO E*

*

SUP*LEufNT CONSTITUTE ATTACM CRtGINAL BILL OF LACPMG ON ALL COLLECTSMtPM(NTS ANO SUP'ORI ALL PRC P ato F REIGHT gy* a paRT or THes om0Est.CM ARGES WITH THE cRtGiN AL PARD FR[lGHT SdLL ANOsett.CF LADiNC6

****"*" 'kD8/"##" **.. ....os.,,j* *, ,";* .= .c c v , C, . . . . w /o . ..o s. . . .

C o.v T.,

i.......,o

l

1 1,1 till Illi l I i ll I li lti i !, .., '' ' *~**''',- .- ... ... .

. .. , Y,.,e 8.

AU HCR: . .. .. . n. . I

J. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _

|'

- _ _ _

_ _ _ _ _ .,

ATION.

BATTELLE N O RT H WE STSATTELtt usucasAL INSTITUTE PACIFIC hCATMwEST LAtonAfontESP O SOE 999. asCmLAND WA5mmCTON 99352 / TELEPmONE 509-942 6t19

| 109C-3_

-

THE ADMINISTRATION OF THE WORK TOBE PERFORMED UNDER THE TERFS OF ANYRESULTING PUFCHASE ORDER WILL BE'

DELEGATED TO MR. R.K. PARCHALL, WHO WILL -

ISSUE INSTRUCTIONS AS NECESSARY. .

THESE INSTRUCTIONS MUST IN ALL CASESBE WITHIN THE SCOPE OF THE PURCHASE

~

ORDER AND SELLER SHOULD WITHHOLDACTION ON ANY INSTRUCTIONS WHICH INSELLERS OPINION DO NOT MEET THISREQUIREMENT. MR. RK MRSHALL ANDMR. ES RINEHART SHOULDBE PROMPTLY NOTIFIED OF ANY INSTANCEkHERE, IN SELLERS JUDGMENT, THEINSTRUCTIONS S ELLER RECEIVED FALLOUTSIDE THE SCOPE OF THE PURCHASEORDER.

:1

I

Ii

-

.

.

*'_.

/ |* Jos A'

E. S. Rinehart, ManagerGeneral Purchasing

C-5o.~,.,

._ _- -.

- ___ - _ _ _ _ . _

.

i }*

| . , - . - .*

i . .,

I .

'PACKING' LIS?

.( f P.O. No 1o990 AY ,

.*

|. Manufacturer's Batch No. 30-2785

[-

455490 -Sampl:= lot Requisition Ho..

-

*.

. .- ;. ~ .r, - ., J y :

-

--- :- . .

-. .

. * - * .7,2:.'s.:.,,

; . - * -

c '.+'%&g.,.

i * . -

.,

W+.5, Q- * Q ;:E,.

- =.

| Container--No.+ . Schl-No. Gross Wt. (approx. ) Bottle No. 'G 7''T -- .SS Net"

_6M-096 19231 103,000'

it.s n erability 115 15 100 87.27.

sample6Lo96 19231 103,000 1 2632 192 2500 2181.786S O96 19231 103,000 2 2632 132 2500 2181.78-

6M-096 19231 103,000 3 2632 132 2500 2181.78,

6x-09S 19232 103,000 4 2632 132 2500 2181.78:

|. ! 6.42098 ,- .~ ..

!' - 6s og8 19232 ~ 103,000' 6. . 2632 .132, 2500 - 2181.7819232 103,000 - 5.

2632 132 2500 ' 2181.78 -.

! 65 131 19233 103,000 7 -2632 132 2500- 2181.786M-131 19233 103,000 - 8 2632 132 2500 .2181.78

*

'

6M-131 19233 103,ooo 9 2632 132 .2500 2101.78 -6M-132

'

19235 103,000 lo 2632 132 2500 2181.78! . 6M-132 19235 103,000 11 '2632 132 2500 2181.78'

'65 132 '19235 103,000 12 ~ 2784' 134 2650._ . 2332.69412,000 , 3185116013a250 .26399 54

.. .

* Round to 26,405--

,.

.,

-.- . . - . . . ._..m

. . ,

. . ,, , . . , -..

.,. . , . . . . . . . .

. . , . - .

| . . . _' ~:. ,

:| Note: All veights in grams - ., . [' .,,

*,

~ 7.) f,

*

. ,, , . . .

. . . . - -,-., . . ;. .:7. -_

*Conta$ner Packing' List '. .. E'.. Ei[-

' ,

. **Dcciudes Tape and labels , , . * $$5. ~ . . ,Q, 1'...* =- ' ' ' -. ; i.m. . . '::

' The 6M shijging containers are to be emptied and ret,urned to Y-12 Plant imediately, ,. .

.

, ,

.- u . e 4u,' .. . q-- '

, . .-

. . .. . . . -. -. . .

6 .

O

e

.

, , , . - % - O

, e

* '

C-6 '

. . ., ..

, -o~'-

. -.

,* * * O %,

. ,,...

w- n- e- + e - n ro*g ~,i~ 'w'~ w t994'

._.

p >-.

.

,

./".

*CEE4ICAL AUD PFYSICAL DATA

~

O Manufacturer's Batch No. 30-2785 -

" Sacple Lot Requisition No. 450490*.

P.O. No.10990 AY. . .

. . ;;;y .. .

Uranium Content (vt %) by Dichro= ate Titration. ,87.2715/87.h726(dry)-

* *.. . . . , ,

Isotopic Analysis (vt %) By Mass Spectometer u . ' .f , '.

';.

. - - t . 0. 07 ,y .,:: - ;.P. . ..- . 9gy_23g .. - . - . . . .

.

.. - ;.

~~E990L*;iffs*I*"

U-235 - ;U-236 0.08 -

U-238 . 89 95'

- - - - -

Total Nitrogen (ppm) 10.0,

2.

. Surface Ar'ea by Krypton Surface Method (M .gm)'. 'd.'63'"

~ '* ** *

.-.. .

Avg. Particle Size Fisher Subsieve Sizer (Micron).

2.16/2.12 (dry)*

- 5:00 ' -

O/URatio(Calculated)Carbon by Leco Analyzer (ppm) !$4" 54.0

~

H O (vt %) W J' O.23 ,2. .. -

- I .., ,

4

*

SPECTOGPAP3.IC ANALYSIS -

(ppm metal basis)- ~ *

--

,

,- ..

~

Ele =ent g EBC* Element ppm - EBC,

,,

- - * .. . . _.

'Al < 1.0 .< 0.0001 Mo - < 10.0 '< 0.00h03 0.2 0.2000 .N ' 10.0 .O.0190'

0.0002, Ni '* 2.0 0.0022C 5h.0 .

< 0.002 Pb <50 <.0,0002Ca < 10.0

. Cd < 0.1 < 0.0310 Si .< 10.0 < O.0010 . '.

Co . < 1.0 < 0.0090 Sn < 1.0 < O 0001 ..

Cr 20.0 0.0160 - Ta < 10.0 ' < 0. 0170Cu 1.0 0.0009 Ti -<h.O < 0.0072 ..re 90.0. 0.0630 - V- - < 1.0 < 0.0014

.

.

ng < 2.0 < 0.00008 w < 100.0 < 0.14 00' ^

nn 2.0 0.0058 Zn < 10.0 < 0.0020'

-,

,

.

~.

. .

Total EEO - < 0 5231

* Equivalent Boro:. Content'. .

.

'

!

C-7'

-,

.-

.

a

.

I

_ - . ._

....,

' It:,nitts Cor ugr,ji

~

Performed on Feb 25, 1977. .

by Hanf

' * * * *

f=)?..-

. .

.. ,

-.- -. .

. .

.

~ ,- ..

..

:,

.* -

,

,.,

.-

..-

.

.

. . ,

.

M . .'S . '! ' Lab ! Custome:- I . D. Wt. % (a) .'

-

|| n 0 (1 8 P '? a. 9.2 D6 '9 A 238.= H.f7 o. o 5.

'

236 = 00&3 o. oo 2-

,

. , .-

235 = c;,q y 9, ,, S

.

. 234 = orJiti 6 00 %~.

~~

238 = .

"

236 =.

235 =- '

..

234 = t

238 =.

236 =.

.

. . 235 = ..

.

234 = -.

, 238 =-

,

'''

236 = d -

.

235 =. -

.

.

234 = :

.

'(a) Uncertainties are the _95% Confidence Level .,

-

.

C-8 .

. ..

b

.

.

.

Sampi. Ideni,e. cat.aa Hanford Engineering 'a 5 " ' Na-

I FA-513 Development Laboratory P-9293Composite PowderFUELS AND CONTROL SAMPLE ANALYSIS Date Rec.

DB-922-17-77

Sample Submetter Address Phone Work Order No.

o Lester 308 E. TRL. 3184 C-98890TYPE OF MATERIAL: Special Instructions

p p

5.5 - DY, EU, GJ, Hf, Sim, Ba u ISOTOPIC: O NORMAL O OEPO eu 02 O Th 02 Q UO2 CO, W, P, B, V, ZR & Th a g% ENRICHED

.

0 MIXED OXIDE: %Pu O2

O B4C <0,5 PPM B ISOTOPIC: O NATURALO OTHERS O % ENRICHED

NO. OF ANALYSIS RESULTS NO. OF ANALYSIS R ESU LTS.

LOSS ONIGNITION WT %

DENSITY g/ccPuW T.%

POROSITY SEE SPECIAL REPORT

U WT.% 87 l8 SURFACE2AREA M /g gg

Th WT.%

PARTICLE SIZE SEE SPECIAL REPORT

241 Am ppm PARTICLE SIZE,FISHER SUBSIEVE

_

O/M 2.093 OTHERS particle Size - MIC

OTHERSC ppm ]gp

SPECTROCHEMICAL ANALYSR

S ppm SPARK SOURCEGENERAL SEE SPECIAL REPORT

OMASSPAR K SOURCE

#9R.E. + Ta + W + P SEE SPECIAL REPORT

EMISSION SPEC.] Cippm <}Q GEWERAL SEE SPECI AL REPORT

ISOTOPIC ANALYSESF ppm <$

Pu ISOTOPIC SEE SPECIAL REPORT

O H 0 ppm 19702

U ISOTOPIC SEE SPECIAL R EPORT

B ISOTOPIC SEE SPECIAL REPORTO ppm.

Special Observations-Remarks

SOLUBLE C WT %

3SOLUBLE*

BWT% O sci

O TOTAL C WT *Report Approved By Date Completed

3/11/,77TOTAL 8 WT %

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sa.o..-w o-w c_gg .

mb ..5ff Composite Powder Analysis Suninary

Sample - DB-92, Project IFA-513, 1.9% En. U02

*Specification

Impurity Maxime, ppm pom Present

Al 10) <50..

| C 100 162

Ca + Mg 200 <70

Cl + F 350 <l5| Cr 200 25

i Co 100 <1

Cu 250 <20

Fe 250 120

Pb 250 <10

Mn 250 <10

Mo 250 15

Ni 200 <50-

N 200 84I

P 250 30i Si 200 <60I

Ta 250 <2.4Th 10 50

Sn 250 <10

Ti 250 160

W 250 <2.4

V 250 0.02Zn 250 20

TOTAL 1500 967.

Analysis Specification Limit Analysis Result235

% U 10.0 0. 2 9.97 i 0.05^%U 87.7 min. (dry wt. basis) 87.18'2

.

Surface Area M /gm 6.7HO

. 4000 ppm maximum 1970 ppm20/M Ratio 2.093.

EBC 5.0 maximum 14.0

.?5.*

...;..

C-13!

.

M- + ---=% 7 e ----e r- er - , m4 e $r e a n

Lot 1 Composite, Sample DB 92, 9.9% Enriched U0 Powder, IFA-5132

Element EBC* Factor ppm Present EBC,

Al 0.0001 < 50 0.0050Ba 0.0001 <0.5 0.0001B 1.0000 0.13 0.1300 -

'Cd 0.3104 <2 0.6208Ca 0.0002 60 0.0120Cs 0.0032 <0.5 0.0016Cl 0.0133 <10 0.1330Cr 0.0008 25 0.0200Co 0.0090 <1. 0.0090

i Cu 0.0009 <20 0.0180Dy 0.0815 <1.5 0.1223Eu 0.4124 <0.5 0.2062Gd 4.438 <2.5 11.0950Hf 0.0084 <1.0 0.0084Fe 0.0007 120 0.0840Li 0.1457 <1 0.1457Mn 0.0034 . <10 0.0340Mo 0.0004 15 0.0060

i Ni 0.0011 <50 0.0550N 0.0019 84 0.1596P 0.0001 30 0.0030.

| Sm 0.5513 <i.5 0.8270Si 0.0001 <60 0.0060

,

Ta 0.0017 <2.4 0.0041,

Sn 0.0001 <10 0.0010i Ti 0.0018. 160 0.2880!- W 0.0014 <2.4 0.0034

V 0.0014 <5 0.00704

i Zn 0.0002 20 0.0040TOTAL EBC 14.0092EBC, less Gd and Sm 2.0872

(a) EBC = Equivalent Boron Content,

1

I

i'

.

-| .

r

C-14,

f

. . . c , .--.y _ . , , - _-....-m y. -

UO POWDER CERTIFICATION OF COMPLIANCl?2

.

Quality Control Release No. 1 (Conditional release; unconditional releasevill be issueo wnen ana. Lysis is conpleted.)

Project Halden-IFA 513.

Powder Lot Identification 1 Iot Size, kg UO2 30

Sa=ple No. DB 92

Applicable Specificaticos ASTM C 753-73 and Env Purchase order 10990 AY

,

Review of Analytical Data

The analytical data for. the UO p uder lot identified above has, . . .,

2- been reviewed and the reported. results ce= ply. vith the chemicaland nuclear requiresents of the applicable specifications, except forthose items noted below.Exceptions and justifications for release:

1. Carbon content is 162 ppm; spec limit is 150 ppm max. Vendor dataindicates 34 ppm C for this material. Previous experience withUO2 p uder containing C impurities in the range 100-200 ppm hasresulted in decreases of C content during sintering to less than<

50 ppm. The spec limit for C in sintered pellets is 100 ppm.2. Impurity analysis and EBC determination are not yet conpleted.

; Vendor data and partially completed analysis results suggest thatthis lot of material is very high purity. Final analytical resultsare expected before any pellets are sintered, so that the :::aterialvill still be in a form returnable to ERDA if it proves to be un-acceptable.

'' Date]~b~?7'

Signed "

* ''Approved Date.

|

| *

|

u

C-15

I

.

UO PO*dDER CERTIFICATION OF C0FTLIANCE2

Quality Control Release No. 2 ,

Project Halden-IFA 513t

.

Powder Iot Identification 1 Iot Size, kg UO2 30

Sa=ple No. DB 92

Applicable Specifications ASTM C 753-73 and BW Purchase Order 10990 AY

Review of Analytical Data

The analytical data fer. the. UO p vder lot identified above has2

been reviewed and the reported. results conply with the che=icaland nuclear requirements of the applicable specifJ. cations, withthe following exceptions:Exceptions and justifications for releases:

1. Carbon content is 162 ppm; spec limit is 150 ppm max. This item.

was covered adequately on Release No.1.2.Per cent uranium is 87.1E; spec limit is 87.7% min (dry vt basis).

This spec limit is designed to preclude. sintering proble=s due toexcessive shrinkage. Sintering tests with this powder have shownthat no sintering problems are present.

3. The equivalent boron content is 14 ppm; the spec limit is 5 ppm.The analytical lab is having problems with achieving the usual lowdetection limit for rare earth elements of less than about 0.3pps.

For this sa=ple, detection limits for Gd and Sm vere 2.5 and 1.5ppa respectively. 'Jithout the Gd and Sm EBC values, the total EBC

' of this sample is 2.1 pps. It has been estimated that even if theEBC of this material is as great as 14pp=, no significant effectsvill occur as a result, for this irradiation experiment.

[// / Date M '77Signed / .

Aoproved Date

.

I-16

:

SINTERABILITY TEST PLAN

h Prepared by N. C. Davis .Date 2-22-77/ 2 '- ''

Approved by O. W. Brite [k8]d Test No. 1556

.

I. Purpose of Test. The purpose of this test is to determine the process235parameters and sintering characteristics of the 10% U U0 btained

2for the-IFA 513 fuel pellet program. Specifically, a high density (95% TD)*

with a stable structure is required. Density and dimensional results willdetennine; process parameters, press tooling and the need for additionaltesting. Normal processing shall be followed to the extent possible with

this new lot of UO2 powder.

II. Reference Tests. There has not been any previous experience with this lotof 00 . The chemical and physical data furnished by the powder supplier is

2attached. The powder lot has been sampled for additional and confirmingdata to assure confonnance to specification p. ior to release for this IFA-513program.

The manufacturer's data, and the physical appearance of this powder indicates235

f a similarity to a lot of 93% U , UO2 p wder obtained from the same source,~

(Oak Ridge National Lab.). This powder was recently processed in Tests No.1551 and No.1552. Although this new lot of 10% powder has a higher specific

2 2surface area 6.63 M /gm as compared to 3.1 M /g for the 93% powder, thecoarse granule appearance of the two' powder lots is very much alike. In thereference test final density of only 92% was obtained, indicating specialprocessing, such as Ball Milling would be necessary to increase the. sinter-ability. This may not be the case with this 10% powder having the highersurface area and for the first test normal processing should be followed.

.

III. Material Recuirements. The sinterability sample of 100 grams provided bythe manufacturer, will be used in this test. Approximately 10 pellets canbe made with existing pellet press tooling.

.-

IV. Special Instructions.

To provide additional data on this powder lot, the tap density, and particle' size, sieve analysis should be obtained before proceeding with the following .

,.normal process steps.

8

C117

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_ _ _ _ _

Granulate if required to force all powder to pass a 100 mesh screen.*

*- Slug powder in the 2" slugging die, using low pressure (N 3 tons),3

target density uf 4.3 0.1 gms/cm . Record pressure, dimensions and'density and procede to granulate and use the slug regardless of the

density obtained. '<

Blend 0.3 wt/% sterotex lubricant to the -20 mesh granulated powder.* *

Press pellets (s10 grams each) in the existing pellet die (normal 0.472"*

diameter pellet), using a pressure range of from 2.5 to 5 tons. The3target densities sh'ould range from 5.0 to 6.0 gms/cm . Record pressure, *

I dimensions, weights and calculate the green density. Bubble test forintegrity and idenify each pellet.

Recover all scrap (hand feed the press for these 10 pellets to prevent*

scrap powder).

* Sintering parameters" * Heating rate N100 / hour

Soak - 8 hours at 1700*C : 20 C*

Furnace coal*

.

H to the furnace to bubble thru-water*

2

Record furnace amperes and time with clamp on recorder.*

V. Test Evaluotion.

Record the as-sintered weight*

Record minimum diameter of pellets*

Grind peklets to a clean-up diameter*

.M.easure, weight and, record density*

Break a pellet to visually axamine microstructure*

Record recommendations for re-test or for processing.*

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C-18

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Sinterability Test No. 1556 Sheet 1 of 2

10L Enriched UO ; Manufacture's Batch No. 30-27852

(E (1) Determine tap density3 3100 g/37 cm = 2.7 gm/cm .

.

(2) Screen analysis of as received particle size'

Screen Size Amount Percent,

- 40 + 70 3.0 3.0

- 70 + 100 33.5 33.5

-100 + 140 16.5 16.5

-140 + E00 18.5 18.5

-200 + 325 18.5 18.5

; - 325 10.0 10.0

100.0 100.0%

(3) Above 100 gram - sample reduced to pass through 100 mesh screen, as slugged>

all - 100 m.(4) Slugged in 2" dig at 3 ton pressure

Diameter Length Weig'ht Oensi tyinch inch grams g/cm3

2.010 0.517 100 3.72- (5) Granulated - 20 mesh and 0.3 wt% sterotex blended to lubricate powder - 100 m

*

j sterotex.

(6) See page two for pressing and sintering data.

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Sheet 2 of 2.

.

Sinterability TestDate: 2-24-77

.

Powder Identification and Preparation:\;;-

10% Enriched 007 For Project IFA-513 - fianufacturer's Batch No. 30-2785

See Sheet 1 for powder preparation *

'

Slug Data: Quantity 100 g

Giameter Length Weight Density3

2.010" 0.517" 100 grams' '3.72 g/cm

1700*C'- 8 hours

Sintered Run Humber 1556

Sintered Pellet see belowGreen Pellet

Green Diameter 0.472 Dish V.V. 0.026 Sintered V.V. 0.011

Calculation Factor 2867 Calculation Factor see below

Green Height 99.2 a Sintered Height 97.3 g

.-

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Sinter Ground'

ressure Pellet length Meight Bubble Density Diame- Oiame- Length g/cm3tons t'umbe r " inches" arams Test a/cm3 ter ter " inches" Heicht Density

2.2 1 0.668 9.440 OK 5.00 0.366 0.3630 0.51 6 8.996 10.41

2.5 2 0.628 9.058 OK 5.10 0.370 0.3687 0.488 8.830 10.48

2.9 3 0.709 10.469 OK 5.21 0.372 0.3704 0.555 10.177 { 10.503.0 4 0.662 9.932 OK 5.30 0.374 0.3705 0.522 9.555 | 10.483.0 5 0.701 10.506 OK

~

5.29 0.374 0.3704 0.553 10.111 ! 10.47

J.4 6 0.606 9.226 OK 5.39 0.377 0.3741 0.477 8.931 10.53

3.6. 7 0.679 10.474 OK 5.45 0.378 0.3766 0.540 10.236 10.50

3.8 8 0.650 10.051 OK 5.46 0.378 0.3766 I 0.51 6 9.772 10.50

4.2 9 0.568 8.984 OK 5.60 0.381 0.3784 0.455 8.705 10.52

5.5 10 0.667 11.014 OK 5.80 0.386 0.3843 0.540 10.686 10.53

.

iote 1 All pell et bubbl e tested- in alcohdl satisf actory.

2 Measuring devices and ba' ance in current c ilibratic n system

3 Visual i nspectio ,of pel' ets acceptable

4 Apparently green pellets pressed E .0 g/cm or greai er will y . eld sintered

density of 95% Th or greater, whed, sintere, 1700*C for 8 hou s.

C-20 '-

.

Date 2-25-77.

|jfs EVALUATION OF SINTERABILITY TEST - 1556.

The first sinterability test (1556) of the 10% Enriched U02 powder for the IFA-513,

project was successful. The following observations and recommendations are basedon the test results and the proposed parameters for processing.

,

eNormal processing without any special powder pre-treatment is apparently*

adequate to produce sintered densities greater than 95% TD.

The pellets visual inspection indicated high quality without excessive cracks*

or chips. The appearance of the microstructure of a broken pellet showeduniform, apparently stable structure.

Recommend a pre-production test to conf.irm these results with an existing*

i die and flat faced punches, that wil1 produce dimensions within the specifi-,.

Samf e pellets should 'be drilled for the required-TC hole and' lcation limits.

variations should be made with the sterotex to reduce the density approximately

0.5%.

A final pre-production test should provide data for the processing parameters*

,

and limits needed to produce the pellets for the IFA-513 program.i

This test plan is being prepared and will be made on approval and Quality*

Control release of the powder lot.

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PRE-PRODUCTION SINTERABILITY TEST PLAN

'

Prepared by N. C. Davis .'~' Date 3/4/77

/ft[Approved by D. W. Brite Test No. 1559

.

I. Purpose of Test. The purpose of this test is to determine the final

fabrication parameters necessary to produce the 1FA513 fuel pellets.Previous tests will be refined using the correct tooling size toobtain the specified dimensions and density.

II. Reference Test. The previous sinterability Test No. 1556 will beconfirmed in this pre-production test. In the previous test, this

23510% U , Oak Ridge powder was determined to be highly sinterablewith normal processing.

III. Material Reouirements. In order to test this powder with two

amounts of sterutex, approximately 200 grams will. be required.

IV. Soecial Instructions. The previous sinterability Test 1556 pro-vided data on tap density and sieve analysis for this lot of U0

2powder. This test also indicated that normal processing shouldbe adequate for making production pellets. The following stepsshould be followed for this confirming pre-production test:

Granulate "as received" U0 to pass a 100 mesh screen.*

2

Slug the 200 grams of powder in two 100 gram increments,*

using the 2" die and s 5 ton pressure. This is an increasefrom the 3 tons used on the previous test which only yielded

3a slug density of 3.7 g/cm . Record slug size and density.* Granulate the slugs to -20 mesh and again split into two

100 gram increments.

* Blend 0.3 wt% sterotex with one increment and 0.4 into theother. *

.

C--2 2

(jjt.:* Press pellets {s 10 grams each) with existing pellet die

(nonnal 0.541" diameter pellets with flat ends) using a pres-.

, sure range of from 3 to 5 tons. The target density range3should be 5.2 + 0.1 g/cm . Record pressure, dimensions,

O

weight and calculate the green pellet density. Bubble testfor integrity and identify each pellet.

* Drill two of the green pellets with a No. 43 tungsten carbidedrill 0.089".

* Sintering parameters -

* Heating rate s 100*/ hour* Soak 8 hours at 1700*C + 20*C* Furnace cool.

H to furnace to bubble through-water.*

2* Record furnace amperes and soak time with clamp

on recorder.

V. Final Test Evaluation.* Record the as-sintered weight of pellets.* Record minimum diameter of each pellet.* Grind pellets to clean-up diameter.* Measure, weigh and calculate density..* Break a pellet to visually inspect microstructure.* Record results and recomendatioris for production.

! * Prepare production process parameter sheet for approval.

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Pre-Production Sheet 1 of 2Sinterabil.ity Test

Date: 3-7-77

Pouder Identification and Preparation:o

235~

Proiect - IFA-513. 10% U U0; oowder MFa Batch 30-2785,cranulates as received powder- 100 mesh, slu'a 5 ton'in 2'in.' sluacino die, oranulates - 20 mesh, blend 0.3 wt %

*Sterotex to 100 crams to 0.4 wt % Sterotex to 100 grams

'

Slug Data: Quantity 200 grams

Diameter Length Ueight Densityd2.01 0.503 100 grams 3.8 gm/cm

2.01 0.509 101 grams 3.8 gm/cm'

Items 1-9 (below)w/0.3 wt% Sterotex 1700*C '8 hoursItems 10-18 (next page) w/0.4 wt:

Sintered Run ?! umber lEEg

Sintered Pellet See belowGreen PelletGreen Diameter 0.541 Dish V.V. NA Sintered V.V. NA

Calc,ulation Factor 37668 Calculation Factor See below

Green Weight 201 Sintered Weight See below

Sinter Ground'

Tons Pellet length Weight Bubble Densi!;y Diame- Diame- Length g/ce,3Pressure t! umber " inches" arame Test o/cm3 ter ter " inches" Weicht Density

3.7 1 0.506 |0.985 ok 5.24 0.428 0.4249 0.398 9.673 10.46

3.7 2 0.545 10.697 ok 5.21 0.427 0.4246 0.427 10.387 10.4e3.7 3 0.625 12.234 ok 5.20 0.427 0.4244 'O.489 11.540 -----D

3.7 4 0.625 12.241 ok 5.20 0.427 0.4244 0.490 11.873 | 10.454.2 5 0.504 10.304 ok 5.43 0.432|0.4303 0.402 10.033 1 10.47

4.2 6 0.506 10.344 ok 5.43 0.433 0.4304 0.403 10.071 |10.482.8 7 0.548 10.337 ok 5.01 0.422 0.4191 0.425 10.014 10.43

2.8 8 0.541 10.221 ok 5.02 0.422 0.4191 0.420 9.906 10.44

2.9 9 0.683 |12.869 ok 4.89 0.421 0.4186 0.529 12.474 10.45

.

NOTES 1 Pellet 83 drilled w/ d43 drill 0.CB9 in., as sints red 0.069'in.2 All celle ts measu ed and d eichedwibhcalib ated toc is of balknce. *

3 Allcellebscrackandchipfree,all passed lubble Test. |

4 Greendenbityof 5.2g/cd3 yieldsksinteraddensidyofs10.46or95.4% TD vhenusing0,3wi%Sterotek. *

|C-24 |

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* - Pre-Production Sheet 2 of 2Sinterability Test

Date: 3-7-77L

._ Powder Identification and Preparation:{U2 - -1

* Proiect 1FA-511.'10Y U235""

00_ onwder MFa. Batch 30-2785. (See Sheet 1)'

. . . .. .

o

"

Slug Data: Quantity 200 grams

Diameter Length Weight Density

See Sheet i -

_ ,

Pellets below Items 10-18 w/0.4 wt % Stenox

1700*C - 8 hours

Sintered Run Number 1559

Sintered Pellet See belowGreen Pellet _

Green Diameter' O.541 Dish V.V. NA Sintered V.V. NA

Calculation Factor 37668 Calculation Factor See below-

_

| 6 een Weight 201 Sintered Weight See below

. . . . .

I Sinter GroundTons Pellet length Weight Bubble Density Diame- Diame- Length g/cm3

PressureNu=Ser " inches" grams Test a/cm3 ter ter " inches" Ueicht Densitvi 3.2 10 0.550 10.630 ok 5.13 0.425 0.4220 0.431 10.287 10.41 --

3.2 11. 0.595 11.489 ok 5.13 0.425 C.4218 0.465 11.120 10.441

{ 3.6 12 0.584 11.458 ok 5.21 0.427 0.4247 0.459 11.125 10.45

! 3.6 . 13 0.575 11.306 ok 5.22 0.427 0.4245 0.453 [ 10.627 Drilled'

.

| 3.7 14 0.583 11 ~.461 ok - 5.22 0.427 '0.4246 0.458 11.120 10.46

3.9< 15 0.568 11.333 ok 5.30 0.429 0.4274 0.448 11.031 10.47.

#

3 .,9 16 0.564 11.265 ok 5.30 0.430 0.4275 0.446 10.970 10.46>

5.1 17 '0.534 11.310 ok 5.62 0.437- 0.4340 0.431 10.936 10.46-

4.5 18 0.569 11.735 ok 5.48 0.434 0.4305 0.455 11.334 10.46 '

. |"

i _~ 1

*.

NOTE 1 Pellet #13'drille i w/ #43 drill.3

2 Apparentl y with 0.4 wt/% - Sterotex when pel' ets are pressed to 5.13 g/0m. . .,

_(above 10 and 11) the rest,1 ting density wil' be 95% or greater--very l' ttle

difference from t1e 0.3 wt% Sterote<.~

|TCholesizeassinteredpellet no. 13 was 0.069 in.3-

4

.C-25

....:..... . . ;. -J

* -e -r r--,- - - " --r

I

3/10/77*

EVALUATION OF PRE-PRODUCTION TEST 1559

.

The pre-production test (1559) of the 10% enriched UO f r the2

IFA-513 project was successful. Density and dimensional results pro-vide assurance that parameters can be established to fabricate theIFA-513 pellets. The following observations and connents are based onthe test results and the proposed parameters for processing:

A visual inspection of the pellets indicated good physical integ-*

grity. The cross section appearance of a fractured pellet showed'

uniform microstructure.

Normal processing without any special powder pre-treatment isapparantly adequate to achieve sintered densities of 95% orgreater. However, all the as received powder should be reducedthrough a 100 mesh screen to assure uniformity.

* The press tooling used in this test is satisfactory for the produc-tion of the 1FA-513 pellets. As pressed they are 0.541 inch diam-

3eter and if pressed to approximately 5.15 g/cm density and sin-tered 1700*C for 8 hours, they will reduce s 21.5% in both diam-eter and length. This will allow s 4 mils .to clean up the requireddiameter of 0.4205".

* The as pressed length should be held to 0.636 1 010 to maintainthe specified sintered length of 0.500'.

1

* The drill used for the TC hole #43 produced a final ID of 0.069which is within the specifications.

* Little diffe ence in thc final density was observed in the use of

0.3 or 0.4 wt% sterotex. It is difficult to obtain meaningful,

results in a small test; however, the larger amount of the pore-~

forming additive is recommended in this highly active powder..

a

C-26

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Extremely uniform distribution of this sterotex will be necessary tomaintain the 95 + 0.5% density specified.

s*

The process parameter sheet and density content charts are beingprepared for approval and release for production.

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Date 3/10/77. .

Pellet Fabrication Pro: css Para:.ictersOak Ridge Batch No. 30-2785

.ProjectIG-313 Powder lot No. - Enrich:r.cnt 10t Re l eas e, ,,,__,,, ,, ,,,,

.

PW+it Specifications: Reference. C.R. Hann letter 0.W. Brite IF_A _513 pro. ject;/D_/77,

- Ocnsity Diameter Lcngth DishDimensiged2[pplica ticn gyn_tig i 0. St t 0.0005" t Os 015" Spherical R. t 0.02 Ogt,htOdO2_ *

IFA-513 Flat ends with _ _ _ _:

.

Drilled 120 95 0.4205 0.500 T.C. centerline hole 0.067-0.071" *

IFA-513

Solid 375 95 0.4205 0.500 Flat ends no holes .

Total 495

Pcwder Preparation: Maximum Batch Size: 560 grams fissilel

Powder Bler. ding Time: N.A. reduce to -100 mesh3Slug Dantity 3.8 +0.1 g/cm Slug Size 100 9 Control Chart plot s lot$

Nanula te, -20 Mesh: Lubricant 0.4 t_0.1 Weight %~

Special Instructions: Blend'-100 M sterotex to -100 mesh UO., powder fines as a master blend

then_ add _to..halance of -2n grannlatad nnwdar and en11 nn.will in minnt.e

. . . - - _

't Pressing and Sintering,

3Gr:ren Cinsity__5.15 + 041 or.-/cm Length 0.636 ! O 010 Control Chart *nlot s 10;_,,,,m_,

Press Tooling Use flat facg.Dunches and cellet die that oroduces 0.541" diameter nellet.

. . - .

Sintering Heating P. ate _ s 100*/ hour Maximum Temperature'1700 t 20 *C: Time e Hours

Cooling Rate furnace H Flow 10 CFH Purge aroon2

special instructions: * Identify all pellets while areer with consecutive numbers to fully,_ characterize final sintered pellets. Drill 120 Dellets with No. 43. 0.089" tunosten

carbide drill.

Grind pellets in accordance with above diameter specification, clean in Ultrasonic Alcohol Eathond dry 100*C t 10''C for one hour. Inspection in accordance with Batch Inspection ' ample plan.s

Co=nen ts : Identify archive samples - 8 drilled and 31 solid; take analytical and *

micrestructure samples as specified.on 1FA-513 specification sheet.

P

Date: 3/10/77 Approved by: D.W.Brite[ ate: 3/14/77'

P(jredby: N. C. Davis")'

-

* Process parameters as listed are based on final sinterability or pre-production Test Results.

(Attachea) ' #1559 ~ Program Leader Approval /

C -28-

Pellet Fabrication Follower Data Sheet.

Dale.L~'..!d'_Z2-.

!(I.' Project [[/9 - f/._3 f.ot t! umber (@$ Rei c as e,__2. __Enri chment6

Powder Preperation: ** .

o Slug Density 3 , 2T 7O 3 , '7 Sl ug S'i ze - /CO eh,' __

f

(Control chart attached). Granul a te 3d__7 /, -20 + 100 mesh j/A- -100 mesh pft._ Re -s l ug

1.ub ri can t ,4 % w/o sterotex / 4/, f orams 3624, grams U02/Veg 3629

Blend /[ hin. Ope rator

Comments /fMSt-h Os fr4Leh 4:51 /.2f' b|RfD 4./Yl/3 dr>2L bb/#

_tuelc%/ S.TSAf4 k.i El STZ 94.-I h.r.rNI

Pellet Pressing: Batch No. / Identi fi cation #f),

Green Densi ty - f. /T' Green length '''. d Y Quanti.ty f)-d //th-/'(See control chart attached)

Pellet Sintering: Furnace Run No. /f'[d Date 3 '.2/-7 7Time P' //M Temperature /74# Pyrometer /7/O

"'t )Average Pellet Diameter (), /[2 f- O [[Z f- Batch Weight [2.f7-f

Operator M

Pellet Grindina: Speci fied Diameter O/? o t/,s d- O. <,C?o f - '##

Batch Weight [$[[ -v I L d7 ow. ,' ,/ jdds~_I

Operator A/ ~

Pellet Cleaning & Drying: '74.ktb ' C ose/ ,vsse Alco/c[ eb U LLs - ~# em W~~0ttrek .11ew s st~ f0*C fioned Ron Ows/ Doera tor JV R,

Batch Inspection: /o, #/ Diameter /, o %. Length A//2- Dish /e o[ Density, , -

o Jaa y Visual fra % Chips & CracksAnalytical :'DD- 92. cedb Composite Y IsotopicV Chemicak

'i

D*0 -9)o 4'l + 'l S * JWOxygen /UraniumY . Urani u: :V |

'.

Commen ts mM At vm /m <j ,t-- / en y tL / u n a.a J.s n ,a. , ) ./ , !

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Applied Chemistry and Analysis.r ,.- .-

'o.... QP2EL I I, 1977- -

p s.y.e . ISOTOPIC Ah'ALYSIS OF URANIUM,.

' .

ANALYZED O p j? /t il 197),

lianford Engineering Development Laboratory"

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_].IJ2028 P 1387- D 0 93 233.= 9 9.9 9 e 005*

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236 = 0.076 0 0d4 -*

,

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- 235 = 9. 8(o 0.05 - * ~. .

.,

(" 234 = 0.olo 9 0,oof

.|IJJ079 P93&Y D L5 9 V ]~

. 238 = 79 9f o,u s .

'

236 = o.o N o , co '/'-

.

" - 235 = 9.9 o ~ o .4, s'.

.

'

234'= 0 070 0.co*f

I] 2 Jo Eru P 9Jn . OB M 238 = fr9.9fr o.o s-.

.

236 = 6,676 .* O' ###/ .. .

.

235 = 4.f7 Ceo5- ...,. , _

234 = 0.07.2 0, oes / -c*

' '

. 233 , .

- - .

*-

~-. . . .

.,

. 236 =.

235 = t. -.

.

.I 234 =0

d//- m/[MUncert5intics are the 95% Confidence Level. Approved: ~

c.

C-31-

*

..' g

--- -

_ _ __ __ _

|:

,

.Lot 1, 9.9% Enriched U0 Pellets. IFA-513

2Sample Identification - 08-93

^ *EBC and Imourity ContentBoron ppm Max. ppm Meets Spec.

Impurity Eautvalent Present EBC Allowed Yes No,

.

A1 0.000122 <50 0.0061 300 xBa 0.000122 <0.2 0.0000Be 0.000015 <2 0.0000B 0.999999 0.2 0.2000 1.5 xCa 0.000153 <25 0.0038 100 xCd 0.325Q97 <2 0.6502C Q.000004 25 0.0001 100 xC1 0.0132 <10 0.1320 25 x'

Cr 0.000799 25 0.0200 500 xCo 0.009239 <Q.3 0.0028Cu Q.000868 <20 0.0174 50 x -

F 0.000007 <5 0.0000 25 xHf 0.00084 <0.6 0.0005Fe 0.000672 70 0.0470 400 xPb 0.000011 <10 0.0001 20 x

; Hg 0.000040 10 0.0004 50 xMn 0.003443 <10 0.0344 10 xMo 0.000403 <10 0.0040 150 xNi 0.001122 <50 0.0561 300 xN 0.001924 11 0.0212 75 x0 Neg.P 0.000087 10 0.0001'

St 0.000066 <60 0.0040 400 x,

Ag 0.008236 <10 0.0824 30 x'

Sn 0.000072 <10 0.0007W 0.001496 <3 0.0045V 0.001406 <Q.5 0.0007 2Zn 0.000241 <20 0.0005 20 xZr 0.000029 <0.5 0.0000Sm 0.524575 <1.5 0.7869'

Eu 0.433973 <0.5 0.2170Gd 4.19458 <1.5 6.2919Dy 0.097064 <1.5 0.1456

8.7304 4 x,

Less Gd and Sm 1.6516

*

.

C-32

'..

. _ , , ..

h Lot 1, 9.9% Enriched 00 Pellets IFA 513 Sample 0B-932

, CALCULATION OF HYDROGEN CONTENT

Total hydrogen is calculated by assuming all gas collected byvacuum outgassing at 1600*C is hydrogen, plus calculation of thehydrogen contained in moisture released at 400*C.,

3OFFGAS ANALYSIS RESULT = 0.009 cm /g 002

63 2 x 10 pg g 0,804 pg H0.009 cm 2 2*

g U0 3 g U02 22,400 cm . 2

<5 pg H 02MOISTURE CONTENT =

g UO2

.

<5 pg H O 2gH 0.556 pg H2 2 2

-

g UO ' ' I8 9 N 0 * i U02 2 2

TOT /L H CONTENT = 0.804 t 0.556 = 1.36 pg H /g 002 2 2

_

4*

!

|

{.; :..

C-33

.

- - - 9 -y_ m y

. . . __ . . - - . - - - - . . - - . - . _ - . . - - _.. _..

i

SAMPLE - DB 94,

ANALYSIS SUMMARY, EBC AND IMPURITY CONTENT,

Boron ppm max, ppm Meets Spec. ei Impurity Equivalent Present EBC Allowed Yes No

A1 0.000122 <50 0.0061 300 xBa 0.000122 <0.2 0.0000Be 0.000015 <2 0.0000 ,

,

? B 0.999999 0.3 0.3000 1.5 xCa 0.000153 <25 0.0038 100 xCd 0.325097 <2 0.6502C 0.000004 47 0.0001 100 xC1 0.0132 <10 0.1320 25 x

'

; Cr 0.000799 25 0.0200 500 x: Co 0.009239 <0.3 0.028i Cu 0.000868 <20 0.0174 50 x2 F 0.000007 <5 0.0000 25 x

Hf 0.00084 <0.6 0.0005 -

I Fe 0.000672 65 0.0437 400 xPb 0.000011 <10 0.0001 20 xMg 0.000040 <10 0.0004 50 xMn 0.003443 <10 0.0344 10 x

4

! Mo 0.000403 <10 0.0040 150 xi Ni 0.001122 <50 0.0561 300 xi N 0.001924 <10 0.0192 75 x| 0 Neg.

P 0.000087 2 0.00022

Si 0.000066 s50 0.0040 400 x<

| Ag 0.008236 <10 0.0824 30 xd Sn 0.000072 <10 0.0007

W 0.001496 <3 0.0045j V 0.001406 <0.5 0.0007 2

Zn 0.000241 <20 0.0005 20 xZr -0.000029 <0.5 0.00003

Sm 0.524575 <1.5 0.7869Eu 0.433973 <0.5 0.2170Gd 4.19458 <l.5 6.2919

! Dy 0.097064 <1.5 0.1456

8.8252 4 x

.Less Gd and Sm 1.7464=

. .

f

- '

1

i

C-34

- - - - _ . . -- _.. - . - . . . - . - . - . . - - - . - . . , . - - , --

c-

-

([ Lot 1, 9.9% Enriched UO Pellets, IFA 513, Sample DB 942

CALCULATION OF HYDROGEN CONTENTe

Total hydrogen is calculated by assuming all gas collected byvacuum outgassing at 1600*C is hydrogen, plus calculation of thehydrogen contained in moisture released at 400*C.,

3OFFGAS ANALYSIS RESULT = 0.007 cm /g U02

63 2 x 10 #g g 0.625 pg H0.007 cm 2 2"

g U0 3 g U02 22,400 cm 2

<5 pg H O2MOISTURE CONTENT = g 00

2 -

<5 pg H O 2gH M9 N2 2 2g 00 18 g H O = 0.556 g 00

2 2 2

f TOTAL H CONTENT = 0.625 + 0.556 = 1.18 pg H /g 002 2 2

,

W

e

k.:.: :,

C-35

.

- __ __ . -

SAMPLE - DB 95

ANALYSIS SUMMARY, EBC AND IMPURITY CONTENT

Boron ppm Max, ppm Meets Spec. ,Impurity ' Equ'aa lent Present EBC Allowed Yes No,

A1 0.000122 <50 0.0061 300 xBa 0.000122 <0.2 0.0000Be 0.000015 <2 0.0000 *B 0.999999 0.3 0.3000 1.5 xCa 0.000153 <25 0.0038 100 xCd 0.325097 . <2 0.6502C 0.000004 21 0.0001 10C xC1 0.0132 <10 0.1320 25 xCr 0.000799 25 0.0200 500 xCo 0.009239 <0.3 0.028

; Cu 0.000868 <20 0.0174 50 xF 0.000007 <5 0.0000 25 xHf 0.00084 <0.6 0.0005 -

Fe 0.000672 80 0.0538 400 xPb 0.000011 <10 0.0001 20 x,

Mg 0.000040 25 0.0004 50 xMn 0.003443 <10 0.0344 10 xMo 0.000403 <10 0.0040 150 xNi 0.001122 <50 0.0561 300 xN 0.001924 14 0.0269 75 x0 Neg.P 0.000087 2 0.0002Si 0.000656 <60 0.0040 400 x

! Ag 0.008236 <10 0.0824 30 xSn 0.000072 <10 0.00074

i W 0.001496 <3 0.0045V 0.001406 <0.5 0.0007 24

Zn 0.000241 <20 0.0005 20 xZr 0.000029 <0.5 0.0000Sm 0.524575 <1.5 0.7869

'

Eu 0.433973 <0.5 0.2170Gd 4.19458 <l.5 6.2919Dy 0.097064 <1.5 0.1456

8.8460 4 x

Less Gd and Sm 1.7672=

,

C-36

|.

s

e

r

Q.(Lot 1, 9.9% Enriched U0 Pellets, IFA 513 Sample DB 95

2

a CALCULATION OF HYDROGEN CONTENT _

Total hydrogen is calculated by assuming all gas collected byvacuum outgassing at 1600*C is hydrogen, plus calculation of the

a hydrogen contained in moisture released at 400*C.

3OFFGAS ANALYSIS RESULT = 0.008 cm /g U02

63 2 x 10 pg O'.714 pg H0.008 cm 2

*

g UO2 22,400 cm g U032

.

MOISTURE CONTENT = 7 pg H 0/g 002 2

7 pg H O 2gH2 2 = 0.778 pg H /g U0g U0 18 g H O 2 22 2

. = . .

TOTAL H CONTENT = 0.714 4 0.778 = 1.49 pg H /g 002 2 2

.

.)-

(

(??~C- 37,

i'

i

e

_

UO PELLET CERTIFICATION2a

Project IFA 513 Ealden Fuel Pellet Fabrication

'Pellet Lot No.1

Pellet Batch No.1

Applicable Specifications: ASTM Specification C776-76 and memo, C.R.Eannto D.W.Brite, February 17, 1977.

Review of Inspection Data

The fabrication impection and analytical data for this lot of pelletshave been reviewed ar uth the exception of EBC, they conform to theabove referenced specifications.

The EBC values calculated for three pellet samples from this lot were8.7, 8.8, and 8.8 ppa. The specification limit is /. ppm maximum. The reasonfor these high EEC values is believed to be current problems in achievingthe usual lov detection limits for Gd and S= of about 0.3 ppm. The detectionlimits reported for these samples for both Gd and Sm were 1.5 ppa. The EECvalues without Gd and Sm were 1.7,1.7, and 1.8 ppm. It has been estimatedthat even if the ESC is as great as 8.8 ppm, no significant effects on theirradiation experiment vill occur.

i b Date~

Signed / '

Approved - Date

s

%

C-38.

i

.

4

&

APPENDIX D

PELLET DATA

s

%

,

. , .. ,,

TABLE D-1. Pellet Data for Rod _, IFA-513

PELLtf PttLE7 DIAMEttR LtNGi> vis10 aEIGmi OEN51Tf DENSilYPUSIfluN NOFHtw (INCHt8) (INCNt5) Di& HETER ( r.) (G/CC) ( 1 TU)

0-1 0-2 D-3 L-1 L-2 (INCHES)1 1 4205 4206 4207 .d920 .a92u .0700 11.382 10.81 95.J12 120 .e205 4205 4207 5020 .5020 .0700 11.50e 10.41 94.973 7a 4207 4208 4209 .seeo .5000 .0700 11.523 10.41 95.004 58 420s 420e .a206 .a9a0 493u .0700 11.375 10.81 94.945 lin .edu? 4207 .a20s .ageo .eveo .0700 11.375 10.39 94.836 7 42n2 4203 42 %e 494u 493u 0700 11.337 10.39 94.827 5 4205 4205 420a .ag90 .e990 .070n 31.s91 30.cl 9a.978 77 4208 4207 .a207 .5000 .5010 .0700 11.559 10.42 95.129 512 420e .u206 42n7 4890 .ns90 0.0000 11.e04 10.42 95.0a

10 aa3 4205 4207 4207 .e990 8880 0.0000 11 621 10.e5 95.3211 at? .a20e 4204 4203 .5000 .5010 0.0000 11.842 10.a0 9a.9212 165 4206 4207 4208 .a960 4950 0.0000 11 763 10.42 95.0913 336 4206 .e207 4208 .5020 .5020 0.0000 11.909 to.at 95.02to 450 4205 4206 .a206 .a910 4900 0.0000 11 613 10.a0 ge.89

15 491 4206 4204 .edul .a950 0950 0.0000 11.735 10.42 95.0816 277 .c204 4203 4202 .5060 .5050 0.0000 11 971 10.42 95.00

17 163 4204 4206 .a207 496u .4950 0.0000 11.756 10.42 95.0918 330 .a208 4206 8205 .5030 .5030 0.0000 11.926 10.41 95.0019 329 4208 4206 4206 .5060 .5950 0.0000 11.999 toast 95.0920 389 4205 4203 4202 .5010 .5010 0.0000 11.e78 10.43 95.132i 45p 4207 .c207 6203 4900 .e910 0.0000 11.619 10.41 94.98

? 22 357 4205 4208 4206 .5040 .5u40 0.0000 11.954 10.42 95.0323 131 4207 .c208 4207 .s950 .a960 0.0000 11.711 10.37 94.65ra24 23a 4206 4205 4205 4940 093u 0.0000 11.719 10.43 95.1925 265 420e 8205 4204 .5000 .5000 0.0000 11.851 10.u2 95.0026 510 420e 4205 .a20e .e920 4920 0.0000 ft.67a 10.43 95.1327 3n7 .agos 4209 .agea .5000 5010 0.0000 11.847 10.38 94.7529 394 4206 4209 42n5 4900 .5000 0.0000 11 567 10.83 95.1929 315 4209 4207 8206 8990 4990 0.0000 11.825 10.40 94.9030 a65 .a20e 4205 .4205 4960 4940 0.0000 11.730 10.39 94.8031 a78 4207 4206 4205 4920 .**10 0.0000 11.633 10.40 04.8532 396 .'4208 .a207 4205 .5000 .5010 0.0000 11.691 10.43 95.1633 220 2204 .a206 .u207 .a91u 4900 0.0000 11 680 10.46 95.ae34 132 .u202 4201 .a200 .a950 .n950 0.0000 11.721 10.42 95.1235 dh3 .eFoo 4203 4205 .em90 4e80 0.0000 11.555 10.a0 94.se36 819 .a209 8209 4207 .c920 4939 0.0000 11.699 10.82 95.0937 270 420e 4?Se .=20e .5000 .5010 0 0000 11.846 10.40 94.9136 317 .a20s 4205 420e .5000 .Suso 0.0000 11.932 10.43 94.9539 489 .adu5 4206 420e .5030 .5030 0.0000 11.015 10.41 98.9ea0 19e 4207 4206 42n7 8950 4950 0.0000 11.755 10.42 95.10

|

|

i

_ _ _

TABLE D-1. Continued

at 254 4203 .edu5 4205 4980 499u 0.0000 11.619 10.43 95.1s

42 147 4203 4205 .s205 4030 4910 c.0000 11 691 10.e1 95.02

43 501 .a205 4207 .a209 492n .a93u D.0000 11 7ne 10.e3 95.2084 2.43 420M 4207 42nb .e950 4940 0.0000 ft.73M 10.a2 95.0ea5 311 .e205 4207 42ae .seno 498u 0.on00 11 795 10.80 ge.88

46 478 4206 4205 .c202 4970 .a970 0.0000 11.778 10.42 95 *

47 SOA 4208 4208 4E07 .a9eu 4950 0.0000 11.754 10.43 95.

se 424 .e206 .a208 4205 49a0 4930 0.0000 11.716 10.43 95.:2

49 374 220e .s203 4202 .5000 .5030 0.0000 11.938 10.43 95.1550 une 4203 .a202 42n2 .u960 .o960 0.0000 11.754 10.43 95.1651 124 .u?p7 4209 4209 .e420 .u939 0.0000 11.701 10.e2 95.10

52 154 .e206 420e .o.ne .nono 4950 0.0000 11.709 10.43 95.17

53 500 4206 4207 .42n7 .a9au .o95u 0.0000 11.70n 10.a0 9s.85su 2o0 8207 4207 .a208 .e900 .eatu 0.0000 tt.n93 10.co 95.47

55 3P2 .e208 .e201 4202 49a0 .o950 0.0000 11.712 10.41 95.0256 116 4208 4207 4207 4940 .a940 .0700 11.363 10.38 94.7457 to .e208 4209 .4209 .5000 .5000 .0700 11.51s 10.39 '4.7954 28 8207 .a208 .a207 4970 .e970 .0700 11.e46 10.40 Ga.86

59 31 4207 4208 .azn7 4980 4990 0700 11 484 10.40 94.8960 56 4209 4208 4207 4960 4970 .0700 It.a62 10.40 94.8661 1 4205 4207 .a207 4900 .e900 .0700 11.276 10.39 94.83

62 2n 42o1 420e 420e 4940 .a950 .07n0 11.380 10.41 94.96I

C3a

h3 AvtRAGE DIAMETER IS 4206 INCHES h1TH A STO UEV UF .00020AvtRaGL LENGIH IS 4964 INCHLS n1TH A STD DEv 0F 00444

AVtPAGE a.EIGHT IS 11.690 GRAMS WITH A STD DEV 08 .17787AvtRAGE DENSITY 18 10.41 G/CC a!TH & STD DEV UF .01731AvtRAGt THEORETICAL DENSITY IS 95.02 PLRCENT w!TH A STU UEV UF .15793

TOTAL FUEL LENGi*t IS 30.7755 INCHESTOTAL Uu2 aEIGHT IS 728.772 GRAMS

e t r. y

_ _ _ _ _ _ _ _ -

i

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% W WWWWWW4mmmmmmmmmmemW3mmemmmm4mmmmmm@mmmeow eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee

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g wW oeemmmmmNwmNN4NNNemmwNewmWMNormWNMNoNmmee MN OMMG@ G444WSSW@ 24GmG4WGOWWOSS WWGGS GW&WTS4

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kEm mmemhmSNememW4mNmbehhNoWmeNOmmmeoemwhomN00 p o 7 3 e e e m e e @ o s e e e w 4 o e m O. ~o N e o o w N N. w ~o m. .t o. ~e m w W mWemWmememeekhNeO~eede ene~ee ~ ~,eeMw

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wwwwwwmwwwwwwmmmwwwwwwwwwwwwwwwwwwwwww m

mEmM4m op roooooooooooooooooooooooooooooooooooooooo

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eddiL Zu

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w-ooooooooooooooooooooocooosooooooDoooosooq se3Me@@NeoNmmtmemOmmNewmo@eNNOE 3 Mom &Femosy JeoceaeopooQeeeoeGeoeoeDoe@ eooemeeoreemos

We@ @ @ @q m e. m m @ U [email protected] e e e e e e e o e e e e e e o e e o e e e e e o e e e e e e e e e

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mm MhmemE4emmw&NmEsemN@ me@maemeeOS 3444peemA 4g socoooccooooococooooooooooooooooococooooog ONNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNN

34WO@ SG44WUGOUG4WWOUSWW WWee3433@ @ GG34W40e e o e e e e e o e e e e e e o e e o e o e e e e o e o e o e o e o e e e o e o

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men ~eeenoemmNneeeeeeNNemmmoemenemenmaneememy wxeooooooooooooooooooooooooooconoooooooooood zUaNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNez

=. =. =e =e =e =. = =ee==========.==e=.=.==e=ew o e o s e o n = = = =. =. =.L9 wm e e e e e e e e e e e e e e e o e e e e es owh

meenecoeemmas.*Nuenoemmeome%4mmeewmeemnemB oooCooooooopeaconococcooDoooDoooooooosoo

ONNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNU S WO O44WOWOUGU USO4443442WWW WWW OGGWGWUOOOe e e o e e o e o e e o e e o e e o e e e e o e o e e e o e e o e e e e o e e o

NAMMJS NV doemmmem=4ohnembog twot CmoWEodWowomhoGmsi Nm4 Lwa sahm4eNa@ Op eN=No@EmoW 3mmmheeom4E NM3 m == UmmwwNUNWOMWmwSNNmNamNam@ 44NUNemk%

2* madwJWJw wNMS@ehteowNmer@NeoomNmWeeheeo=NmemehEeoem emmwwwwwwwNNNNNNNNNNmmmmmmmmmMO&Q

h

D-3

-. -

TABLE D-2. Continued

#1 222 4205 .a207 4207 .a960 .a95D 0.0000 11.76e 10.s6 95.48a2 2a2 4206 4205 .a207 4930 .s920 0.n000 11.722 10.e5 95.3543 511 .a207 4207 4205 .an9u 4H90 0.0000 ft.e22 10.e4 95.23

ao 326 .a200 4202 42nl .5010 .5010 0.0000 11.026 10.39 9a.?985 aP6 .a204 4205 .a205 .5000 5000 0.0000 11.959 10.42 95.1146 479 .a208 4204 .c20e 4090 4990 0.0000 11.903 10.40 es.8s87 401 .a209 4209 42o7 4970 .a970 0.0000 11.777 10.40 98.8548 GAA .a202 4204 .a20s .e930 49ao 0.0000 11 696 10.42 95.1049 339 .a200 4201 .u2n2 .5050 .5060 0.n000 11.96a to,a2 95.0750 327 4205 4207 4206 .5ua0 5040 0.0000 11.917 10.39 94.7551 ten .a207 .e20e .a208 4900 4900 0.0000 11.669 10.e5 95.5652 379 .s206 4205 .a207 .505u .5usu 0.0u00 11.963 10.ut 95.0353 143 4208 .a204 .a206 .e949 .d950 0.0000 11.776 10.45 95.37

58 279 . ados .a204 4207 .5000 5u00 0.0000 11.r64 10.42 95.12

55 372 .a20s .a205 .a205 .5030 .5020 0.0000 11.928 10.83 95.18

56 37 .a207 .a207 8205 .a9mo .a9eo n.0000 ft.a95 10.18 92.48

57 12e 4207 4208 . sane .5000 4990 .0700 11.517 10.41 9e.98

5a 75 .a207 4208 .a208 .5010 .5003 .0700 11 549 10.41 95.03

59 P3 .a20e 4208 .a207 .505n .5090 .0700 11 651 10.41 95.01

60 e 4208 4208 4209 4960 4979 .0700 11.425 10.38 94.73

41 on 4208 4200 4209 5000 .5000 .0700 11.556 10.43 95.13

? 62 20 4209 4208 4206 4950 4950 0700 11.a15 10.41 94.9e

4

avtPAGE olaMETLR IS 4206 INCHLA *1TM A STO DEV UF 00021avtpAct LENGTH IS 5977 INCHES alTM A SID DEV OF 00453a vt r.ar.E =EIGHT IS 11.725 t. RAMS alTH A SID DEV UF .16675AVtGAGE DENSITY IS 10.41 G/CC alTH & STD DEv OF 03963avthdGE tnt 0NETICAL DENSITY IS 95.02 PERCENT alfM a STD DEv UF .36337

TitTAL FutL LENGTH IS 30.8570 INCHESTufal UU2 atIGMT IS 726.931 GWAMS

* C ,. -

_ _ _ _ _ _

y

t> t' a r

TABLE D-3. Pellet Data for Rod 3, IFA-513

PELLLT PLLLtf DIAMETER LLNGTH voto = LIGHT DEN 5tiv UEN8 TITP081710N NUMakW (INCHES) (tNCHE5) DIAPETE4 (G) (G/CC) ( 1 10)

01 p.2 p.3 L-1 L.2 (INCHES)1 52 42ne 8205 .e205 .e970 .4970 0700 11.452 10.a2 95.032 .e4 4205 4205 .e203 .aSto 4920 .0700 11 313 10.41 94.9e3 96 4203 .c202 4202 4960 .e950 0700 11.394 10.e1 9s.9e# 23 420e 4203 .e201 .e9c0 .4940 .0700 11.376 10.42 95.085 64 4206 4207 4205 .e930 .e92u .n700 11.355 10.at 95.036 10 8205 4209 4209 4960 .e960 .0700 11.458 10.43 95.13

7 66 420R 4208 .s207 4950 4960 .0700 11.e55 10.43 95.20e Pa .a207 4208 .e208 4950 .a940 .0700 11.e03 10.e1 94.969 256 4206 4206 4205 .5050 .5050 0.0000 11 969 10.41 94.99

to 362 4202 .a204 420e e96U 4970 0.0000 11.764 10.as 95.23e

11 25e 4205 4207 .a204 4990 8990 0.0000 11.e32 10.42 95.0512 806 .a206 4207 .4207 .503u .5040 0.0000 11 929 10.80 94.9113 237 4203 4200 4201 4900 4910 0.0000 11.600 10.45 95.3114 157 4203 8205 4205 .e930 4920 0.0000 11.701 10.48 95.2515 318 4204 4203 0203 .5070 .5070 0.0000 11.991 10.40 94.9016 297 4205 4206 .a2n$ .5u40 .5000 0.0000 11.947 10.41 95.0217 19e .e205 4207 4207 4920 4930 0.0000 11.735 10.86 95.47to 50e 4206 4207 4205 .e9so .e98u 0.0000 11 810 10.42 95.03

cp 19 137 4204 4205 4205 4940 .a940 0.0000 11.746 10.45 95.358 20 866 420e .a203 .a200 4970 4970 0.0000 11 762 10.at 95.00* 21 423 4206 4205 8203 .a910 .a910 0.0000 11.624 to.a0 94.93

22 805 4207 8205 4203 4950 .e960 0.0000 11.755 10.82 95.1123 221 .e207 .a206 8206 4960 .4970 0.0000 11.802 10.44 95.2424 152 4205 8205 4206 .5010 .5000 0.0000 11 901 10.45 95.3225 503 42ut 4203 .a203 4930 4890 0.0000 11 599 10.39 94.8326 al6 4205 4207 4208 .a930 493U 0.0000 11.695 10.82 95.0327 266 8207 8205 .a203 .5020 .5020 0.0000 11.900 10.82 95.0828 42a 4207 8208 4205 4940 .e940 0.0000 !!.116 10.41 95.0129 413 .aFoe .a20e .a202 .e970 .e980 0.0000 11.730 10.37 9a.6130 176 4206 4207 4206 4960 .4950 0.0000 11.76a 10.e3 95.1331 417 4208 4207 .a206 .a970 .a970 0.0000 11.403 10.43 95.1232 212 420e 4206 .c205 4920 .4920 0.0000 11.713 10.46 95.4533 248 4206 4207 4207 4980 .5000 0.0000 11.832 10.40 94.9034 149 4203 4202 4201 .c940 .a94u 0.0000 11.715 10.se 95.2135 166 4207 420e 42n5 4950 49e0 0.0000 11 746 10.e3 95.1936 172 4205 8206 .a205 .5000 .5000 0.0000 11 883 10.ca 95.2737 246 4207 4207 .a206 .a970 .49n0 0.0000 11.804 10.82 95.0538 195 .a206 8208 4210 4920 .4920 0.0000 11 691 10.43 95.133e 335 .a205 4205 4205 .5030 .5030 0.0000 11 921 10.41 95.02a0 395 .a2pu .a2us 4206 .c920 .e9tu 0.0000 11.668 10.43 95.15

.

TABLE D-3. Continued

at 178 .a207 .a207 .a207 .a910 4900 0.0000 11.071 10.45 95.3142 186 4202 .a203 .a204 .e920 4930 0.n000 11 090 10.se 95.2e43 519 .a205 .s206 420e .a950 .a9ao 0.0000 11.7o9 10.ee 95.23as 170 .e207 4208 420e 8930 4940 0.0000 11 723 10.43 95.15a5 26e .a205 .a2n6 .a20h .a960 .a96u 0.0u00 11.7ee to.a2 95.06a6 ea0 4202 4205 4205 .a930 4920 0.0000 11.660 to.at 9e.9747 353 .a206 8206 .adoe .5910 .5020 0.0000 11.882 10.41 94.*6as 400 .a205 .a207 .a206 5020 5030 0.0000 11.946 10.es 95.2749 250 4203 4203 4205 .5010 .5000 0.0000 11.e57 10.42 95.04

50 40s .e20e 420s 4207 4950 .a900 0.0c00 11.767 10.43 95.1551 302 4201 4202 .a202 .5010 .5010 0.0000 11.mb7 10.42 95.04

52 #30 .a200 4201 4201 .ao20 .a920 0.0000 11 626 10.o0 94.9ar

53 376 420h 4206 .e205 4000 .a99u 0.nc00 11.e32 10.e2 95.04

54 431 4202 4203 .e203 .e050 .u990 0.0000 11.70e to.et 95.01

55 a02 4207 4207 4206 4040 4940 0.0000 11.715 10.41 95.0056 65 .a208 .a207 4205 .s960 .a970 .0700 11.a53 10.42 95.1057 115 4206 4207 .a207 4940 .a940 0700 11.360 10.38 94.7558 89 .a202 4206 .a207 .5000 .5000 .0700 11.530 10.42 95.0959 105 4205 42n7 .a20e .500o .a990 .0700 11.502 10.40 94.8860 67 .a205 4206 .a203 4960 .o960 .0700 11 427 10.41 95.0261 15 .a20e 4207 .e206 .5050 .5050 0700 11.642 10.41 95.00

? 62 10e .e207 4208 .a206 4950 4960 0700 11.a32 10.42 95.0ecn

avtwAGt DIAHtTER IS .e205 INCkts wifM A STD ulv UF .00020AvtWAGE LLNGTH IS 4965 INCHES w1TH A STD DEv UP 00a06kVEpar,E WElGMT 15 11.696 GRAMS allH A STD Dtv UF .17283AvtpAGE fiEhSITY 15 10.42 G/CC a f f'4 A STD Dtv 0F .01717AVEWAbt THtuRtf1 CAL DENSITY 13 95.v8 PtWCENT alTN A STD DEV UF .15665

TOTAL FUEL LENGTH 13 30.7m10 INCMktliiTAL 002 aE1GMT IS 725.133 4.kA*5

e l p. ~

. _ _ _ _ - - - _ _ _ _ . -n s

7-_ _

m>3hww MMoeNecommewNPPMSWPPhmePOMempFmechmewoekeg SPmeePPhPPMSPwOpme=PNehePewMwSwCPwoMNSEe

{ 2 e e e e e e e e e o e e e e e e e o e e e e e o e e e e o e o e e e e e e e o eO W we@eeeeeee@eeM@e@e@e@eeme@@mme@@e@@@@@eM

Om PPPPPPPPPPPPPPPPPPPPPPPPPPPPPPPPPPPPPPPP

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2G e e e e e e e e e e e e e e e e e e e e e e e e e e e e e o e e e e e e e e e eWw 0000000000000000000000000000000000000000O mmmmmmmmmmmmmmmmmmmwwwmmmmmwwmmwwwwwwnmw

hKm NMNMNNe@@ OFemMweeOmwhMmMeMMONOSMPANehenwJG edeseeePPMWe4N40GeWhNeheehPehmopeceWMPPMww M e r c e M M M e t h > P h e h e s e e m e d m es e p h r e > > 4 D h o m e E 4W e e e e e e e e e e e e o e e e e e e e e e e e e e e e e o e e o e e e e e e e4 wmmmmmmmmwwwwwwmmmmwwwwwwwmmmmwwwNmNwmmm

mmmmmmmmmmmmmmwwwwwwwwwwwmmmwwwwwmmwwwwwn

emM WWm o>I000000o000000000000000000000 ccOOOOOOOcco

wWucOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOm, 31 zhhhh=>>>OOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOO>e>O00000000000000000000000000000000000000O< ww e o e e e e e e e e e e e o e e e e e e e e e e o e e e o e o e e o e e e e o e

Q 000000000000000000000000000000COM

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Y NOOOOOOOoOOOOOOOoseOOoOsOOOOOOOOO 00000000g ee=NeeFANOchesweOOPMhNMhwNeppFMdWWheswMPS

O JPPOSPPPPOOPPOPOPOOPPPOPPOOePOO PPPOPOPPOPe semy emeescoememommeseroemeeecogeeremeereW Ze e e e e e o e e e e e e o e e e e e e e e e e e e e e e e e e e e e e e * * e *

WWb G10 zu

% WEJw

g wwo00000000000000000000000000000 DOOOOODOOOp OMh0NeeeeNDMmemceomeMhNehNNP@remeMrehewMO

JPPOOPOP&OPPPOPOPOOPPPOPPOOePOPPP&OO OPPOPOQ sew #eeeeFO44Womemmesedeemmespe.eee#emee#ee e e o e o e e o e o e e e e o e e e e e e e e e e e e e o e e e o e e o e e

UWe

W M@ehMheePheadmewhemeePNeemommNd4NOhNh49eeo0000000000000000c00000000000000cceOcOOOOL omNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNesaceeeegesemesesO 4eeeeeeeeeeeeeeeeO =4&Ge e o e e e o e e o e o e o e o e e o e e o e e o e e e o e o e e o e e e e e e

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Yag Me

WeW wNehkehe4hhePMNWeheNSMeMhhO@eemh4MNPMh4Ge#m

WI S OOOOOOOOOOOOOOOOOSOOOOOOOOOOOOOOOOOOOOOO4 EU3NNN8dNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNW 42 a. w e g e. w e s. e e e e e e. e. e. e s. c e. s e. w. e e. e e. e e. e. e. e. e. e. e. e e s e mq == e e e e e e e e e e e e e e e e e o e e eH Ow

=Pm4mhhe#heeNNmNeechm>MemmeMPMehmMPmmeONe0 000003030000000000000000000000 COOOO?OOOC

QNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNN -essome1eeeeeeeeeeeeeeeeeeWesecocesesseege o e e o e o e e e e e e o e o e e o e o e e e o e e e o e o e e o e o e e o e

h3W asJK N m M e e P @ p e t * N P. k M K% NohseO@eNOMNwNOreNNeueGM

i Ji MmWmO Ne*hhC4 * * JF e n w h o * M o r* O M m 4 N e h m e N e h e N oMS = NNN64w@eMMNaNeeNMMoNMMmeeMoMeeNMSLL

2wh3WwJh-Jw WNMeddhePOwNmemakePommmemehepomNMemebePOWe wwwwmmmwwwNNNNNNNNNNMMMMMMMMPMeE3

.)

D-7

_._ _ _ _ ._ _

TABLE D-4. Continued

41 434 4206 4206 82e7 .a9a0 4940 0.0000 11.704 10.80 94.9382 235 4206 .e207 4207 .s910 .a920 0.0000 11 705 10.e5 95.37e5 20a 82d7 4205 4205 .5029 .5020 0.0000 11.896 10.at 9e.984e a73 4205 .a20e .a206 .5000 .n99. o.0000 tt.ntt 30.38 9e.7245 261 4205 .a206 .e206 .5010 .%o10 0.n000 11 45A 10.80 9e.8684 201 4205 4207 4206 4990 .o990 0.0000 11.a35 1C.42 95.0447 jan .d205 .a20s .e2n5 .5900 .%000 0.0000 11 8a3 10.ee 95.3046 193 420e .e207 420e .aq6a .a953 n. coco 11.765 10.eu 95.27a9 ime .uia5 4205 .e203 .%e20 .5020 0.0000 11 897 10.42 95.0550 2n* 4202 4201 8201 4090 6940 0.0000 11.774 10.40 94.86

51 25% .c210 .a209 4206 .5000 .%cuo n.n900 11.ee7 10.80 94.8952 e5) 4207 .a207 .a201 4869 4670 0.0000 11 519 10.39 #e.02

5$ Se7 82u7 4207 4205 493u 4940 0.0000 11.714 10.=2 95.1154 502 4 2 a r. ,4205 .a/97 .aolu .a930 0.0ena ts. eft to.no 96.on

55 20s 4203 4202 4202 .5cao .5000 0.0000 11.911 10.40 94.8756 16 4204 .a206 .s205 .5040 .5030 .0700 11.612 10.42 95.1057 122 4208 4208 4206 .ageo .o940 .0700 11 376 10.40 94.8558 82 .a204 .a205 .e205 .5020 .5020 .0700 11.529 10.38 94.7259 50 42a5 8207 4208 .5010 .5000 .0700 11 533 10.81 94.9460 tct .a202 .a20e .a205 8950 .a950 .0700 11 393 10.41 94.97-

61 79 4206 .a207 .s206 .5000 .5000 .0700 11.545 10.e3 95.12? 62 106 4203 .a209 4208 4910 .a920 .0700 11.370 10.45 95.31co

AVEnaGE olaNETER IS .e205 INCHES WITH A STp UEv UF 00022AVEWAGE LENGTH IS 8978 INCHES alTH A STD DEv UF 00452avthaGt =EIGef 15 11.722 GRAMS WITH & STD DEV UF .18024avteaGt OENSITV.IS 10.41 G/CC w!TM A STD DEV UF 03819avtRAGE THFuwETICAL DENSITY IS 95.02 PENttNT =ITM a STD DEv UF .3e641

TOTAL FUEL LENGTH IS 30.e648 INCHE8Turat U02 at.IGHT IS 726.774 GRAMS

. . .

- N N

,

)V0T1I 5e59735e934 5u1 m5e71 J50404929701 957 175o31

e 7. e. 9 8 8 8 9 8 0 0 3 9. Q. e. 3 2 0 6 0 4 116 3 9. e.12 3 4 4 9 131. d. 3. c. 9 4Sh%E 4 e844 oe6555455553e355545ee555354555335e5U1 99999Wv99999999999949999999999499 * 9 99999

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M TC1C e010u910dd514o5sd41 o339 uuu3 e530035d4520e

J. e. 4 4. e. 3. e. 4. e. e. e. 4 4 4. e. e. e. e. 4. s. 4 4 3. a. e. a. e. s. 4. e. 4. e. =. 4 6. e. =. =. u. s.3/44E1 000000u0u0090000u00090u0000060090900u000D 111111l1t1111111l11111l1111111111111l 111

fn3 5705ua19u236eo31 e7977 o1015e10d0oe1 eAa151GG 18913e58o049vl352902127 042b30e0 ode 91 o0 43

4 3 3 4 2. s. 3 3. c. 1 o.7. o. o. 7 1 9. e. 7.o. 00031 o. o. 5. v.1. v. . . 0. / 11 i 77 07I1. . . .E

n 111111111111111111 11111111111111 1111111111111111111111111111111 11111111111111111

)3 ah1 Et5 uT a90u00u00ou0000u00uu0000u09Q0u90uou0 uuu00

- tEC00o00000co0000o000 u0u00000o0000uo000o000uM h77i77777uw0900c0009000 90c9vc0 w0uwu09g0 uuA

F v A 10 0. u. 0. u. 0. u. u. u. 0 0 0 0 0. u. 0 0 0 0 0 0 0 0. u. u. 0 u. u. 0 0 0. u. u. 0 0 9. u. 0 0 0I1I D 0000u0u00000000000u00u0L00000000.

5duo 00099090099999u0090u09uu9 900uudu0 uJ099d = 6s5629452499093433593o31e599751le578e423o L999994999909 ue99 90969v99e9 9 ee99 uw99B v999R

4. e. 4 4 4 4 4 4 6 4 4. e. 5 4. e. e. 5 5. e. 4. e. s. 5. e. s. 4. e. 4. s. 5 4. S. u. 4. e. e. s. e. 4. e.)

nSr TEo Gmf Nt

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( 109u0900009u00uJu00 e0090 w00 990900 u0090009t = 6 5 e 5 2 9 3 8 d39 8 9 o 4 e 23 e 8 8 9 3 u 9 5 9 9 e 5 2 8 b 4 7 4 e31 6a L9999999999e99e9v009e98 9ve94 ee090e99 o99 99De. 4. e. e. 4 4 4 6. u. 8. s. e. 6. s. e. e. 5 5 4. s. 4 4 5. s. e. *. *. s. s. 5. *. 3. s. 6 8. w. 6 6 6 6

telle 380es85ee9?e0eser75se561 o d7 7 h 0 t e 3 s s 5 7 5 S 7 tP 00oo0000Quu0000o00o0O00oo00c0oc0o0000O0o

02ddd2222dddd24dd22d2d42dd4cddd cdd44cdd2d4 4. e. e. e. 4 4 4 4. e. e. 4 4 4. e. e. 8 6. e. 4. e. 4 4. e. e. e. u. e. 4. e. e. 6. e. 4. e. e. e. e. 4. e..

5-

DN)ESE I t297s777 e57 es3e2se653501 9? do? ee4? d3e5 oet5e

L EM 0000000000o000o00QvO000o0ou000oo00000o00B M C 0 224 dd 2 2 d 2 2d 22 2 d d 2 d d d d 2 2 d2 d d 42 d d c d 2 2 4 4 d 2 d

4 4 4 4 4 4 8 4 4 4. e. 4 4 4. e. e. e. e. e. e. e. 4. e. e. 4 4. e. 4 4 4. e. e. 4. e. 4. e. 4. e. 4 4A AhT I1

D1

877701705572515e7 deo?7110797757ee5050e731000000000o00000o0o0p000000000000u0001000022d242222d22d22ddd222c2d2d22d22242ddd2d2

4 4 4 4. e. 4 4 4 4. e. 4 4 4 4 4. e. 4. e. e. 4 4. e. 4 4 4 4 4 4 4. e. 4 4 4. e. 4 4. e. 4 4. e.

IdEELW 93279o329594164513c8207547 w976eO5893e503Le 96248t302226235899e6980555e3850P331 42459Eu 11e22421132l112234e32222A11221143PN

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TOEILTLI 123e56789o123e56789012345678901234507890ES t111l11111222222222233333333334

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. . -- _. - _._

TABLE D-5. Continued

at 231 .e20e 440. .de06 . oeo . e99 v.0009 11.... 10.=7 v5.89

42 21e .ed0e 4203 .edO3 .501u .5ulu 0 0000 11.oee 10.=3 95.to

43 359 4d00 .edos .e403 .swoo .499u v.uucu 11.et* 10.e3 95.le

44 39e 4203 .#203 .edos .5000 4999 0 0u00 11.001 10.de 95.28e5 230 4d05 .edos .ed0e .sw30 .4940 0.ucou 11.imd 10.e5 93.3d

46 353 4d05 420e 4400 .59e9 .5ulu v.0000 11.v5= 1u.*3 95.te

87 480 .edoo .ecco .edoi .*95w .8950 0.U004 11.730 10.=1 **.95

48 370 4d07 .ed05 .edQ5 4979 .e979 v.0duu 11.o01 19.25 93.So49 377 420e 420e 820e .svec .e950 0.000u 11.735 10.61 9e.9T50 368 .s207 .edoi .edD7 .eved .e979 U.uu00 11.799 lu.e1 vs.ou51 159 .edue 420e 420e 4930 .4930 0 0000 11.724 10.ee 95.de52 309 .e20b 4201 .eios .5010 .5u10 0 0000 11.e51 10.39 98.7e

53 494 4d05 .edof 4d07 .=980 .4980 0.uvou 11.es3 10.es 95 2e54 345 420e 4209 4209 5939 .50e0 0.0000 11.vev 19.e4 95.2e

55 167 .4202 .eded .edou 4960 .e98u 0 0u09 11.797 10.43 95.le

56 92 420e .edos 4203 .5000 .5010 .0F00 11.525 10.41 95.0157 8e .e205 420e 4d06 .5930 .5939 .070u 11.e17 10.e3 95.2958 55 420d 420e .edO5 4979 .4909 .070u 11.450 10.e3 95 1e59 18 .edoe .e20d 4d02 4990 .5uou .0700 11.315 19.=3 95.1760 88 4206 4207 4d07 .5020 .5020 .0700 11.571 10.41 94.91

c3 61 17 4206 8207 4d08 .5u00 .5010 .0700 11.58e 10.e5 95.35

L 62 27 .e20e .e207 4d05 4950 .4960 .0700 11. ele 10.41 94.94

o

AVERAGL DIAdLTER I$ 4205 INCMLS a!Tn A STD DEv 0F .000c1AVERAGL LENGTM IS 4958 INCMES n!Tn a STD uEV 0F .00 denAVERAGL nEIGNT 15 11 68d GRAMS nITM A STO DLV 0F .16892AVERAGL DENSITY IS 10.42 G/CC n!TM A STD DEv 0F 03007AVERAGE TMLORETICAL DEN 8ITY IS 95 09 PtRCENT n!Tn a sTD DEv 0F .27440

TOTAL PULL LENGTM IS 30.7375 INCMESTOTAL 002 nEIGMT IS 728.282 (eRAMS

e ( ,

_ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _

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TABLE D-7. Immersion Densities of Selected IFA-513 Pellets

i Solid Pellets Cored Pellets

Pellet % TD % TD Pellet % TD % TDIdent. 5/12/1977 5/13/1977 Ident. 5/12/1977 5/13/1977g

143 95.50 95.53 398 95.36 95.43148 95.60 95.66 406 95.21 95.19168 95.50 95.55 425 95.20 95.19171 95.38 95.43 429 95.20 95.24172 95 .54 95.60 449 95.17 95.24181 95.51 95.60 453 95.20 95.16208 95 .56 95.47 474 95.23 95.20245 95.56 95.60 475 95.29 95.33260 95.45 95.42 485 95.21 95.22266 95.33' 95.37 494 95.28 95.28288 95.19 95.26 504 95.15 95.09298 95.19 95.29 5 95.34 95.25308 95.33 95.32 13 95.44 95.41336 95.30 95.32 16 95.42 95.37357 95.26 95.30 131 95.38 95.36376 95.36 95.33 33 95.36 95.39380 95.32 95.30 37 95.32 95.46392 95.36 95.42 44 95.23 95.33

66 95.47 95.4279 95.40 95.49

101 95.43 95.37

.

,.

D-13

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.

NUREG/CR-1077PNL-3156

R-3

DISTRIBUTIONjNo. of No. ofCopies Copies

(OFFSITE ONSITE

A. A. Churm 44 Pacific Northwest Laboratory

DOE Patent Division9300 S. Cass Avenue W. J. BaileyArgonne, IL 60439 J. O. Barner

E. R. Bradley360 Nuclear Regulatory Commission E. L. Courtright

Division of Technical Information M. E. Cunningham (15)and Document Control J. L. Daniel

7920 Norfolk Avenue N. C. DavisBethesda, MD 20014 M. D. Freshley

R. L. GoodmanR. J. GuentherC. M. Hagen

2 DOE Technical Information Center C. R. HannK. A. Hsieh

4 W. V. Johnston D. D. LanningChief, Fuel Behavior Research R. K. Marshall

Branch C. L. MohrDivision of Reactor Safety C. Nealley

Research F. E. PaniskoU.S. Nuclear Regulatory Commission P. J. PankaskieWashington, DC 20555 W. N. Rausch

R. E. SchreiberH. H. Scott G. D. WhiteFuel Behavior Research R. E. Williford

Branch Technical Information (5)Division of Reactor Safety Publishing Coordination pg (2)

ResearchU.S. Nuclear Regulatory CommissionWashington, DC 20555

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u