China Atomic Energy Press Edited by China Institute of Atomic ...

Annual Report of China Institute of Atomic Energy

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China Atomic Energy Press

Edited by China Institute of Atomic Energy

Price: 100.00

Annual Report of China Institute of Atomic Energy

2011

Edited by China Institute of Atomic Energy

China Atomic Energy Press

Beijing, China

图书在版编目（CIP）数据

中国原子能科学研究院年报. 2011 : 英文 / 中国原

子能科学研究院编. -- 北京 : 中国原子能出版社,

2012.7

ISBN 978-7-5022-5605-0

Ⅰ. ①中… Ⅱ. ①中… Ⅲ. ①核能－研究－中国－

2011－年报－英文 Ⅳ. ①TL-54

中国版本图书馆 CIP 数据核字(2012)第 150944 号

Annual Report of China Institute of Atomic Energy 2011

Published by China Atomic Energy Press P. O. Box 2108, Postcode: 100048, Beijing, China Printed by Printing House of WenLian in China Format: 880 mm×1 230 mm 1/16 First Edition in Beijing, July 2012 First Printing in Beijing, July 2012 ISBN 978-7-5022-5605-0

Annual Report of China Institute of Atomic Energy 2011 出版发行中国原子能出版社（北京市海淀区阜成路 43 号 100048）责任编辑付真王宝金印刷中国文联印刷厂经销全国新华书店开本 880 mm×1 230 mm 1/16 字数 500.4 千字印张 18 版次 2012 年 7 月北京第 1 版 2012 年 7 月北京第 1 次印刷书号 ISBN 978-7-5022-5605-0 印数 1—500 定价： ¥100.00 元版权所有侵权必究

Editorial Committee of Annual Report of China Institute of Atomic Energy

Editor in Chief ZHAO Zhi-xiang Associate Editor in Chief LIU Wei-ping ZHANG Wei-guo Consultant WANG Nai-yan WANG Fang-ding RUAN Ke-qiang ZHANG Huan-qiao Editorial Committee WAN Gang MA Ji-zeng WANG Guo-bao WANG Nan YIN Zhong-hong SHI Yong-kang YE Hong-sheng YE Guo-an LU Jian-you LIU Da-ming LIU Sen-lin LI Lai-xia LI Yu-cheng WU Ji-zong TANG Xiu-zhang ZHANG Wan-changZHANG Tian-jue ZHANG Dong-hui ZHANG Sheng-dong ZHANG Cun-ping ZHANG Chang-ming ZHANG Hai-xia ZHANG Jin-rong YANG Bing-fan YANG Qi-fa LUO Zhi-fu YUE Wei-hong ZHOU Pei-de CHEN Ling HU Ji KE Guo-tu ZHAO Shou-zhi ZHAO Chong-de HOU Long JIANG Shan JIANG Xing-dong XIA Hai-hong GU Zhong-mao XU Wei-dong HUANG Chen HAN Shi-quan FAN Sheng WEI Ke-xin Editors MA Ying-xia WANG Bao-jin WANG Tiao-xia TANG Xiao-hao ZHANG Xiu-ping HOU Cui-mei

Address: P. O. Box 275-65, Beijing 102413, China Tel: 8610-69358024, 69357285 E-mail: [email protected] URL: http://ZYKB.chinajournal.net.cn

PREFACE 1

PREFACE

In the past year of 2011, according to the directions of related governmental departments, under the direct leadership of China National Nuclear Corporation (CNNC) and in the spirit of the annual work conference, China Institute of Atomic Energy (CIAE) had successfully accomplished all the yearly objectives, achieved significant progress in a number of areas and fulfilled the Performance Evaluation of CNNC in the 8th time. 1 The drafting of “The 12th Five Year Plan” in progress, and the Planning System becoming more mature

In order to further elaborate the planning objectives, CIAE had proposed a comprehensive planning framework composed of Master Plan, Subject Plan, Special Program Plan and Department Plan.

For Master Plan, CIAE had published and submitted to CNNC “the 12th Five Year Plan”.

For Subject plan, CIAE had successively released the Talent Cultivation Plan, Nuclear Facilities Decommissioning Plan and Radioactive Waste Management Plan, and drafted planning documents on science and technology development, fixed asset investment, nuclear technology application, nuclear safety, information technology, etc.

For Special Program Plan, CIAE had initiated the drafting of the related documents on the application of China Advanced Research Reactor (CARR), updated the development plans on China Experimental Fast Reactor (CEFR), and mapped out plans on the application of China Reprocessing and Radiochemical Laboratory (CRARL).

For Department Plan, CIAE had drafted planning documents for the Department of Nuclear Physics, the Department of Reactor Engineering Research & Design, the Division of CEFR Project, etc. 2 R&D projects embracing new breakthroughs.

In the year of 2011, the total number of projects under researching in CIAE was 185.

Development of Nuclear Energy Technology: Nuclear energy development programs such as Fast Reactor Standardization had been progressing in schedule; 1 000 Mega Watts Demonstrating Fast Reactor completed the examination of technology option and initiated conceptual design; MOX Fuel Element of Fast Reactors had finished the work on design of single fuel element and fuel assembly, design & analysis of MOX core of CEFR and

PREFACE 2

demonstration of experimental line for pellets; Maintenance and Inspection of Key Facilities of Reactors was carried out as planned, and Online Fuel Failure Monitor & Core Damage Evaluation System had been successfully employed in Qinshan NPP PhaseⅡ ; Basic Research Programs on Hydrochemistry for Pressurized Water Reactors had all satisfied the expected targets.

Basic Research on Nuclear Technology: “Venus-1#” ADS Experimental Facility was identified by IAEA as International Standard Experimental Facility. Neutron Stress Technology and Imaging Nondestructive Inspection Technology had been experiencing breakthroughs. In-situ calibration method for Fixed Environmental Monitoring γ Radiation Dosimeter had been progressing as planned, and radioactive reagent such as B-10 had all achieved the yearly objectives.

The number of new projects approved in 2011 was 87 and the fund for these programs increased by 43% comparing with that of the previous year. 46 projects had been accomplished, and 26 R&D achievements had been appraised. The past year of 2011 had also witnessed 42 prizes of different levels, 147 patent applications with 102 authorized, and 125 papers indexed by SCI. 3 Application of nuclear technology and service of nuclear engineering advancing steadily, industrialization of nuclear technology further expanded.

Programs on the development and application of nuclear technology had been progressing soundly. Radioactive Substance Inspection Device was applied for FINA World Champion, High Express Green Channel Inspection Systems were deployed in toll gates of high express systems in northern China, and Movable Container Inspection System fulfilled its mission for International Horticultural Exposition 2011 Xi’an. Cobalt Source Center received the second batch of cobalt rods from Qinshan Nuclear Power Plant and produced cobalt source of about 6 million curies, High Energy Electron Linear Accelerator successfully wined the bid of Radiation Research Institute of Zhejiang University, and Neutron Radiator for Hospitals was approved by Science and Technology Committee of Beijing. Boron Neutron Capture Therapy gained the support from the national science and technology program, Coal Detection Using Neutrons had selected the development option, an Ion Membrane had been conducting jointly development efforts with Zhongshan Guoan Torch Company.

Technological service of nuclear engineering achieved new accomplishments. 32 agreements were signed, with total fund surging up to 67.8 million RMB Yuan. For domestic programs, CIAE signed technological service contact on pre-design research of fast reactor with Sanming Nuclear Power Plant and assisted the proprietor to conduct the negotiation with the Russia side on technological design. For foreign programs, CIAE completed the technological negotiation with Algeria side on the First and Second Phase Upgrading Project

PREFACE 3

and the Third Phase Project Design. CIAE also wined the bid of AP1000 Refueling Grab Program and Cobalt Source Disposal Project of Agricultural Science Institute of Zhejiang University.

4 Construction of “Four Platforms” continuing to advance, status of infrastructure improved.

Construction of “Four Platforms” embraced new progress. China Experimental Fast Reactor (CEFR) reached its first synchronization on July 21, 2011 and satisfied the target of “operating smoothly for 24 hours with 40% of the power”. China Advanced Research Reactor (CARR) had completed all testing work of B stage on September 22, 2011. China Reprocessing and Radiochemical Laboratory (CRARL) and the associated projects had finished the work of system commissioning. The Project of Beijing Radioactive Ion-beam Facilities (BRIF) started construction of related buildings on April 28, 2011 and pre-installing and testing work are now on the track.

Programs on Nuclear Waste Treatment progressed steadily. Upgrading Project of Radioactive Ventilation Center, Program of Interim Storage Tank for Liquid Radioactive Waste and Program of Transportation System for Medium Liquid Radioactive Waste had all finished cool testing. Pipeline Network System for low radioactive liquid waste had upgraded pipelines of about 2 000 meters, and 101 storage tank for liquid waste with tritium content finished safety related preparations for emergency responses.

Overall Development Planning Program had been progressing in schedule. The first phase of the program completed the basic amelioration of the areas for scientific research and associated service, the second phase is being implemented gradually, and the third phase has completed preliminary design.

Associated Capacity Construction Program performed well. Safety Technology Upgrading Program of No. 303 Hot-Cell had prepared for examination, Basic Technology Infrastructure Construction Program had completed all the yearly construction work.

Fixed asset investments rose steadily, and decommission management programs that were licensed surged up to 8, including Emergency Response System for Nuclear Facility, and with total supportive fund up to 346 million RMB Yuan.

5 Large scale installations and experimental facilities operating in good condition.

HI-13 Tandem Accelerator supplied beams for about 3 700 hours, the application of life expansion for 49-2 reactor had been approved, and facilities for radioactive waste had finished the treatment of the medium level liquid waste. Physical Protection Center, Nuclear Emergency Response Center and Network Center had all been operating in good condition.

PREFACE 4

6 Talent cultivation carried out comprehensively, and core technical talents cultivation framework basically formulated.

In order to further strengthen the work of talent cultivation, CIAE specially held the work meeting for talent cultivation, publishing the “Draft of Human Resources Development in the 12th Five Year Plan” and proposing new initiatives named “12345 Talent Cultivation Plan”. XU Mi, researcher and chief engineer of CEFR, was elected as a new academician of Chinese Academy of Engineering on October 8, 2011.

7 Domestic and international co-operations further enhanced.

For domestic co-operations, CIAE had signed Strategic Cooperation Agreement with China Academy of Space Technology and Radioactive Ion Facilities Cooperation Agreement with Peking University.

For international co-operations, CIAE had inked Cooperation Memorandum of Understanding with TRIUMF National Laboratory of Canada, and conducted 20 cooperative programs with Russia, France, USA, IAEA, etc. CIAE had also hosted or co-hosted a number of international conferences and training programs, invited 59 person-times foreign experts, received 318 person-times foreign guests from more than 30 countries, and sent 432 person-times visiting scholars of different missions.

President, CIAE

June, 2012

CONTENTS I

CONTENTS IMPORTANT NUCLEAR SCIENCE ENGINEERING China Experimental Fast Reactor (CEFR) Progress of China Experimental Fast Reactor in 2011··········································ZHANG Dong-hui, et al(3) Progress of Project “The Key Technology Research of Passive Shutdown System for CDFR” ············· ··································································································································HU Wen-jun, et al(4) Summary of Research on Interactive Safety Analysis Program of Pool Type SFR·································· ····························································································································QIAN Hong-tao, et al(4) Application of INPRO Methodology in Evaluation of Nonproliferation Features of TWR······················ ································································································································ZHANG Jian, et al(5) Measurement and Analysis of Sodium Void Reactivity Effect in CEFR···················ZHOU Ke-yuan, et al(5) Thermal Fatigue Analysis of Takeover Pipeline································································HU Li-na, et al(6) Analysis of Design of Sodium Reception and Secondary Loop Sodium Plugging and Removal System for Fast Reactor············································································································LIU Lin-ding, et al(7) Acoustic Leak Detection Based on Wavelet Packet and Genetic Algorithm for LM FBR Steam Generators ·························································································································WU Lin-lin, et al(7) Research on Valve Body Design of Large Bore Sodium Valve·······································LV Ming-yu, et al(8) Analysis of Leak Before Break and Calculation Method of Critical Crack··························LIU Jia, et al(8) Manufacture of Simulator of Irradiation Device for China Experimental Fast Reactor··································· ······························································································································HUANG Chen, et al(9) Progress of Research on Demonstration Fast Reactor Main Pipe Material······················LI Ya-ping, et al(11) China Advanced Research Reactor (CARR) China Advanced Research Reactor Project Progress in 2011·············································ZHAO Tie-jun(12) Beijing Radioactive Ion-Beam Facility Progress Report of Beijing Radioactive Ion-Beam Facility (BRIF) in 2011··························YI Hui, et al(13) Construction Progress of CYCIAE-100·······································································The BRIF Division(14) Completion of Main Magnet Fabrication for CYCIAE-100··································ZHANG Tian-jue, et al(17) Progress of the Water Cooling System for CYCIAE-100 ·············································LI Zhen-guo, et al(20) Main Magnet Installation in the Temporary Building for CYCIAE-100·······················LV Yin-long, et al(21) Installation and Commissioning of the Main Magnet Elevating System for CYCIAE-100····························

································································································································LV Yin-long, et al(24) Installation of the Magnetic Mapping Device for CYCIAE-100···································LV Yin-long, et al(25) Mapping and Shimming of Magnetic Field in CYCIAE-14·································ZHONG Jun-qing, et al(26) Primary Design and Study of the Lattice Structure in Scaling FFAG··································LI Ming, et al(27) Processing and Installation of the Stripping Probe for CYCIAE-100 ······················XIE Huai-dong, et al(29) Mechanic Design of the Radial Probe Target for CYCIAE-100 ······························XIE Huai-dong, et al(30) Calculation of New Beam Dump Shielding for CYCIAE-100 ····································WANG Feng, et al(31) Development of Pre-amplifier Module for BF3 Counting Tube·········································HOU Shi-gang(34)

II Annual Report of China Institute of Atomic Energy 2011

Design and Experimental Study of the External H－ Ion Source for a 10 MeV Medical Cyclotron·············· ·································································································································JIA Xian-lu, et al(35)

Design of a Compact Pulsed Power Accelerator································································ZOU Jian, et al(36) Design of Spiral Inflector and Central Region for a Medical Cyclotron·················YAO Hong-juan, et al(37) Design of Main Elements of the Axial Injection Line for CYCIAE-100···············YAO Hong-juan, et al(39) Peak Detector Circuit for DCCT Improvement··························································WEN Li-peng, et al(41) Manufacture of the RF Cavity for CYCIAE-100····································································JI Bin, et al(42) Mechanical Design of the Injection Beam Line of Small Medical Cyclotron·······SONG Guo-fang, et al(43) Mechanical Design of the Inflector and Central Region of Small Medical Cyclotron·································

························································································································SONG Guo-fang, et al(44) Measurement and Simulation of Beam Centering on CYCIAE-10···························AN Shi-zhong, et al(45) Simulation on the Pulsed Beam Transport for Injection Line of CYCIAE-10··················AN Shi-zhong, et al(46) Insulation Consideration of the Cryo-vacuum System for CYCIAE-100·············ZHANG Su-ping, et al(48) Concept Design of Multipacting Measurement Circuit With Nano-second Resolution·································

····························································································································WANG Chuan, et al(49) Mechanical Improvements on the Main Magnet for CYCIAE-14·······································CUI Tao, et al(50) China Reprocessing and Radiochemistry Laboratory Progress of CRARL Project in 2011·····················································CRARL Engineering Department(52) Radioactive Waste Renovating Projects Progress on Radioactive Waste Treatment Facilities Construction······················ZHANG Cun-ping, et al(54)

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH Nuclear Physics Tensor Effect on Proton Bubble Structure of 46Ar···············································WANG Yan-zhao, et al(57) Shell Model Study on the Proton Pigmy Dipole Resonances in 17, 18Ne·····················MA Hai-liang, et al(58)

Microscopic Effective Charges and B(E2) Values of Terminating States in Mirror Nuclei 51Mn and 51Fe

·····························································································································MA Hai-liang, et al(58) Fusion Reactions of 16O+76Ge and 18O+74Ge Near Coulomb Barrier··························JIA Hui-ming, et al(58) High-Spin States in 86Sr··································································································LIU Jia-jian, et al(60) High-Spin States in 87Sr·································································································LI Hong-wei, et al(61) Fast Timing: Lifetime Measurements With LaBr3 Scintillators······································LI Cong-bo, et al(62) Technique of Measuring Effective LET in Integrated Circuit (IC) ······························SHI Shu-ting, et al(63) Study on p+28Si Reaction for Proton Single Event Effects Research ·······························HE An-lin, et al(64)

Immunofluorescence Detection of γ-H2AX Foci Induced by 7Li Ions and γ-rays Radiation··························

·········································································································································SUI Li, et al(65) Research of Fast Neutron Radiation Effect on Rats ··············································ZHENG Jie-ying, et al(66) Test of RPC Detector by Cosmic Ray············································································LI Xiao-mei, et al(67) Calculation for Single Spin Asymmetry of Neutral Pion in Polarized Protons Collision at 200 GeV············ ···························································································································HU Shou-yang, et al(68) GEM Detector Electric Field Simulation····································································BAI Xin-zhan, et al(68) Progress in Measuring 238U(n, xnγ) Cross Sections With HPGe Detector Array···WANG Zhao-hui, et al(69)

CONTENTS III

Design of Pre-collimator System for Neutronics Benchmark Experiment···················NIE Yang-bo, et al(70) Study of Fast Neutron Background Detection at Deep Underground Laboratory···············REN Jie, et al(71) Calibration of Li-glass Detector Efficiency·······················································ZHANG Qi-wei, et al(72) Lifetime Measurement of Inner Shell in the Collision of Fe, Au Ions and C Foil···CHANG Hong-wei, et al(73) Phase Stability of Intermetallic Compound Ce3Al in Mechanical Milling··········ZHANG Yan-ping, et al(74) Renewal and Modified Evaluation Data of 233U in CENDL-3.1·······························YU Bao-sheng, et al(75) Uncertainty Analysis for Neutron Leakage Spectrum of LLNL Pulsed Sphere Facility due to Fission Cross

Sections of 235U····························································································WANG Wen-ming, et al(77) Calculation of Prompt Fission Neutron Spectra for 235U (n, f) ···························CHEN Yong-jing, et al(78) Systematic Characteristics of Fast Neutron Fission Cross Sections for Actinide Nuclei·································· ·····························································································································WANG Ji-min, et al(79) Benchmarking 232Th Evaluations With KBR and Thor Experiments························WU Hai-cheng, et al(80) Study on the Processing Method for Resonance Self-shielding Calculations·····························LIU Ping(81) Research on Nuclear Reaction Network Equation for Fission Product Nuclides············QIAN Jing, et al(82) Iso-spin Dependent Microscopic Optical Model Potential Based on Dirac Bruckner Haretree Fock Method

··································································································································XU Rui-rui, et al(83) Preparation of 64Ni-Gd-Cu Target··················································································FAN Qi-wen, et al(84) Preparation of Super-Thin, Large-Area, Double-Sided Gold-Plated Mylar Film······ZHANG Rong, et al(84) Post Accelerator for Proposal of CARIF··········································································PENG Zhao-hua(85) Reliability Test of an ECR Ion Source for Accelerator Driven Sub-critical System (ADS) ···························· ······························································································································CUI Bao-qun, et al(86) Development of ECR Ion Source for ADS·····································································TANG Bing, et al(87) Installation and Trial Run of the Furnace··············································································HU Rui, et al(88) Progress in Neutron Texture Diffractometer at CARR···················································LI Mei-juan, et al(88) General Design for CARR Neutron Guide System···················································LIANG Feng, et al(89) Experimental Software Design of the Neutron Texture Diffractometer at China Advanced Research Reactor

···························································································································LIU Xiao-long, et al(90) Floating Zone Growth of LiFePO4 Single Crystals···············································TIAN Geng-fang, et al(91) H3

10BO3/ZnS(Ag) Scintillator Screen for Thermal Neutron Radiography····················WANG Yu, et al(91) Non-destructive-Testing of Nuclear Fuel Element by Means of Neutron Imaging Technique·························

·····························································································································WEI Guo-hai, et al(92) Crystal Structure and Thermal Expansion Properties of Lu2－xFexMo3O12··················WU Mei-mei, et al(92) Neutron Time of Flight Spectrometer for Velocity Selector Calibration·················YU Zhou-xiang, et al(93) Progress Report of Small Angle Neutron Scattering on CARR···································ZHANG Li, et al(94) Small Angle Neutron Scattering Study on Structure of PAMAM Dendrimer Encapsulation With Small

Molecules in Aqueous Solution··············································································LI Tian-fu, et al(95) Investigation on Crystal Structure, Magnetism and Colossal Magnetoresistance of Y2CrS4·························· ·······················································································································LIU Rong-deng, et al(95) Study on Different Forms of Calcium Metabolic Behavior in Normal and Osteoporosis Rats by 41Ca

Tracing··················································································································DOU Liang, et al(96) Discussions of Chemical Extraction Methods for Iodine-129 Determinations Using AMS System················ ······························································································································XIE Lin-bo, et al(96) Superheated Droplet Detector Response for Temperature··································HUANG Jin-feng, et al(97) Key Issue of Ultra-trace Environmental Samples by 236U/238U-AMS Method··············LIN De-yu, et al(98)

IV Annual Report of China Institute of Atomic Energy 2011

Suppression Factor of 182W for 182Hf AMS at CIAE·····················································LI Zhen-yu, et al(98) Study on Different Samples in Measurement of Manganese-53 With AMS······················HU Hao, et al(99) Design of Stopper of Prompt Gamma Neutron Activation Analysis Facility at China Advanced Research

Reactor··········································································································SUN Hong-chao, et al(100) Preliminary Study on the Determination of 235U and 239Pu Using Delayed Neutron Counting Method ····················································································································ZHANG Gui-ying, et al(102) Radiation Effect of CLAM Steel by Triple Ion Beams Irradiation····················ZHENG Yong-nan, et al(102) Investigation of H-Pd, H-PdAg and H-PdY Alloy Systems by Positron Annihilation Lifetime Spectroscopy

·····································································································································ZUO Yi, et al(104) A SSS Spectrometer ·······································································································LIU Yi-na, et al(105) Construction Design of Tissue-Equivalent Proportional Counter·······················ZHANG Wei-hua, et al(106) Manufacture of Single 60Co Source Irradiation Facility ···························································GAO Fei(107) Recent Progress in Research on Microcalorimeter for Radioactivity Measurement of Tritium······················

····························································································································CHEN Xi-lin, et al(107) Recent Progress in Liquid Scintillation Counting System for Absolute Radioactivity Measurement·············

·····························································································································LU Xiao-xia, et al(108) Design of Radioactive Reference Barrels and Simulation Verification of Linear Source································

································································································································XU Li-jun, et al(109) Study of Preparation of Large Area Standard Source ······················································LIN Min, et al(110) High Power Laser and Accelerator Development of Nanosecond Short Pulse High Power KrF Laser System··············GAO Zhi-xing, et al(111) Experimental Study on Planarity of Shock Waves Driven by High Power Eximer Laser Pluses·············· ·····································································································································LIANG Jing, et al(111) Energy Spectrum of Protons Driven by Ultra-short Laser Interaction With Thin Gold Foils ····················· ·······························································································································LU Jian-xin, et al(112) Influence of Laser Prepulse in Ultra-short Laser-Driven Proton Acceleration ···········LU Jian-xin, et al(112) Proton Acceleration Drived by High-intensity Ultraviolet Laser·································LU Jian-xin, et al(113) Plasma Expansions With Time-Dependent Electron Temperature ··············HUANG Yong-sheng, et al(113) Investigation of Isotope Separation Utilizing Spontaneous Magnetic Field of Ultra-Short Laser Pulses ····· ···········································································································································LI Ye-jun(114) Calculation for Improvement of 350 keV Electron Accelerator···············································LI Jin-hai(115) Research of Elements for Beam Redistribution·······························································LI Jin-hai, et al(115) Dynamics Calculation of CH-DTL···················································································LI Jin-hai, et al(115) Dynamics Calculation of Spoke························································································LI Jin-hai, et al(116) Dynamics Calculation of Travel Wave Tube····································································LI Jin-hai, et al(116) Calculation of Uniform of Beam Scanning··············································································LI Jin-hai (117) Design of Cavity for 10 MeV Electron Irradiation Accelerator··································MA Yan-yun, et al(117) Research of Quick-Response Protective System for Klystron of Multi-Energy Electron Linac··············

······································································································································TU Rui, et al(118) UHV Vacuum System R&D of Multi-Energy Electron LINAC·····································YIN Meng, et al(118) Self Shielding System R&D of 350 keV High-Voltage Electron Accelerator················YIN Meng, et al(118) Science and Technology of Reactor Nuclear Fuel Solution System Transient Analysis····························································YU Chao, et al(120)

CONTENTS V

Consultative Report on NPP Improving Loading Factor·····························································LV Niu (121) Study Report of Design Guide for Tube Arrays in Cross Flow ······································XUE Song-ling(121) Study Report of Design Guide for Single Circular Cylinder in Axial Flow····················XUE Song-ling(122) Study Report of Design Guide for Single Circular Cylinder in Turbulent Cross Flow···········XUE Song-ling(122) Numerical Model Analysis of Fluid-Elastic Instability of Thin Rectangular Plate Due to Overflow············

···································································································································LI Xiang, et al(123) Small Punch Test on Before and Post Irradiated Domestic Reactor Pressure Steel········································

······················································································································ZHONG Wei-hua, et al(124) Status of R&D on Tritium Permeation Barrier Coatings for Tritium Breeding Blanket of Fusion Reactor

····················································································································YUAN Xiao-ming, et al(125) Failure analysis for JNK Boracic acid Tank Room of NPP ·············································QIAN Jin, et al(125) Piping Stress Analysis of Secondary Cooling Water System in CARR··················DAI Shou-tong, et al(126) Stress Assessment of Security Injection Tank··························································DAI Shou-tong, et al(127) Thermal Stress Analysis of Security Injection Tank················································DAI Shou-tong, et al(128) Anchor Stress Checking of Security Injection Tank················································DAI Shou-tong, et al(129) Static Stress Analysis of Security Injection Tank····················································DAI Shou-tong, et al(130) Seism Analysis of Security Injection Tank······························································DAI Shou-tong, et al(131) Buckling Analysis of Supporting Skirt of Security Injection Tank·························DAI Shou-tong, et al(132) Radiation Measurement for Ji’Nan MNSR Decommissioning······································PENG Dan, et al(133) Preliminary Design of Special Unloading Tool for Miniature Neutron Source Reactor··································

································································································································HAO Qian, et al(134) DAQ System of Current Based on MNSR····························································HONG Jing-yan, et al(135) Preliminary Research of Neutron Energy Spectrum of Thermal Neutron Beam Port for IHNI·······················

·······································································································································LU Jin, et al(136)

Radiochemistry and Nuclear Chemistry Study on Anode Process in Molten Salt Electrolysis of CeO2····································LIN Ru-shan, et al(138) Concentration Determination of Tetravalent Uranium by Direct Spectrophotometric Method······················

····························································································································WANG Liang, et al(138) Determination of α Dose Rate of 238Pu Solution·························································LIU Jin-ping, et al(139) Preparation of Uranous Nitrate by Membrane Electrolysis·······························YUAN Zhong-wei, et al(140) Research of Trend of Technetium in U/Pu Partition Step of APOR Process················WANG Hui, et al(140) Extraction of Np(Ⅳ, Ⅴ, Ⅵ) Ions From Aqueous Nitric Acid Solutions With TODGA and DHOA·······

···························································································································ZHU Wen-bin, et al(141) Valance Adjustment of Np and Pu in 1AF Fluid of Pilot Plant································ZHU Wen-bin, et al(141) Study on Extraction Performance of Tri-iso-amyl Phosphate······························JIANG De-xiang, et al(142) Catalytic Reduction of U(Ⅳ) With Hydrazine in Nitric Acid Solutions·······························LI Bin, et al(142) Determination of Trace Plutonium in Uranium Product by ID-ICP-MS····························JIN Hua, et al(143) Determination of Micro U, Np, Pu by Highly Oriented Pyrolytic Graphite Pre-diffraction EDXRF·············

································································································································SONG You, et al(144) Analytical Instrument of X-ray Fluorescence Determine Concentration of U and Pu in Organic Solution at

the Same Time········································································································SONG You, et al(144) U(Ⅳ) Preparation by Method of Electrolysis································································FU Jian-li, et al(145) Separation and Purification of Fissiogenic Ruthenium From Irradiated Uranium···········································

····················································································································CHANG Zhi-yuan, et al(146)

VI Annual Report of China Institute of Atomic Energy 2011

Development of an Analytical System for Determination of Free Acid via a Joint Method Combining Density and conductivity Measurement·······························································FAN De-jun, et al(147)

Development of an Analytical System for Rapid, Remote Determining Concentration and Valence of Uranium and Plutonium··················································································LIU Huan-liang, et al(147)

Study of Multi Total Reflection X-ray Fluorescence Spectrometer······················KANG Hai-ying, et al(148) Study Progress of On-line Monitoring Device for Uranium and Plutonium by XRF······································ ·······················································································································KANG Hai-ying, et al(150) Study on Radiochemical Separation and Measurement of Half-life of 88Kr········YANG Zhi-hong, et al(150) A Method for Determination of 99Tc in Soils Using TEVA Resin··························YANG Su-liang, et al(151) A Convenient Method for Synthesis of 2-allyloxymethyl-18-crown-6··················YANG Su-liang, et al(152) Determination of Stability constant of Coordination Reaction of 2-allyloxymethyl-18-crown-6 with Sr2+ in

Water···············································································································YANG Su-liang, et al(153) Study on Performance of EmporeTM Technetium Rad Disks································YANG Su-liang, et al(154) Study on Performance of EmporeTM Strontium Rad Disks-Ⅱ·······························YANG Su-liang, et al(155) Sequential Separation of U, Np and Pu From Environmental Samples···············WANG Xiu-feng, et al(155) Separation of Uranium From Spent Fuel Solution in Burnup Measurements Process······································

································································································································YANG Lei, et al(156) Separation of Molybdenum From Spent Fuel Solution in Burnup Measurements Process·····························

·························································································································ZHAO Ya-ping, et al(157) Content of Transuranium Nuclide in Process of Irradiating Thorium······························MA Peng, et al(158) Morphology Characterization of Uranium Particles From Laser Ablated Uranium Materials························

·····························································································································ZHANG Yan, et al(159) Studies on Measurement of Impurities in Uranium Sample·····································ZHU Liu-chao, et al(159) Monitoring Fallout From Fukushima, Japan After Nuclear Accident···························LI Jian-hua, et al(160) Radioactive Waste Treatment and Disposal Preparation of Inorganic Sorbent KNiFC and Its Application·································YOU Xin-feng, et al(161) Preparation of Inorganic Sorbent for Strontium and Its Application·······················YOU Xin-feng, et al(161) Destruction of Tributyl Phosphate and Exchange Resin by Electrochemical Oxidation·································

·····································································································································MA Hui, et al(162)

Site Cleanup of Radioactive Isotope Container Rinsing Pool and Surrounding Environment························· ·························································································································GAN Xue-ying, et al(163)

Isotopes Biodistribution of 99Tcm Labelled Dextran Conjugates for Sentinel Lymph Node Detection·························

·······················································································································YANG Chun-hui, et al(164) Preparation, Radiolabelling and Biodistribution Study of 177Lu-DTPA-G3·········DENG Xin-rong, et al(165) Preparation and Biodistribution Evaluation in Mice of 177Lu-DOTA-TOC··········DENG Xin-rong, et al(165) Determining Contents of Five Impurities in Cyclotron-Produced 64Cu Solution by Emission Spectroscopy

·······························································································································JIANG Hua, et al(166) Determination of Medronic Acid and Its Related Substances by Reversed-Phase High-Performance Liquid

Chromatography······························································································ZHAO Xiu-yan, et al(166) Quantification of Kryptofix2.2.2 in18FDG by HPLC····················································ZHAO Yan, et al(166) Development of Up-Converting Phosphor Immunochromatography Test for Quantitative Detection of

Enrofloxacin···············································································································LI Li-bo, et al(167) Development of Up-Converting Phosphor Immunochromatography Test for Quantitative Detection of

CONTENTS VII

Sulfadiazin··················································································································LI Li-bo, et al(167) Specific Activity and Impurities in Irradiated Natural Nickel Target·························MA Jun-ping, et al(168) Determination of Two Columns’ Performance······························································LIU Zi-hua, et al(169) Applied Mathematics and Computer Technology Synchronizability Analysis of Harmonious Unification Hybrid Preferential Model·····LIU Qiang, et al(172) Algebraic Condition of Nonlinear Dynamical Network Synchronization······················LIU Qiang, et al(172) Unified Hybrid Network Theoretical Model Trilogy·····················································LIU Qiang, et al(173) Influence of Deterministic Attachments for Large Unifying Hybrid Network Model···LIU Qiang，et al(174) Influence of Random Attachments for Large Unifying Hybrid Network Model···········LIU Qiang, et al(175) Nuclear Safeguards Techniques Uranium Enrichment Analysis With Electromechanical Cooled HPGe Detector·····LIU Hong-bin, et al(176) Development of Uranium Works Reference Sample for NDA Measurement·················HE Li-xia, et al(176) γ Ray Radioactivity Measurement of 88Y and 22Na Point Source····································HE Li-xia, et al(177) Study on Application of Mobile Radiological Monitor··················································LI Xin-jun, et al(177) Emission Data-Analysis of TGS Under Continual Scanning Mode·························ZHOU Zhi-bo, et al(178) Transmission Data-Analysis of TGS Under Continual Scanning Mode···················ZHOU Zhi-bo, et al(178) Nuclear Material Accountancy Assessment Technical Measures in Nuclear Centrifuge Enrichment Facility

··································································································································GAO Xue-mei(179) Study on Calibration of Device of Heterogeneous Matrix With Uranium inside···············BAI Lei, et al(180) Software Development of Measurement System Heterogeneous Uranous Drums·········································

··························································································································SHAO Jie-wen, et al(181) Study on Automatic Control of Measurement System Heterogeneous Uranous Drums·································

··························································································································SHAO Jie-wen, et al(181) Physical Protection System Effectiveness Evaluation Project·················································ZONG Bo(182) Application Research of Developed Drummed Nuclear Waste Neutron Counting System·····························

······························································································································ZHU Li-qun, et al(182) Development on New Style of Drummed Nuclear Waste Neutron Counting System········ZHU Li-qun, et al(183) Radiation Protection and Environmental Protection Supervisory Monitoring of Workplace at CIAE in 2011·······································WANG Shao-lin, et al(184) The Biokinetic Model of Americium································································WANG Chuan-gao, et al(188) Research on Health Risk-Based Radioactive Acceptance Criteria of Municipal Solid Waste Landfill············

···················································································································ZHANG Hong-jian, et al(189) Simulation of High-Sensitive Measurement for 239Pu···························································WANG Wei(190) RESEARCH AND DEVELOPMENT FOR TECHNIQUE APPLICATION

Neutron Ghost Imaging Technology Research on CARR Reactor·······ZHANG Guo-guang, et al(195) Monte Carlo Simulation for Moderator of Compact D-T Neutron Generator···········DOU Yu-ling, et al(195) Mapping Nuclear Decay to Complex Network ··································································LI Yong, et al(196) Study of Associated α Particle Imaging Technique for Explosives Detection·········ZHENG Yu-lai，et al(197) Monte Carlo Simulation of Dosimetric Parameters for HYBRID PdI Source in Brachytherapy·····················

··························································································································ZHENG Yu-lai, et al(198) NQR Stimulation Technique for Explosives Detection System·······················HE Gao-kui, et al(199) Application of Grey Relational Cluster Method in Muon Tomography for Materials Detection ····················

VIII Annual Report of China Institute of Atomic Energy 2011

·······································································································································WANG Yue (199) IMPORTANT NUCLEAR INSTALLATION AND EQUIPMENT Annual Report on SPR Operation in 2011··········································································NIU Sheng-li(203) HI-13 Tandem Accelerator in 2011··········································································KAN Chao-xin, et al(205) Operation and Service Based on 5SDH-2 Accelerator········································WANG Zhi-qiang, et al(206) APPENDIX International Scientific Technology Exchanges in 2011·········································································(209) CIAE Seminars in 2011···························································································································(211) Subject of Prize of Science, Technology and Industry for National Defense··········································(214) Subject of Prize of Science & Technology for China National Nuclear Corporation·····························(215) Subject of Prize of Science & Technology for China Nuclear Energy Association·································(217) National Prize for Progress in Science and Technology on Energy in 2010·············································(218) Science and Technology Award of Beijing Municipality in 2010··················································(219) CIAE Application of Patent in 2011········································································································(220) CIAE Patent in 2011·································································································································(234) List of Scientific Publication in Foreign Languages in 2011··································································(244) List of Scientific Publication in Chinese in 2011····················································································(260) List of Lectures in International Meetings in 2011·················································································(272)

IMPORTANT NUCLEAR SCIENCE ENGINEERING·China Experimental Fast Reactor 3

China Experimental Fast Reactor (CEFR)

Progress of China Experimental Fast Reactor in 2011

ZHANG Dong-hui, ZHAO Jia-ning (China Experimental Fast Reactor Engineering Department)

1 Background

Fast reactor is the reactor which realized the chain fission with fast neutron. As an optional type of generation Ⅳ reactor, fast reactor has three characters: 1) It can change 238U to 239Pu and raise the uranium resource utilization fraction up to 60%-70%. This feature could ensure the sustainable development of nuclear energy; 2) It can transmute MA of PWR spent fuel. This feature could shorten the time of radioactive waste toxicity descending to the equivalent level of uranium ore from 300 000 years to thousands years; 3) It is very safe. Fast reactor has good inherence safety features such as negative feedback, low pressure, and large margin of thermal features, etc. And fast reactor could adopt many passive designs about safety systems. For example, passive residual heat removal system, passive overpressure protection system could be used. Off-site emergence action could be avoided with good safety design.

CEFR is an important project of 863 high-tech plan. The thermal power is 65 MW and electricity power is 20 MW. The first loading is UO2 fuel. CEFR adopt the pool-type design with Na-Na-H2O heat transform system. The passive residual heat removal systems are settled in main reactor vessel. The reactor contains totally 195 systems, such as reactor block, main heat transform system, auxiliary systems, fuel assembly handling system, radioactive waste treatment system, steam system, electricity system, I&C, safety engineering features, protection and control systems, ventilation systems, BOP, etc.

2 Power tests

CEFR was identified in 1995 and began to construct from 2000. The reactor reached the first physical criticality on July 21, 2010. All of the lower power tests had been done before the end of 2010. After strictly review, National Nuclear Safety Authority gave us the permission to raise power. The reactor began to raise power from February 9. All of the 35 tests had been done till July 3. And finally CEFR successful connected to the grid with 40% nominal full power at July 21.

During the process of power raising and experiments in 2011, reactor trip happened eight times totally. The system resistance is under fluctuation in this working condition. To solve the problem, the flow protection signal is delayed during the experiment and the methods such as preheating and valve opening by steps are used to decrease the system perturbation. The problem can be solved successfully.

In further work, to enhance the system reliability, the resistance equipment will be considered. The system characteristics will be modified to obey line 3. And the signal delay time will be optimized. The reactor trips during normal operation will be abstained efficiently.

We found and solved few defects of design and equipment and adjusted the reactor to a stable condition. A large amount of data has been gained from tests which proved the ability and safety feature of CEFR.

4 Annual Report of China Institute of Atomic Energy 2011

3 Electricity generation efficiency analysis CEFR reached the first connection to the grid on July 21, 2011 with 40% full power. According to

the calculation, the electric power should be 6.72 MW while the test result is 3.23 MW. In order to find out reasons, a calculation model was made according to the whole heat transfer procedure.

The calculation adopts equivalent enthalpy decrease method. The result shows that the heat loses and steam parameters low, tertiary loop working abnormal are main reasons.

According to the analysis, we should enhance the heat insulation, strengthen vacuum of condenser and put the reheat system into working to raise the electricity generation efficiency.

4 Conclusions

Power tests have been implemented in 2011 and the experiments according commissioning programme also have been implemented on each power level. The safety of reactor and designed capability has been verified and acquired a lot of experimental data. CEFR connecting grid successfully is the milestone for China’s fast reactor technology development, which laid solid foundation for further development of fast reactor technology.

Progress of Project “The Key Technology Research of Passive Shutdown System for CDFR”

HU Wen-jun, YANG Hong-yi, YU Hong, XUE Xiu-li, SONG Wei

(China Experimental Fast Reactor Engineering Department)

Passive shutdown technology is one of the key technologies to increase safety performance of

larger-size sodium-cooled fast reactors. The objective to the project was to develop the preliminary design of the rod on the basis of theoretic analysis of passive shutdown assembly.

In 2011, the following work was performed: 1) The dynamics grid technology was applied on the basis of commercial CFD software; 2) The simulation of the small-size scale benchmark was finished, and the velocity spectrum was gained; 3) The study of numerical method was focused on control equation, couple of pressure and velocity in fluid and such couple between velocity and pressure; 4) The draft of passive shutdown assembly was finished based on preliminary hydraulic analysis.

Summary of Research on Interactive Safety Analysis Program of Pool Type SFR

QIAN Hong-tao, TANG Hui-jian


The aim of the project was to develop an interactive safety analysis program of pool type sodium

cooled fast reactors (SFR), based on a French system code OASIS. The function and physical model of the program should be verified by the application on CEFR design.

An integrated model has been developed to simulate CEFR, including the primary circuit, the


intermediate circuit, the steam-water circuit and the decay heat removal system. Also the control and regulation system was simulated, including reactor protection system, power regulation system, steam pressure regulation system and water supply regulation system. The thermal hydraulics analysis under the various power level steady states, and 2 transient situations of loss of off-site power and a regulation rod uncontrolled pull out have been performed. The calculation results indicate that it is following.

1) The calculation results can be read directly, and the curve of the important parameters can be displayed dynamically when using the interactive program.

2) The analysis on steady state and transient states indicate that the performance of decay heat removal system accords with the design requirement. The reactor decay heat can be removed to the final heat sink of the atmosphere by natural convection in the event of loss of normal heat transfer path.

It can be concluded by the accident sequence analysis that the simulation of the control and regulation system and the response of various systems were reasonable.

Application of INPRO Methodology in Evaluation of Nonproliferation Features of TWR

ZHANG Jian, YANG Xiao-yan, QIAN Hong-tao


Through the once-through fuel cycle mode, the Traveling Wave Reactor (TWR) concept can utilize the uranium resources much effectively. The once-through fuel cycle has the inherent characteristics of the non-proliferation. In this project, the INPRO methodology is used to evaluate the inherent nonproliferation features of TWR core and its spent fuel reprocessing. The major work consists two parts: 1) Construction of the evaluation model of TWR and its spent fuel reprocessing; 2) Evaluate the nonproliferation ability of TWR and its spent fuel processing.

In this project, the nonproliferation abilities of different TWR core schemes and fuel cycles have been analyzed. This work is an example of the application of the INPRO methodology, and can guide the evaluation of Chinese nuclear energy systems and provide a reference for other nuclear energy systems to carry out such work. The evaluation results provide important technical reference for the TWR core design and fuel cycle design on how to consider the nonproliferation ability.

Measurement and Analysis of Sodium Void Reactivity Effect in CEFR

ZHOU Ke-yuan, YU Hong, HU Yun (China Experimental Fast Reactor Engineering Department)

The sodium void reactivity effect (SVRE) is one of the important parameters in the design and safety

analysis of sodium-cooled fast reactors. In some serious accident conditions, for example the total instantaneous blockage (TIB) accident, sodium boiling may happen in local area of reactor core, and then several kinds of feedback reactivity will be introduced followed by sodium void phenomenon, in which the most important reactivity effect is the sodium void reactivity. The measure value of SVRE will be


used in design verification and safety analysis. The SVRE worth has been measured at five typical positions in CEFR core during its physical

start-up test phase. The results have been analyzed and show good agreement to the test requirement. The results also verify the feasibility of using the rapid abnormal rising of RE rod as the inspection signal of TIB accident in CEFR. The theoretical calculation and analysis of the SVRE measuring test had been completed using CITATION code, which provide the data support before the test and verify the reliability of the analysis system after the test. Through this research project, the SVRE analysis technology of sodium-cooled fast reactor had been acquired.

Thermal Fatigue Analysis of Takeover Pipeline

HU Li-na, YU Hua-jin, WANG Yue-ying, LIU Jia, TANG Long (China Experimental Fast Reactor Engineering Department)

This article uses the finite element analysis software ANSYS to analyze the fatigue life of the three

links pipeline with different angles in the first level pipe of experimental fast reactor. The fatigue analysis is operated following the startup and shutdown process which has two load step,

the start temperature 250-495 as load one and, shutdown temperature 495-250 as load two. The permanent end of the z direction namely (axial displacement) is fixed, and the other end is fixed the displacement along x and y direction; also, axial displacement of the takeover is also fixed. The material of piping is 316L stainless steel and the material is reference to ASME Article Ⅱ of D of material properties. According to the ASME standard appendix Ⅰ-9.2.1, the fatigue design curve is carried out. Analysis of results: Figure 1 shows the local thermal stress cloud chart of the takeover with 60 . Choose three nodes in maximum thermal stress region, extract the stress values and calculated over the pipeline thermal fatigue life using the values. Table 1 lists the different stress amplitudes, the allowable number of cycles and fatigue damage coefficient when the takeover with different angles. Running 800/Fatigue damage coefficient are: 60º, 0.001 40; 75º, 0.002 33; 90º, 0.112 56; 105º, 0.509 87.

Conclusion: 1) The maximum thermal stress value appeared in the joints of pipeline and pipe; 2) With the increase of the angle between the permanent pipeline and takeover, the fatigue life reduced, the fatigue damage coefficient increased, and the fatigue allowable strength increased. This conclusion can be helpful for the opening hole and connecting pipeline design.

Fig. 1 Local thermal stress cloud chart of 60º take over


Table 1 Fatigue life and damage coefficient

Stress amplitude Sa/MPa 10－3 Allowable cycle number Nf Storage node

60º 75º 90º 105º 60º 75º 90º 105º

Node 1 213.17 360.67 470.47 712.67 747 27.00 7.711 1.504

Node 2 243.62 329.92 490.71 679.62 354 42.20 6.510 1.466

Node 3 226.63 342.25 480.23 697.39 611 35.15 7.100 1.738

Average value 227.81 343.28 480.48 719.49 571 38.12 7.107 1.569

Analysis of Design of Sodium Reception and Secondary Loop Sodium Plugging and Removal System for Fast Reactor

LIU Lin-ding, LUO Xue-jun, LI Jing


Through comparison of sodium reception and secondary loop sodium plugging and removal system on CEFR with BN-800, the main difference of the two designs is as follows: 1) System division is different. BN-800 can be divided into sodium reception system, secondary loop sodium storing system and secondary loop emission and exhaust system, but there is only one system on CEFR; 2) Equipment composition is different. In order to solve the problem of exhaust at high point and sodium discharge at low point, BN-800 installed some vacuum vessels. BN-800 augmented two electromagnetic pumps on account of arrangement need, and BN-800 didn’t install sodium filter; 3) System arrangement is different. The secondary loop sodium storing tank and the first-order emergent discharging tank are placed at the same level which is +9.000 m in BN-800, but there is about more than ten meters elevation difference in CEFR.

We will bring forward the system plan which is china commercial fast reactor may be adopted; the plan will be absorb the advantages on the basis of comparison between BN-800 and CEFR. The system is composed of sodium filters, sodium storing tanks, vacuum vessels, electromagnetic pumps, valves and pipes. The system should adopt sectioned range system; the sodium main is divided into three parts which can run independently and switch each other with valves. We should give full play to the advantages of two sets electromagnetic pumps, the system is receiving sodium while the other system can be fill up at the same time. Therefore, the receiving efficiency will be greatly increased. The rational potential difference at arrangement plan can achieve sodium discharge, except that you must use the electromagnetic pump to discharge sodium.

Acoustic Leak Detection Based on Wavelet Packet and Genetic Algorithm for LM FBR Steam Generators

WU Lin-lin, YU Hua-jin, WU Zhi-guang


Steam generator is one kind of key equipments in liquid metal fast breeder reactors (LM FBR) whose reliability will influence the safety of nuclear power plant. We can see that SG is the highest risky equipment from the running experience of all the LM FBR in the world. So, taking the detection earlier to SG, we can have


enough time to take action to avoid the happening of accident. Wavelet packet decomposition was used to compute the characteristic vectors of acoustic leak

signals in frequency ban. Strong fault-tolerant Shannon entropy was chosen as characteristic vectors, then, we can compute every ban’s Shannon entropy. Characteristic frequency ban depends on the contribution which devotes to noise by using genetic algorithm. Then, we can take detection of acoustic leak by enacting threshold. It is demonstrated through some experiments that the new proposed method performs well reliability and veracity, and it is effective to improve the sensibility of acoustic leak detection system.

Research on Valve Body Design of Large Bore Sodium Valve

LV Ming-yu, YU Hua-jin, LUO Xue-jun


Large bore sodium valve is one kind of key equipments of China Demonstration Fast Reactor (CDFR). It is installed in the pipeline before and behind SG units as a locking mechanism. Valve body which is used to bear pressure is the core of sodium valve design.

Considering characteristics of sodium valve, such as high temperature, low pressure, high sealing requirement, we adopt pressure-area method to determine design parameters of body of large bore sodium valve. Core idea of this method is that based on premising parameters of valve body, check primary membrane stress and primary membrane stress plus primary bending stress in sensitive area of valve body respectively. Then, through modifying and checking design parameters incessantly, all parameters of valve body can be determined. The detailed result lists in Table 1. Furthermore, the method which is used to design valve body of large bore sodium valve is formed.

Table 1 Design result of valve body of large bore sodium valve

Primary membrane stress check Primary membrane stress plus

primary bending stress check

Tr/mm Tb/mm Dj/mm LA/mm LN/mm Af/mm2 Am/mm2 Ca Peb/MPa

20 20 384 172 36.8 40 041 4 344 1 19.5

Analysis of Leak Before Break and Calculation Method of Critical Crack

LIU Jia, YU Hua-jin, WANG Yue-ying


Now leak before break (LBB) technology is widely used in nuclear power plant design. It has a good development in foreign countries, but domestic research is relatively little. The study of crack propagation is core of LBB analysis. It can be found that crack initiation and propagation is actually atomic changes and leads to dislocations and other microscopic changes, eventually leads to the macro result of material


damage. The classic elastic-plastic fracture mechanics ignore the discontinuity of the crack tip region and the whole pipeline defects; crack propagation computation based on atomic-scale molecular dynamics is huge, and time statistics is not easy. In order to get better results, developing multi-scale coupling of continuum mechanics and molecular dynamics methods is needed.

Bridging multi-scale method assumes that the coarse-scale finite element and fine-scale molecular dynamics exist in the entire computational domain. The entire displacement field can be written as:

u u u′= + u is the coarse-scale displacement, and u′ is the fine-scale displacement.

Coupled equations is written as： T( ) ( )Md t N f u= , A ( ) ( )M q t f q=

Where TAM N M N= , Two equations are coupled through the coarse scale force.

Coarse scale force is gained by the interpolation of finite element shape functions to molecular dynamics force. Coupled equation of Figure 1c is expressed by frontal equation. But the development of multi-scale is used for reducing the molecular dynamics calculations area. So the equation of Figure 1d model should be calculated.

Fig. 1 Model of Bridging multi-scale method

The coupled equation is T( ) ( )Md t N f u= ， impA 0( ) ( ) ( ) ( )M q t f q f t R t= + + .

Multi-scale method reflects not only the macroscopic properties of materials but also the material’s crack growth and the dislocations in the process of fatigue and creep deformation mechanism from the microscopic view. So introduction of multi-scale calculation is very necessary in the LBB design analysis.

Manufacture of Simulator of Irradiation Device for China Experimental Fast Reactor

HUANG Chen1, XU Xian2, XU Bao-yu1, SU Xi-ping1, YU Xiao-chen1, LI Hai1, DU Ai-bing1

(1. China Experimental Fast Reactor Engineering Department, China Institute of Atomic Energy;

2. Department of Reactor Engineering Research and Design)

This research belongs to the development of nuclear energy project of CEFR irradiation device design and previous studies of cladding material 316 (Ti) SS irradiation performance. The main content of the research is the development of irradiation device containing cladding material 316 (Ti) SS samples, mainly include irradiation device designing, irradiation samples’ preparation, irradiation device manufacture. The period of the work is from January 2010 to December 2012. Manufacture of irradiation


device simulator is the main research work of 2011, which is used for out-of-pile tests before the formal irradiation device fabrication, in order to verify the design. This article briefly describes the development work of irradiation device simulator carried out in 2011.

Irradiation device has the same outer structure as the other subassemblies in CEFR. The internal structure was designed according to the type and quantity of the irradiation sample of 316 (Ti) SS, which has three irradiation containers vertically settled. The irradiation container design is the key point to ensure the required irradiation temperature. The Irradiation container was designed with double-wall tubes, where the samples were set within the inner container immersed with liquid sodium, and 0.1 MPa helium was filled. Because of the good thermal conductivity of liquid metal, the samples within one container will have the same temperature. A different gap size between the double walls was designed filled with inertia gas in order to obtain the different irradiation temperature. Figure 1 shows the schematic diagram for the irradiation device; Figure 2 shows the simulator of irradiation container.

The main difficulties during irradiation container simulator manufacture lies in: 1) irradiation container processing: irradiation container involves two tanks (inner and outer ones),

which were obtained by processing the bar emptied; 2) welding of irradiation device: The irradiation device consists of three main components by

welding connection (handling head, the middle of the main part and leg). The straightness of the device after the welding is very strict;

3) sodium filling into the container: As many samples including the plate and tubular types inside the container, limited volume is left, which increases the difficulties for filling the liquid sodium completely.

Through the joint efforts of technical persons and processing masters, the above technical problems were basically solved, which laid the foundation for the subsequent formal irradiation device manufacture.

Fig. 1 Schematic diagram of irradiation device

Inner part Outer part

Fig. 2 Irradiation container simulator


Progress of Research on Demonstration Fast Reactor Main Pipe Material

LI Ya-ping, LUO Xue-jun


The main characteristics of the sodium pipe system in demonstration fast reactor are high-temperature, thin-wall and big-caliber, which is different from the high-pressure and thick-wall of the pressurized water reactor system, and the system is long-term operate in the environment of liquid metal sodium. How to guarantee the reliability of the system in high temperature is the first thing need to consider in design. The purpose of the research on demonstration fast reactor main pipe material is to get the all performance index of the material in high temperature sodium, and accumulate the test date for application; comparing the material’s capability of different fabrication technology to choose the suitable fabrication technology for demonstration fast reactor main pipe.

Based on the investigation of the domestic manufactory’s throughput, the longitudinal seam welding technology is considered as the fabrication technology of the demonstration fast reactor main pipe material. Before the domestic welding pipe used in the nuclear island of demonstration fast reactor in first time, the high temperature creep investigation on the base material, weld zone, fusion zone and heat affected zone, physical and mechanics property research, and corrosion property study in high temperature sodium should be carried through, that ensure the domestic welding pipe satisfied the design requirements.


China Advanced Research Reactor (CARR)

China Advanced Research Reactor Project Progress in 2011

ZHAO Tie-jun (Department of CARR Project)

2011, China Advanced Research Reactor (CARR) Project finished the B stage commissioning and

resolved the relative technical problems. Meanwhile, the acceptance items and the cold neutron source were carrying out. 1 B stage commissioning

Based on the experiments last year，the B stage commissioning came to the end in this January, while one of the safety rods stuck on January 11th when CARR started. Immediately the settling program was made by CARR Project department. After revising the design by Tsinghua University, the new safety rod prototype was made to verify the performance. In August the formal product was approved and installed into CARR. In this period, some systems were improved and such equipments as helium blowers and heavy water pumps were re-developed or repaired to make better ready for the following experiments.

On September 19th, the safety authority approved CARR to resume the commissioning. By the end of September, all the experiments in B stage were finished.

After safety checking extensively, the safety authority approved CARR to start the C stage commissioning on December 30th. 2 Acceptance items

All the acceptance items finished or were under way in 2011: 1) The documentations of design, construction, installation and equipments have been built; 2) The urban planning acceptance and fire control acceptance were applied for ratifying; 3) The environmental impact assessment report, occupation sanitation and occupation safety report

were under compiling and data monitoring; 3 Cold neutron source (CNS)

The design for the deuterium refrigeration system in the reactor finished in September and the equipments will be manufactured by foreign company. The helium refrigeration system was revised by the manufacture so as to adapt to the liquid deuterium system.

IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 13

Beijing Radioactive Ion-Beam Facility

Progress Report of Beijing Radioactive Ion-Beam Facility (BRIF) in 2011

YI Hui, SUN Yang (Division of the BRIF Project)

The year 2011 is featured with several important events for the Beijing Radioactive Ion-beam

Facility (BRIF) project. At the beginning of the year, the two divisions of the BRIF project, i.e. Engineering Division and Technology Division, have been merged into one as the BRIF Division. Following the structural re-organization, significant progresses have been achieved within the year, including the roof seal of the building by the end of the year, completion of the fabrication of major facilities for the project, and the successful pre-installation of key components at the temporary building.

1 Construction of the building and roof sealing

The BRIF project was granted the planning permission, building licence and construction licence at the beginning of the year, and on April 28, a ground breaking ceremony was conducted at CIAE, with attendees from a variety of institutions involved. At present, the roof sealing of the building has been realized after getting through a series of difficulties in the process.

The auxiliary devices, including the crane, protective door, water supply and drainage, regular devices, etc, have entered purchase phase. The contracts for the protective door and the crane have been concluded and the fabrication is under way. The water supply and drainage system as well as heating ventilation and air conditioning is to be contracted. The design of other equipments has been finished.

2 Check and acceptance procedure conducted for key devices of the main engineering system, and pre-installation of key devices of the cyclotron successfully performed

The CYCIAE-100 Cyclotron: So far the fabrication of key components of CYCIAE-100 has been accomplished, including the main magnet, main coil, main vacuum chamber, hydraulic elevating system, magnetic mapper and the 100 kW RF amplifier. The main magnet, weighing roughly 500 tons, has arrived at CIAE safely with the joint efforts of experts from CIAE and technicians from the factory. On October 8, 2011, a turn-over ceremony was held at CIAE to mark the event. The fabrication of the RF cavity is also finished and the check and acceptance is to be conducted soon.

After the main magnet, main coil, main vacuum chamber, hydraulic elevating system, and magnetic mapper are in place, per-installation was successfully carried out at the temporary building.

The purchase of the ion source, injection line and central region, the dual-extraction system and the power supply system has been conducted and is in smooth progress.

The Isotope Separator On Line (ISOL): The construction of key equipments for ISOL have been finished, the check and acceptance procedure has been performed for the pre-analysis magnet, main analysis magnet, bending magnet, switch magnet and vacuum tube. The experimental verification for the high pressure tube has been accomplished.


The Superconducting Booster (SCB): The Superconducting Booster has reached the sputtering condition after the experiment by nuclear physics department.

3 The quality control

Following the merging of the two independent divisions of the BRIF project, to adapt to the new organization, the BRIF division has updated the quality control system and has it implemented for the project.

Construction Progress of CYCIAE-100

The BRIF Division (Written by ZHANG Tian-jue, LI Zhen-guo, LV Yin-long)

Significant progress has been achieved in 2011 with respect to CYCIAE-100, a key task for the BRIF

project. All the work has been fully accomplished in line with the schedule and goals set for the year.

1 General progress for CYCIAE-100 1) Along with the proceeding of construction for CYCIAE-100, many critical technical modifications

have been proposed regarding the equipment layout, building design, including the location change of the beam commissioning target, passage of the cyclotron vault, structure of the protection door and crane, area of the control room, etc. All these have played an important role in the optimization of the building design.

2) Many measures have been implemented to ensure the technical requirements for the main engineering techniques are satisfied in the process of building construction, including constant on-site supervision, witness of important events, etc.

3) The work regarding the detailed design of major equipments, fabrication, and check and acceptance procedure is in smooth progress.

4) The construction of the temporary building has been accomplished and put into use, providing favorable condition for the pre-stage installation of key devices for CYCIAE-100.

5) The installation and commissioning of the major components for CYCIAE-100 has been accomplished in the temporary building, including the 416 t main magnet, coil of 200 000 ampere-turns, 200 t high precision hydraulic equipment, large-scale high precision magnetic mapper, etc. In addition, the work on high power RF cavity with a loaded Q value over 9 500 has started, as well as the installation and test of the 12-foil automatic exchanger for the stripping extraction system. 2 Progress of key tasks

By the end of 2011, the budget of the existing contracts for CYCIAE-100 has accounted for 87.6% of the total expenses. The fabrication of large-scale equipments has been accomplished one by one, and the check and acceptance has been performed for key devices. The installation and commissioning of many components, including the main magnet, main coil, hydraulic elevating system, magnetic mapper, high performance power supply, has been accomplished. The work on mapping and shimming is ready to start out.


1) Main magnet The check and acceptance procedure for the main magnet was conducted on July 30 of 2011, and the

components were transferred to CIAE on October 8, suggesting a new phase of the project. The pre-stage installation of key devices in the temporary building was done in November, as shown in Fig. 1.

2) Main coil and tuning coils The main coil and the harmonic coil for the return yokes have arrived at the temporary building. For

the main coil, it takes a ring shape with an outer radius of φ4 693 mm and an inner radius of φ4 206 mm. The height for a single piece is 358.5 mm with a net weight of 7 t. So far it has been the largest excitation coil in China. It is also the largest in dimension in the field of compact cyclotrons in the world. The assembly of the main magnet and main coil has been successfully conducted, as shown in Fig. 1.

3) Hydraulic system For the hydraulic elevating system, it has been assembled with the main coil in the temporary

building and the joint commissioning has been performed as well. The upper part of the main magnet, weighing about 200 t, has been lifted to a height of 1 400 mm and is moving stably up and down. The commissioning precision has fulfilled the design requirement, and the reset precision of the main magnet has reached ±0.02 mm.

4) RF system The fabrication and check and acceptance for the RF cavity have been accomplished. The cavity is

featured with a complicated structure, the largest ever in terms of dimension for cavities of similar accelerators in China, which places very challenging requirements on machining and welding. With the joint efforts from the specialists of CIAE and technicians of the factory, numerous technical problems have been successfully addressed in the process of cavity fabrication. After strict test and check and acceptance, it shows that the structural dimension of the RF cavity has met the specification in the drawings. The loaded Q value for the two cavities is over 9 500. The picture of the assembled cavity is shown in Fig. 2.

5) Vacuum system The fabrication of the main vacuum chamber has been finished, and the vacuum leak detection has

been performed under the condition of assembly. The main vacuum chamber has arrived at CIAE. The contract for another key device of the vacuum system, the cryogenerator, has been signed, and the fabrication has been accomplished. The engineering design of the cryopanel has been finished, ready for manufacturer selection.

Fig. 1 Installation of the main magnet

in the temporary building

Fig. 2 Cavities being assembled

6) Ion source and injection system The engineering design for the ion source and injection system has been accomplished and the


fabrication contract has been signed. Up to now the fabrication has been basically finished and after the check and acceptance procedure, the installation will be conducted in the temporary building for pre-stage commissioning.

7) Dual-extraction system The assembly for the target rod has been finished and the experimental verification has been

performed as well. The fabrication contract and check and acceptance procedure have been done for the target exchanger, slide way, inner rod, bellows, etc. The pre-stage installation of the first set of stripping target system is under way.

8) Magnetic mapping and shimming system The installation and assembly for the mapper and main magnet has been finished. A series of wok

has been performed thereafter, including the debugging of driving software for the mapper, measurement of the magnetic hysteresis loop and B-I characteristics, comprehensive analysis of the measuring accuracy of the mapper. On that basis, the preliminary mapping has been conducted on the median plane of the main magnet.

Fig. 3 Ion source and injection line Fig. 4 Magnetic mapper under installation and test

9) Power supply and electronics system The fabrication, measurement and check and acceptance have been finished for the digital power

supply of the main magnet. The long-term stability is better than ±1×10－5. The test with load shows that the performance satisfies the design requirement, as shown in Fig. 5.

Fig. 5 Long-term stability of the power supply for the main magnet

The development for the ion source power supply based on high voltage and high frequency isolation

technique has been accomplished and the check and acceptance procedure has been performed. The


design, fabrication, installation and test of the 8-passages power supply network measuring equipment have been finished, and the power distribution cabinet of the pneumatic system has been designed.

10) Water cooling and pneumatic system The fabrication of the water distribution cabinet has been finished. The contract for the circulating

water cooling unit (including deionized water production and water quality improvement equipment) has been signed, and the assembly for the pneumatic system has been accomplished.

11) Control, does monitoring and safety interlock system The fabrication of wide energy range neutron detector, including the related readout electronics, has

been finished. A set of EPICS device drivers for costumer detector readout VME module under real time operating system has also been carried out to interface the system to modern computers. Graphical human and machine for radiation supervisory and safety interlock system has been developed. The redundant PLC system in the hard wired safety interlocks system has been ordered in the same time.

Completion of Main Magnet Fabrication for CYCIAE-100

ZHANG Tian-jue, LV Yin-long, ZHONG Jun-qing, JING Wei, PAN Gao-feng, ZHANG Su-ping, XIE Huai-dong, WANG Zhen-hui, LIN Jun, LIU Geng-shou, YANG Fang

(Division of the BRIF Project)

The main magnet of CYCIAE-100, which weighs roughly 416 tons after machining, is mainly

consisting of 4 pairs of sector magnets, 4 return yokes, top/bottom yoke, central plug, and shimming bars. It falls into the category of large-scale high precision device, placing challenge on the processing and assembly of critical components featured with demanding precision requirement. The year 2011 has witnessed significant progress of the main magnet system, ranging from the component assembly, key dimension measurement, vacuum leak detection, packing and transportation, to the installation and assembly on site. 1 Component processing and assembly 1.1 Assembly and inspection of sector magnets and top/bottom yoke

After the measurement and matching with the angle of the 8 sector magnets conducted in 2010, it is required that the magnets be installed onto the top/bottom yoke. In order to reduce the error for measurement accuracy of laser tracker induced by outer vibration and the error of sector magnet expansion induced by temperature difference, while measuring the assembly accuracy, it is required that the device such as the crane in the assembly workshop cease to work and the assembly measurement for top/bottom yoke and sector magnets be conducted within the same time span. In the process of assembly and adjustment for the sector magnets, a specifically designed assembly tool is installed at a position corresponding to the valley of the top/bottom yoke so that the assembly can be carried out with direction. After repetitive measurements and adjustments, the assembly accuracy is shown in Fig. 1, which suggests that the gap between the outer border of the sector magnet and the groove of the top/bottom yoke is less than 0.03 mm and the gap between the surfaces of the sector magnets and the top/bottom yoke is less than 0.05 mm. It can be seen from Fig. 1 that the requirement for designed assembly accuracy between the top/bottom yoke and the sector magnets is satisfied. After the assembly is qualified, the angle in the valley keeps constant through repetitive turning and measurement. The gap between the arc surface for the inner


circle of the sector magnet and the surface for the outer circle of the central plug is less than 0.08 mm, and the measurement error of the surface between the shimming bar and central plug is less than 0.05 mm.

Fig. 1 Precision measurement for the assembly of sector magnets and top/bottom yoke

1.2 Assembly and measurement for the return and bottom yokes After the installation of the sector magnets, the first set of shimming bars is assembled at both sides

of the sector magnet. It suggests that gap between the surface of the sector magnets and side surface of the shimming bars is 0.03 mm and the gap between the surface of the sector magnets and bottom surface of the shimming bars is less than 0.03 mm. The surface of the shimming bars at both sides of the sector magnet has undergone several times of repairs to make sure that the surface gap between the front end of the two shimming bars at the upper and lower sector magnets is less than 0.05 mm. When the assembly for the top/bottom yoke, sector magnets, and shimming bars is completed, they are fixed to the 6.5 m planer-type milling machine for the processing of the elliptic contour surface of the top/bottom yoke and shimming bars. The head of the shimming bar has a central hole with a diameter of 40 mm and a fillet of R10. In order to ensure the cleanliness of the abutted surface between the sector magnets and the top/bottom yoke, it is required that no cooling liquid be applied to the milling machine and meanwhile, adhesive tape be used for the sealing of the abutted surfaces between sector magnets and top/bottom yoke, and between the sector magnets and the central plug to avoid the contamination. After the processing is completed, using the laser tracker, it can be seen that the difference between the measurement and the theoretic design value for the contour surface is within 0.05 mm, well satisfying the design requirement. 1.3 Processing of the elliptic surface for the sector magnets

The assembling steps for the return yokes can be divided as follows: 1) the 4 return yokes be installed to the bottom yoke, measure the distance between the two sides of the return yoke and the sector magnets to make sure that the distance keeps constant with each other, which suggests that the installation is basically completed; 2) measure the distance between the upper and lower sector magnets to determine the dimension of the seal surface of the upper and lower vacuum; 3) remover the top yoke, and put the assembled bottom yoke and the return yokes on the milling machine to reach the dimension of the upper surface; 4) put together the top and bottom yokes and measure the distance between the sector magnets until it meets the design requirement. The test of the laser tracker shows that the location displacement for the corresponding sector magnets about the return yoke is less than 0.15 mm, as shown in Fig. 2. The distance between the sector magnets at a radius of 2 000 mm is (48±0.03) mm. As the contour line of the sector magnet is a curve, after assembly is done, the error of the contour between the sector magnets is 0.07-0.08 mm, meeting the requirement of the design. When the assembly of the upper and lower sector magnets is finished, the


displacement of the side surface is within 0.05 mm, satisfying the requirement of physics design. 1.4 Vacuum leak detection for the main magnet and main vacuum chamber

After the installation of the components is completed for the main magnet system, the vacuum leak detection is jointly performed on the main magnet and vacuum chamber, with focus on the leak point detection of the seal surface between the vacuum chamber and the top/bottom yoke. The result shows that there is no leak point on the seal surface, well satisfying the design requirement.

2 Packing and transportation for the components of the main magnet system

Considering that CIAE is not capable of completing the assembly and flapping of the main magnet and top/bottom yoke alone, through repetitive discussions, it is determined that the top yoke and the 4 sector magnets be assembled during the packing before transportation, and the same applied to the bottom yoke and the other 4 sector magnets. During the transportation, the top yoke and sector magnets are placed upside down, and the bottom yoke and sector magnets are placed upwards. To avoid the collision and vibration deformation of key components during the transportation, there are 8 support points for the top yoke and sector magnets, among which 4 are positioned at the step of the sector magnet on the bottom, and fastened through the hole in the valley with a diameter of 500 mm. The strength of the support stem should be sufficiently good so that it could sustain the main magnet at the side while holding the weight. Another 4 support points are positioned at the contact surface between the top/bottom yoke and the return yokes, and it is required that the points be distributed along the transportation vehicle to avoid the possibility that the support is suspending at the two sides. The support points for the bottom yoke and sector magnets are positioned at the corresponding area in the valley where a special press board is placed to make sure there is no displacement between the magnet and the support. The side support of the magnet takes use of the 30º slope at the bottom yoke, where 4 supports are placed to restrict the side shift of the magnet. It is required that all the contact parts of the magnet be inserted with soft materials to prevent the magnet from abrasion. To ensure a smooth transportation without collision, it is required that wrapping cover be specially made and the connection between the wrapping cover and the support be conducted through bolts.

Fig. 2 Inspection result for installation of return yokes

Fig. 3 Packing of the top yoke and sector magnets 3 Main magnet installation of the temporary building

Given the fact that the main magnet of CYCIAE-100 is heavy precision device, and the temporary building is incapable of the hoisting, a steel intermediate transfer rack is installed in the building. The installation and assembly of the main magnet in the temporary building can be divided into several steps. The


bottom yoke and sector magnets are transported to the transfer rack, where they are dismounted. Then the balance beam is connected to the horizontal hoisting tool of the bottom yoke and the bottom yoke is lifted through four 200-ton hydraulic jacks. After that, the bottom yoke is moved to the installation base though the vehicle of the transfer rack and the 4 lifting racks are used to support the bottom yoke in a steady way. The support legs of the main magnet are installed, and the bottom yoke is put down and the support legs are fixed to the base. There are 4 pieces of return yokes in total, each weighing roughly 16 tons. The return yokes can be hoisted to the installation position through a 50-ton chain block. For the 2 coils, weighing roughly 7 tons each, they are hoisted to the installation position through the combined efforts of vehicle and the chain block. Meanwhile, adjustments are performed on the coil so that the gap between the coil and the inner circle of the 4 return yokes is of the same distance, the error of which is within ±1 mm. Similar approach is applied to the top yoke. Together with the sector magnets, the top yoke is elevated to the height of the return yoke, moved horizontally right above the bottom yoke, and then to be lowered slowly. By fine tuning the azimuthal angle on the top yoke, the landing point can be right on the pin bolt of the return yoke. The 4 hydraulic cylinders for the hydraulic system will be installed at last. Following the installation and assembly of the main magnet, some key dimensions of the sector magnets are precisely measured with laser tracker API LT-3 fabricated by Automated Precision Inc (API) in the U.S., including the shift of the upper and lower sector magnets, contour error between the sector magnets, and etc. The measurement is consistent with the result out of the factory, showing that the key parameters of the main magnet remain unchanged during the transportation and installation in the temporary building. The key precision requirements have been well satisfied, laying a solid base for the follow-up mapping and shimming.

To sum up, significant progress has been achieved in 2011 for the main magnet development of CYCIAE-100. On April 28, the pre-installation on the site was completed and the precision inspection was passed. By the end of June, the on-site check and acceptance by a group of experts from COSTIND, CNNC and CIAE was successfully conducted. On October 8, the main magnet was transported to CIAE with a smooth turn-over. On November 9, the installation of the main magnet in the temporary was finished, followed by the magnetic mapping, marking the completion of main magnet construction.

Progress of the Water Cooling System for CYCIAE-100

LI Zhen-guo, WU Long-cheng, ZHOU Zhi-wei (Division of the BRIF Project)

The civil building construction of the BRIF project started at the end of April in 2011. The key

systems of CYCIAE-100 were completed one after another. The water cooling system for CYCIAE-100 also made a significant progress in 2011, and its progress can be summarized as follows.

1) Based on the engineering design of the water cooling system and the preliminary layout of civil building construction, many meetings were held together with building design unit and some

Fig. 4 Installation of main magnet in the temporary building


modifications were made, including location change of target cooling system and location change of water sewage pit No.4, etc., finally the building construction schematics were reasonably improved and countersigned. All these assured the BRIF civil building construction started on time.

2) The main tubes of water cooling system for CYCIAE-100 need to pass through concrete protection walls of 3.0-3.5 m sick. They should be laid down at the early phase during the building construction. If some things go wrong, it would cause irretrievable loss to later stage work. The field witness was upheld in cooperation with construction management department at the crucial points. When the problems show up, correction was soon made and formal correction file was provided in time. In these ways, some errors were effectively avoided.

3) Circulating water cooling unit (including deionized water production and water quality improvement equipment) is the key device of CYCIAE-100 water cooling system. Its purchase procedure began in 2011. After market survey and technical exchanges, qualified supplies were fixed. The preferred supply was chosen by competitive negotiation, and the formal contract was signed afterwards.

4) Seven water distribution cabinets were manufactured. All major components used inside water distribution cabinets were purchased and installed.

5) Based on the designed parameters, market survey and sample test were conducted for flexible tubes leading to specific equipments. The special tool (clasping pipeline machine) for flexible tube connector making was purchased.

6) The design of temperature monitoring system for water branches has been fixed and the pretest was conduced. The temperature sensor selection and control circuit design have been done in a way that satisfies the requirements of high radioactivity environments, and abides by the principle of easy installation and free from maintenance.

All the equipments of water cooling system for CYCIAE-100 will be implemented after July in 2012 according to the BRIF project schedule plan.

Main Magnet Installation in the Temporary Building for CYCIAE-100

LV Yin-long, WANG Zhen-hui, CUI Tao, ZHANG Tian-jue, JING Wei, CAI Hong-ru, LIN Jun (Division of the BRIF Project)

The main magnet of CYCIAE-100 was delivered to CIAE on October 5th, 2011, following which the

installation was conducted in the temporary building. The temporary building is located in the south of the cyclotron lab, and the equipments of the BRIF project are stocked and tested there. The main magnet is installed on the 500 tons bearing foundation of concrete, which was completed on November 9, 2011, the main magnet, coils, and hydraulic elevating system.

The total weight of the main magnet is about 416 tons, and the largest single part of the magnet is about 170 tons. It is extremely difficult to install the main magnet because only one lifting crane with a capacity of 10 tons is available in the temporary building. A steel structure is specially designed to transfer the main magnet to ensure the safety of the main magnet lifting process, minimizing the risk. The steel structure has been tested in both static and dynamic modes by a simulate load weight 200 tons. The crane employed during the installation 0 is not large, which has saved a lot of project costs. On November 11, the BRIF Division invited the QC personnel of CITIC Heavy Industries to test the installation accuracy of the main magnet. The test results show that the main magnet installation has met the design accuracy.


1 The steel transport frame for installation The specifically designed steel transport frame for the main magnet installation is composed by steel

brackets and carriage. The steel brackets with a designed carrying capacity of 250 tons have 8 steel columns of H500×300 steel, and each column is 7 m in height. The carrying steel beams are located on the columns, and the H shape of the beam is 500×450×70×50, enhanced with the 20 mm thick steel plate. The maximum column space is 7 500 mm. The columns are enhanced by stiffener support, which can effectively reduce the stress within the main beam. The steel structure has lateral oblique support to enhance the stability, reducing the vibration amplitude of the steel structure. Small section steel beam connections between the main beam at both ends of the column, the entire steel structure has been an overall framework structure, to enhance the stability and to reduce the risk of local partial load instability. To ensure the carrying capacity of the steel structure, the column foundation of the steel structure is 3.5 m×3.5 m×1.5 m in dimension, which has reinforced concrete foundation.

The main load bearing structure of transporter part of the framework structure is the two long 8 m beams with a cross section of H800×500×50×45. The material is Q345. Above the beams there are three connecting beams, each end of the connecting beam hanging one 50 tons chain hoist. In total there are six chain hoists. The three chain hoists on each side of connecting beams connect a balance beam. Both ends of the balance beam are connected to the hanging point of the main magnet. The adoption of balance beams can effectively reduce the risk of partial load or single chain hoist overload failure.

Fig. 1 Special designed steel transport frame Fig. 2 Load test of the transport frame

In order to verify the carrying capacity of the steel structure, a tank capable of carrying 200 tons of

water is specially designed and fabricated to simulate the magnet. The carrying capacity test is divided into two stages. The first stage is static load test, for which the transport frame is moved over the water tank, and the 6 chain hoists lift the tank off the ground about 200 mm, staying there for more than 24 hours. Then checks are conducted on the weld cracking of the steel structural frame, and deformation of the force components. The second stage is dynamic test, for which the 200 tons water tank is hanged under the transporter by 6 chain hoists, and then the transporter is slowly pushed along the orbit one round trip. Then checks are performed on the weld cracking of the steel brackets, and the deformation of main force components. It has been found that in the dynamic load test the entire steel bracket vibrated acutely. This problem has been solved by replacing the transporter skateboards.

2 The installation process

The main magnet for CYCIAE-100 is heavy-duty precision equipment, and the accuracy of the key components is about 0.05 mm, placing extremely strict requirements on the installation accuracy. The main components of the main magnet are consisting of the upper cover and poles assembly (170 tons), the bottom cover and poles assembly (170 tons), the magnetic yokes (16 tons each, 4 parts), the main coil


(7 tons per piece, 2 parts), legs (each weighing 1.5 tons, 4 parts), and the hydraulic lifting device (each weighing 8 tons, 4 sets).

Installation steps: The first step is to determine the location of the four legs, and to mark on the ground-based embedded steel plates, and then the legs are put in place. The second step is to move the transporter outdoors. The large transport vehicle takes the cover and poles assembly transport below the transporter. It is required that the cover center be aligned with the center of the transporter, and the error does not exceed 0.2 m on horizontal direction. By 6 chain hoists the cover plate and poles assembly are lifted from the truck about 0.5 m. Then the truck drives away. The third step is that the transporter hanging the cover and poles assembly is pushed to the upper of the four legs center. After precise adjustment the cover and poles assembly drop down slowly upon the four support legs. The level of degree requirements of the magnet is 0.2/1 000. By adjusting the thickness of the plates below the four legs, the level of degrees measured of the lower cover has been adjusted to achieve 0.1/1 000. The fourth step is that the four yokes moved to the corresponding position piece by piece, aligned to the pin, the gap adjusted between the yoke inner circle and the cover to the requirement of 0.10-0.15 mm. Then the bolts are fixed. The fifth step is to install the main coils. Due to the large size, high precision of installation, the transporter is used to carry the main coils. The main coil has been put in position, and the gap between the main coil and the yoke inner circle is adjusted to meet the requirement of the uniformity of the gap value that is better than ±2 mm. The gap value uniformity measured after the installation is better than ±1 mm. The sixth step is to install the upper cover and poles assembly. The process of the upper cover and poles assemble is similar to the second step. The transporter carries the upper cover and poles assembly to a position next to the installed lower cover. The cover and poles assembly is lifted to a height of 4 800 mm. The transporter is moved to the above of the lower cover and the center is aligned. The cover is dropped down slowly, and put in place. The seventh step is to install the hydraulic elevating system. In order to speed up the progress of the installation, the four sets of hydraulic lifting device are directly put in place by a crane of 25 tons in the temporary building. Then the hydraulic lifting device is connected with the main magnet.

The main magnet and related equipments have been successfully installed after about one month efforts. The BRIF Division invited CITIC quality control personnel to test the installation accuracy, with American Automatic Precision Engineering Company API LT-3 laser tracker. They accurately measured the critical dimensions of the main magnet, such as the upper and lower magnetic pole side alignment, the amount of air-gap error. The measurement results are consistent with the results of measurements in CITIC. The results indicate that the pre-stage installation does not change the key parameters of the main magnet. The main magnet critical precision has met the design requirements. The main magnet installation in the temporary building has been successfully completed, providing favorable conditions for the follow-up magnetic mapping and shimming.

Fig. 3 The lower cover installation Fig. 4 The upper cover installation


Installation and Commissioning of the Main Magnet Elevating System for CYCIAE-100

LV Yin-long, YIN Zhi-guo, LIN Jun


The main magnet elevating system is a key part for CYCIAE-100. The raising device will play an important role throughout the process of installation, magnetic mapping, vacuum leak detection, beam commissioning, and maintenance. It has a design lifting weight of 180 t and a lifting height of 1 500 mm. The hydraulic synchronized raising applies servo valve closed loop feedback controlling design, and the precision of the four jars is 0.20 mm.

The elevating device was accepted in December 2010, and installed with the main magnet in April 2011 in CITIC. In November 2011 the elevating device was delivered and installed at CIAE.

1 The test installation in CITIC

The main magnet was manufactured by CITIC Heavy Industries. Because of the hydraulic lift and the main magnet connection interface requirements with precision, the test assembly must be done in the main magnet factory. The main intention of the tentative installation in CITIC is to match the jars and the upper magnet part. It has been found in the test assembly process that the pins of lifting are too difficult to put in the holes of the upper magnet part. The problem has been solved by grinding the pins. When the elevating system and the main magnet test assembly is completed, the elevating system has been tested under real load, with a maximum lifting height of 200 mm, a measured synchronization accuracy of 0.20 mm, and the main magnet lifting reset accuracy of better than 0.02 mm.

2 The elevating system installation and commissioning in the temporary building

On October 5, 2011 the main magnet was delivered to CIAE. The installation of the main magnet was completed in early November in the temporary building, which was followed by the installation of the hydraulic elevating system. Before the installation, the whole system should to be tested in the no-load conditions. The four hydraulic cylinders synchronization accuracy should be adjusted to be better than 0.20 mm. Then, the hydraulic elevating system was connected with the upper part of the magnet. After carefully adjusting the verticality of the four hydraulic cylinders, the hydraulic cylinder support seat was embedded with ground plate.

The lifting weight is about 170 tons, and the maximum design working pressure of the hydraulic system is about 21 MPa. When the actual pressure in the test is about 13 MPa, the four-cylinder pressure difference is no more than 20%, suggesting the four-cylinder load difference is no more than 20%. After a week of testing, the main magnet cover could maintain a steady level, and the four-cylinder lifting height error can be controlled less than 0.20 mm. Within the scope (1 500 mm), the four-cylinder load is basically balanced, and the pressure error is less than 20%. The technical indicators have reached the

Fig. 1 Hydraulic elevating system and main magnet


design requirements. The magnet elevating system is among the first in the cyclotron field that applies closed-loop

controlled hydraulic synchronous elevating system. The system has merits of high precision, good accurate reset precision, easy operation, more measured parameters than other systems as the screw lifting system and pen-loop hydraulic lifting system. The system has high application value in the field of large compact cyclotron.

Fig. 2 Test without load Fig. 3 Installation of the hydraulic elevating system

Installation of the Magnetic Mapping Device for CYCIAE-100

LV Yin-long, ZHONG Jun-qing, CAO Lei, YIN Zhi-guo, WANG Zhen-hui (Division of the BRIF Project)

On November 9, 2011, the installation for the main magnet of CYCIAE-100 was completed in the

BRIF temporary building, entering into the stage of magnetic mapping and shimming. The mapper has been a specially designed two-dimensional auto–control mapping device, which is featured with high precision, high speed, easy manipulation. In total four Hall probes will be installed for the mapping system, so four magnetic field data can be obtained at every point. For the first time installation, there are three Hall probes. Before the formal mapping is conducted, one needs to make sure that the mapping device should be accurately installed and the positioning accuracy be fine tuned.

Based on the installation experience achieved on the simulation platform, the installation sequence is identified as: aluminum alloy rails, the measuring arm parts, the radial motion drive components, parts of the azimuth movement drive components, central parts, radial positioning grating and the Hall probe, grating reading head. The circular aluminum alloy rail is required to match the outer pole edge. The gap between the rail and pole edge should be checked after installation. The gear of mapping device rotating is set to be precise by adjusting the gap, in order to reduce the backspace, and to get a good positioning accuracy. Grating and grating reading head, Hall probes, and other precision measuring devices are buried in the radial arm. When the installation is under way, both the accuracy and the cable direction should be ensured to prevent the possible wounding. The installation of grating, grating reading head, and the Hall probes is shown in Fig. 1, and the installation of mapping device in the main magnet is shown in Fig. 2.


Fig. 1 Hall probes installation Fig. 2 Mapping device in the magnet

It is required that the mapping of the axial field of the main magnet be conducted at the center plane of the

air gap, thus the Hall probe is required in the plane of the air gap. This is very challenging for the range of magnetic field with a diameter of 4 000 mm. After repeated adjustments, the vertical distance of the Hall probe and the air gap center can be controlled within ±0.10 mm. In order to accurately find the definition of the reading head in the grating zero position and to ensure the movement of the grating head not to exceed the grating, the limit switches are set to control both ends of the grating. z signal points from the small radius limit switch are set to be the beginning of starting point. The radial accuracy is shown in Fig. 3, from which it can be seen that in the radial direction with the grating and the servo controlled system a good accuracy can be achieved, and the radial accuracy can be controlled within 0.08 mm, fully meeting the design requirements. The magnetic mapping has started following the installation of mapper on the main magnet. In the case of three Hall probes, it takes about 30 hours to map the field (72 000 data points) at one time. The mapping process does not need human operator intervention. The magnetic field data, the position data, temperature and other parameters are automatically saved. In this way it not only reduces the amount of labor intensity, but it also improves the efficiency of the mapping. Grating is used for two-dimensional position of the mapping, which improves the mapping accuracy.

Mapping and Shimming of Magnetic Field in CYCIAE-14

ZHONG Jun-qing, CUI Tao, YIN Zhi-guo, LI Ming, WANG Chuan, LV Yin-long, ZHANG Tian-jue, GE Tao, LIU Geng-shou, WANG Zhen-hui


The mapping system of magnetic field in CYCIAE-14 is comprised of rotatable beam, stepping

Fig. 3 The radial accuracy


motor, optical encoder, Tesla meter, driving system and position system, etc. In order to get the high precision in azimuthal position, the closed loop has been adopted, and the driving system and position system for azimuthal position are parted. The hall probe is fixed in beam, and the beam is connected with position axis by the orientable pin. The encoder is fixed in bottom of position axis. The precision in radial is depending on the high precision blocks fixed in rotatable beam.

We tracked the particle in field by beam dynamics coder after completing the mapping field. Consequently, we can obtain the relationship of the isochronous field shift with a stable equilibrium orbit. Grounded on data of the magnetic field error and the vertical betatron frequency, we got the data of the shimming bars by the algorithm of shimming based on odd and oven triangle. The result of shimming and the comparison of the results from several methods are shown in Figure 1. As is shown in Figure 1, except for the centre region, the measurement result is consistent with that from the algorithm of shimming and simulated result from FEM. The reason inducing the error of field in centre region is that the change of average field is not linear with the cutting depth when the cutting depth of shimming bar is so large.

We get the isochronous field and high vertical focusing field in median plane after undergoing several times of magnetic field measurement and shimming. The results of beam dynamics based on the static equilibrium orbit are shown in Figure 2 and 3. The Walkinshaw resonance is avoided in extraction region, and the integral phase shift is limited to ±8º. The maximum energy of particle is 14.2 MeV.

Fig. 2 Axial focusing and half radial focusing Fig. 3 The integral phase shift

Primary Design and Study of the Lattice Structure in Scaling FFAG

LI Ming, ZHANG Tian-jue, ZHONG Jun-qing, AN Shi-zhong (Division of the BRIF Project)

The principle of FFAG (Fixed Field Alternating Gradient) accelerator, which was first put forward

independently by Ohkawa, Symon and Kolomensky in 1950s and then developed rapidly in 1990s, has in recent years become a new direction in the domain of international accelerator. In the process of development, FFAG is divided into two different types, Scaling FFAG and Non-Scaling FFAG, according

Fig. 1 The results of shimming in CYCIAE-14


to the magnetic focusing structure. Scaling FFAG, in which the betatron tunes are constant and beam can be avoided to cross betatron resonances during acceleration, has been widely studied in Japan. Non-scaling FFAG, in which betatron resonances can not be avoided, can be adapted to the situation that needs to accelerate particles fast. Among the built FFAGs, there is only one non-scaling FFAG used to demonstrate the basic principle, and the rest are scaling FFAGs, all of which are built in Japan and the design methods are very mature. At present, national research on FFAG is behindhand, and it is for this reason that CIAE is planning to study the theory and critical techniques of FFAG. As lattice design is first step to design a FFAG, we choose to study the lattice design in scaling FFAG as primary exploration.

1 Research method

As in the synchrotron, the lattice structure can be optimized through analyzing the beam optic properties, including focusing characters, beam envelop and dispersion etc. In scaling FFAG, the chromaticity is zero and beam optics is kept unchanged during the acceleration, so a fixed energy could be assumed here. Detail steps are outlined below.

1) Choosing the basic parameters of the FFAG, including (1) Lattice structure: FO (spiraling sectors), doublet ( FO1DO2), triplet (DFD or FDF) etc. (2) The injected and extracted energy of the particle accelerated in FFAG. (3) Number of the sectors N, field index, the maximum radius of the orbits, the difference between

minimum and maximum radius, where a relation among the latter three parameters could be written as: r=Δr/(1－(Pext/Pinj)

－1/(K+1)) 2) Determining the closed orbit As the magnetic field of the lattice elements in FFAG is complicated, closed orbits are difficult to be

obtained unless the real magnetic field is got through Finite Element Method (FEM). But as a primary design and study, we use the hard edge approximation and meanwhile assume the field changes little when the particle bends in the magnet. As a result, the trajectory of the particle could be regarded as composition of some arcs and drifts.

3) Solving the beam optics Considering the suppositions above, the beam optic properties could be obtained easily through the

transport matrix of bend magnets, edge angles and drifts. 2 Results

The upper chapter gives the basic method to design a scaling FFAG, here we take a FFAG for the proton therapy as an example, in which the DFD structure is selected, the injected and extracted energy are 30 MeV and 230 MeV respectively, and N=12, K=9 are assumed in the design. In order to decrease the size of the magnet, we choose Δr to be 0.5 m and therefore the maximum orbit of the orbit is about 5 m. Through the method illustrated above, the lattice periods of the FFAG and the closed orbits at different energies could be shown in Figure 1 (left), and the envelop functions could be shown in Figure 1 (right). In this FFAG, the designed parameters of the lattice are shown as follows: angle of the F magnet θF=14º, angle of the D magnet θD=4º, and thereby the angle of the drift θL=8º, maximum field value in the median plane of F magnet is about 1.8 T and the direction of field in the median plane of D magnet is opposite, with a maximum value about 1.5 T. The tunes reflect the focusing characteristics of the FFAG, which can be expressed as Qx=4.4 and Qz=1.6.

3 Summary

The ways to design lattice periods in FFAG and synchrotron are basically similar to each other, and the difference is that the issue of closed orbits in the synchrotron does not have to be solved as it is


determined by the positions of the elements. The previous chapter gives the designed results of the lattice in a FFAG for proton therapy, in which the negative field is introduced to strengthen the effects of alternating gradient focusing. As a result, it makes the circumference of the accelerator much larger, and the factor to show the gained circumference could be expressed as

f=(θF+2θD)/(θF－2θD)≈3.7 It suggests that the circumference of the FFAG is 3.7 times of that of the equivalent synchrotron. But

as the benefit of this, the magnetic field in the FFAG is fixed, the repetition frequency of extracted beam is determined by the frequency for RF tuning, which could be at the level of kHz.

Fig. 1 DFD lattice period and closed orbits at different energies in the FFAG

for proton therapy (left) and beam envelop functions (right)

In this paper, the basic steps and method for primary lattice design in the scaling FFAG are demonstrated, taking DFD structure in a FFAG for proton therapy as an example. The determined parameters are beneficial for the latter three-dimensional magnet design, but the final design should be optimized through tracking the beam optics in the FFAG.

Processing and Installation of the Stripping Probe for CYCIAE-100

XIE Huai-dong, AN Shi-zhong, GUAN Feng-ping (Division of the BRIF Project)

The stripping extraction system for CYCIAE-100 is designed to extract proton beams of 75-100 MeV

in dual opposite directions by charge exchange stripping devices. The stripping probe is the most critical and complicated device in the system. According to the requirement of striping, the probe should be radially inserted into the gap between the sector magnets. In order to ensure the ion beams at different energies after stripping will reach the center of the combination magnet, it is required that the stripping probe be capable of both moving in the radial direction and rotating in the angular direction. The precision requirement of positioning is also high with respect to the motion of stripping probe

The mechanical design of the main part of the stripping probe has been completed in July 2010. The model is shown in Fig. 1.


Fig. 1 Main part of the stripping probe

The stripping probe is mainly consisting of 6 parts, i. e., foil exchanger, rotation driver, rotation

support, rod motion, bellows and the base.

Fig. 2 Processing for target exchanger parts Fig. 3 Motion base unit being processed

Fig. 4 Reliability verification test Fig. 5 Picture of on-site assembly for the stripping probe

At present, the main components of the stripping probe has been procured and processed, and they

are in place at the temporary plant for assembly.

Mechanic Design of the Radial Probe Target for CYCIAE-100

XIE Huai-dong, GUAN Feng-ping, WEN Li-peng (Division of the BRIF Project)

The radial probe target is an important diagnostic component of CYCIAE-100 that adopts blocking

measurement. The probe placed in the median plane of sector gap of the cyclotron is mainly used to measure both the radial and vertical cross-sections of the beam, thus get the corresponding beam


distribution in both directions. The radially inserted target normally uses radial insertion, which is inserted from the symmetric center of the valley or the peak area.

As the beam measuring range has a span of 2 020 mm from the main vacuum chamber wall to the center of the accelerator, the most challenging part for the design is that the cantilever is too long for the target rod. In the design, it adopts a structure that the support sleeve is installed at the front-end of the device, and the front-end support of the target rod is installed in the sleeve. The front-end support of the target bar is near the main vacuum chamber flapper valve, and the target rod cantilever is shortened to 3 150 mm in length. In addition, the target tip uses a plug-in structure, for which the tip can be easily replaced to meet the different needs of the beam measurement.

The main structure of the radial target can be divided into the following parts: the front-end support of the target rod, the rod assembly, rod motion, bellows, and the base. The mechanical design of main part of the radial target was completed in December 2011, with a total number of parts over 1 000, among which more than 100 parts are of different category. There are nearly 100 non-standard parts, and 73 engineering drawings. The model is shown in Fig. 1.

Fig. 1 Model of the main part for the radial target

Calculation of New Beam Dump Shielding for CYCIAE-100

WANG Feng, JIA Xian-lu, WEI Su-min (Division of the BRIF Project)

The 100 MeV high intensity cyclotron, CYCIAE-100, places a demanding requirement on the

collection device to accept the proton beam. According to the original design, the beam dump would be settled in the cyclotron vault. It uses pure aluminum as the target material, and the major shielding adopts 30 cm iron and 1 m heavy concrete. The target is consisting of seven aluminum slices with different thickness, and there is the cooling water between slices, as shown in Figure 1. As the proton bombards the cooling water, the cooling water will be activated. In order to avoid unnecessary radioactive waste, the beam dump has been changed into a cone-shaped structure, as shown in Figure 2. Copper is comparatively a more reliable material for high-power device (20 kW), based on the consideration that the melting point and heat conductivity coefficient is higher than aluminum. Therefore the dump material is changed to copper. Meanwhile, in line with the overall layout of the project, the beam dump position needs to be changed to the isotope vault. For all the changes demanded for the beam dump system, recalculations have to be performed in terms of the source terms and shielding solutions so that it


conforms to the updated requirements.

Fig. 1 Original structure of the beam dump Fig. 2 New structure of the beam dump

The source terms of shielding calculation take into account the neutron field which is produced by

the bombardment of the 100 MeV/200 μA proton beam on a thick copper target. The result is shown in Fig. 3, suggesting that the neutron field is higher than that of the primal solution adopting aluminum as target material.

Fig. 3 Neutron spectrum of different target

The shielding calculation only takes into account the shielding requirement for the beam dump,

because the design power of the beam dump is higher than that of isotopes target. Meanwhile only the neutron field is considered in the calculation, given the fact that the neutron shielding is usually sufficient for the case of photon. Dose rate conversion standards accept the report ICRP 74 fluence dose conversion curve. The calculation considers the safety coefficient stipulated in the statute by a factor of 2, and the auxiliary value by a factor of 2 for dubious of the cross-section database and auxiliary the value by a factor of 2 for photon dose outside the shielding which is produced by neutron capture. The shielding structure takes into account a 2-2.6 m thick heavy concrete wall, 1 m thick concrete wall outside the isotopes vault, concrete floor and 3 m thick soil outside the building. The geometry used in calculation is shown in Figure 4 and Figure 5. The lead of 30 cm is used to shield the activation of beam dump, because the dose rate of activation will be high after several hours of operation. The local shielding structure is divided into two layers: lead shielding is applied to the inner 30 cm, and ordinary concrete shielding of 1.2 to 1.7 m is applied to the outer layer. The calculation also considers the 30 cm copper local shielding of the isotopes target.

There is no need to calculate the dose rate of the area outside the east and south wall, because the area is reserved for the control and it is not allowed to occupy when the accelerator is in operation. There


is another concrete wall of 3-4 m thick between the isotopes vault and the supervised area like the control room, and then the dose rate in supervised area is not calculated. The calculation tallies the average dose rate outside the west wall of isotopes vault and north wall of building from ground to 2 m level. The calculation results are shown in Table 1, Figure 6 and Figure 7 respectively. From Figure 6 and Figure 7 it can be seen that the dose rate of the west side of the main shield exceeds the limit. When the beam dump is operating, it is necessary to put a temporary concrete shielding of about 0.5 m thick on the ground (0 to 2 m level), or to set a barrier several meters from the shielding to attenuate the dose rate to the limit. The average dose rate outside the north wall of building above the ground meets the requirements of the limit. Relative to the original solution, lead is more effective than iron in the aspect of reducing the middle and high energy neutrons as inner layer shielding. And the cost for 1.2-1.7 m ordinary concrete is much lower than that of the 1m heavy concrete.

Fig. 4 Geometry structure at beam plane Fig. 5 Geometry structure at ground

Table 1 Dose rate outside the isotopes vault

Location Max dose rate /(μSv·h－1) Limit /(μSv·h－1) Level /m

1 m from north wall of building 0.064 0.5 0-2

1 m from west wall of building 0.57 0.5 0-2

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Development of Pre-amplifier Module for BF3 Counting Tube

HOU Shi-gang (Division of the BRIF Project)

According to the calculation of radiation protection, the neutron energy in the cyclotron vault ranges

from the thermal neutrons to 100 MeV when the machine is in operation. To monitor the neutron energy on such a wide domain requires special design of the neutron probe measurement device. Based on the results from the Monte Carlo simulation, the location of the maximum neutron flux of the neutron probe is 1.25×103 cm－2·s－1, and taking into account the sensitive volume of the BF3 pipe, the output of the probe pulse frequency is about 20 kHz.

As charge sensitive amplifier has good stability and noise characteristics, it has been decided that a charge-sensitive preamplifier circuit structure be adopted in the design. The charge sensitive amplifier is usually featured with a variety of structural forms, but the overall structure is similar to the present sensitive amplifier, which is mostly knot-shaped field effect transistor (JFET) and op amps work together to constitute the amplifier. This kind of circuit structure has a good and stable performance. After extensive research, a similar circuit structure is chosen, which utilizes the inverting input of op amp, and enhances the stability of the system. Charge sensitive pre-amplifier schematic is shown in Fig. 1.

Fig. 1 Schematic of low-noise pre-amplifier

The charge sensitive amplifier uses a 2N4416 JFET-as the first stage amplifier circuit, AD845JN

as a second stage amplification section feedback resistance of the ceramic capacitor of 1 pF to constitute a feedback amplification by the feedback capacitor and feedback resistor and 2N4416 AD845JN circuit. In order to enhance the exchange and amplification ability of the circuit, an adjustable current source has been designed as JFET active load, which can supply power to R11,


R13, R14 simultaneously. The SPICE simulation shows that the frequency is 121.06 kHz at the unity gain, where the phase

margin is approximately 90 degrees, way higher than the usual engineering margin requirements, indicating the whole system is sufficiently stable. The rms noise of the amplifier voltage is 374 μV and therefore the whole amplifier has a good low-noise characteristic.

By computational analysis and measuring the preamplifier, it can be concluded that this pre-amplifier has a number of advantages, including low noise, long-term work stability, low cost, fully meeting the BRIF project requirements.

Design and Experimental Study of the External H－ Ion Source for a 10 MeV Medical Cyclotron

JIA Xian-lu, ZHANG Tian-jue, QIN Jiu-chang, ZHENG Xia


A 10 MeV medical cyclotron has been designed by the BRIF Division at CIAE, for which the H－ beam is axially injected to the machine. To satisfy the requirement for the cyclotron with H－ ion source, a compact multicusp H－ ion source has been designed with a beam density of 3 mA/25 kV, which could not satisfy the demand of the 10 MeV cyclotron. So a new external H－ ion source has been designed with a diameter of 75 mm and a length of 127 mm. After initial experiment, the beam density of 5.2 mA has been obtained, meeting the requirement of the medical cyclotron.

1 Multicusp configuration

The plasmas produced by the collision between the H2 molecules (or H atom) and high energy electrons emitted by high temperature filament are configured by the multicusp configuration field. Based on the size of the source plasma chamber, ten rows of permanent magnets (Nd-Fe-B material) are placed in parallel outside of the plasma chamber, and every two groups of magnet blocks are placed alternately according to the magnet polarity. Every group of magnet block includes 5 layers with a length of 25 mm, and the cross section dimension for the block is 10 mm×15 mm. A multicusp field is created by upon 4 layers magnet block, and the virtual field is created by the last layer. To increase the field, a row of azimuth magnets are placed between every two rows of magnets with the section dimension of 8 mm×15 mm, the multicusp configuration is shown in Figure 1.

The three-dimensional multicusp field is calculated by ANSYS. The flux density for the magnet is Br=1.0 T, and the relative magnetic conductivity is 1.07. The influence from the air area has been taken into account during the FEM calculation of the magnetic field in which the air area length is selected to be 0.7 m. The radius magnetic field distribution in 0 degree angle is shown in Fig. 2. 2 Filter field

In the inner chamber of the ion source, the H－ multicusp ion source is divided into two chambers by a magnetic filter, a source chamber and an extraction chamber. In the source chamber, hot electrons (>45 eV) collide with H2 molecules to generate the vibrationally excited H2

* molecules, while in the extraction chamber. The major H－ ions are formed by cold electrons (<1 eV) colliding H2

* molecules. The virtual field is the narrow area of horizontal magnetic field, which can filter the fast electron.


Fig.1 Mulicusp configuration Fig. 2 Calculation result for mulicusp field

Due to the fact that a simple virtual filtering field (mode A) is either too thick in the axial direction

that the slow electrons are also filtered or too weak that it does not filter the fast electrons completely when the arc power is high. In the last layer of multicusp magnet close to the plasma electrode, the azimuth magnet is taken out. And the polarity of a pair of radial magnets is changed from “N” to “S”. And two magnets of the same polarity are put beside the changed magnet. And a virtual field about 170 Gs is obtained in the chamber center, the field distribution along the axial line is shown in Fig. 3.

3 The extracted electrode

The extraction electrode is the same with that of the 15 mA ion source. 4 Experimental study of the virtual filter

The ion source is a new one, for which the virtual filter needs to be optimized, and a beam density of 3 mA has been obtained before optimization. To optimize it, 5 iron flakes of the size 100 mm×13.5 mm×1 mm are used, and it is found that the center virtual field remains unchanged, while the 10 mm side virtual filter changes from 145 to 152 Gs. So, the virtual field is much more symmetrical, and beam density of 5.2 mA has been obtained after optimization.

Design of a Compact Pulsed Power Accelerator

ZOU Jian, ZENG Nai-gong, WANG Chuan, ZHENG Xia, ZHANG Tian-jue, JIANG Xing-dong (Division of the BRIF Project)

A 100 kA/60 ns compact pulsed power accelerator was designed to study the influence to the

X-pinch by the load. It is composed of a Marx generator, a combined pulse forming (PFL), a gas-filled V/N field distortion switch, a transfer line, and a copper-sulphate resistive load for testing. A 1.25 Ω

Fig. 3 Calculation result for the virtual filter


waterline with a dimension of 2 m×1 m×1.5 m is designed, which can be moved anywhere by the chain wheel for X-pinch experiment. Figure 1 is the view of the pulsed power accelerator.

Fig. 1 View of pulsed power accelerator

Figure 2 shows the output of voltage and current. When Marx generator is charged to 0.36 MV, the

voltage rise time is 22 ns, the pulsed width is 60 ns, output current is 117 kA.

Fig. 2 Output of voltage and current

The results show that the output of the pulsed power accelerator is 117 kA/136 kV/60 ns, and the rise

time is no more than 30 ns. The Marx generator storage energy is 1.62 kJ. The device is suitable for X-pinch experiments.

Design of Spiral Inflector and Central Region for a Medical Cyclotron

YAO Hong-juan, SONG Guo-fang, YANG Jian-jun, ZHANG Tian-jue, LIU Geng-shou (Division of the BRIF Project)

CYCIAE-14 is a medical cyclotron designed to accelerate H－ ions and extract protons, and it adopts

the external ion source and axial injection line. The spiral inflector and the central region are the important


parts of the machine. The inflector is used to deflect axial injection beam to the horizontal plane, and then the beam will be accelerated during the central region by the RF Dee voltage. After the magnetic field mapping and shimming had been finished, the spiral inflector and the central region were designed again for CYCIAE-14. Using the measured magnetic field data as input, the final design has been finished, and the mechanism design, numerical control machining and installation of the inflector and the central region have been finished as well.

The operational principle of spiral inflector is that electric force remains perpendicular to the central trajectory. Because of the magnetic field in central region, the trajectory through inflector will become a spiral line, and the shape of electrodes is also spiral. The inflector of CYCIAE-14 is designed to k´≠0, so the machining must be done by using numerical control machine tool with the number of its axles no less than 5. The primary parameters of inflector of CRM are listed in Table 1.

Table 1 Primary parameters of inflector for CYCIAE-14

Parameters Value Parameters Value

Injection energy 28 keV Width of electrodes 16 mm

Electric radius A 29 mm Electric field 1.811 kV/mm

Tilt k´ －0.78 Rotation at entrance 201º

Gap of electrodes 8 mm

The central region is the region where the particles run for the first several turns. The design is very

complex, and many aspects need to be considered, including magnetic map, electric map, initial point selection and so on. The RF frequency of CYCIAE-14 is 72.859 8 MHz, isochronous field is 11.960 8 kGs, and Dee voltage is 40 kV. There are four accelerated gaps. The design of electrodes in central region is limited by the structure of inflector and shimming bars of the main magnet. AUTOCAD is used to design the electrodes, with the origin at the center of the cyclotron. Pre_R3D is used for processing the drawings of electrodes of the central region, and the output file of Pre_R3D is used as the input file of RELAX3D for the electric field calculations. The mesh size in small field is 0.03 cm×0.03 cm×0.03 cm, and in large field is 0.05 cm×0.05 cm×0.1 cm. The beam centering results are shown in Fig. 1 for simulated field and measured field. The central rays of reference particle for 40° phase width with the measured field are shown in Fig. 2.

Fig. 1 Beam centering results

for simulated field and measured field

Fig. 2 Central rays of reference particle

for 40° phase width


The electrodes of central region are very complex and irregular, and the surface finish quality, dimension and position accuracy are of demanding requirement. In order to achieve that, the machining must be done using numerical control tools. The electrodes of central region were finished by using 3-axle machine tools. With the limitation of parallelism less than 0.01 mm between the two flanges, the flat surfaces of flanges were finished using abrasive machining, assuring the precision of single part and position accuracy during installation.

Now the design, machining and the installation of the spiral inflector and central region for the CYCIAE-14 cyclotron had been finished, and the picture of inflector and central region after installation is shown in Fig. 3.

Design of Main Elements of the Axial Injection Line for CYCIAE-100

YAO Hong-juan, ZHENG Xia (Division of the BRIF Project)

The 100 MeV high intensity cyclotron CYCIAE-100 uses an external ion source which provides H－

beam with an energy up to 40 keV and a maximum current 10 mA. The axial injection system is employed to transport H－

beam from the ion source to the cyclotron with high transmission and good beam quality, which is composed of beam diagnostic elements, focusing elements, beam correcting elements, bunching elements and so on. The design of the axial injection line of CYCIAE-100 previously adopted an SQQ structure, and now based on the experience on the existing CRM the design has been modified to S3QS structure, the layout of which is shown in Fig. 1. The beam transport flow can be expressed to d1-S1-d2-Q1-dq-Q2-dq-Q3-d3-S2-d4-inf-CYC (S1 and S2 are solenoids; Q1, Q2 and Q3 are quadrupoles; d1, d2, d3, d4 and dq are drift; inf is inflector and CYC suggests the matching point between the exit of inflector and central region). Three quadrupoles are located in the hole of the main magnet bottom yoke; S2 is located at the hole of the central plug. The design results of main elements of the axial injection line are given below. 1 Solenoid

Inside the solenoids are the coils on a stainless steel pipe and the external part is the yoke by DT4 or 10# steel. The magnetic field distribution is along the beam axes and the radial component increases with the increment of the distance off the axes. The designs of the two solenoids have been finished using the

Fig. 3 Picture of inflector and central region after installation finished

Fig. 1 Axial injection layout of CYCIAE-100


program of POISSON/PC based on the results of the beam optics matching. The effective length is 350 mm, and the aperture radius is 40 mm. The coil is wound by TU2 wire with a dimension of 6 mm×6 mm- 3.5 mm×3.5 mm. And there are 4 layers and 34 turns per layer. Two layers have a water route, so there are two water routes in total. The current is 265 A and the power is 2.915 kW. The magnetic field distribution is shown in Fig. 2 and the maximum field is 1 800 Gs.

Fig. 2 Magnetic field distribution of the solenoid

2 Quadrupole

The design of three quadrupoles has been finished using the program of POISSON/PC based on the results of the beam optics matching. The aperture radius is 25 mm, and the effective lengths are 100 mm, 120 mm and 100 mm respectively. For the convenience of design and machining, the hyperbolic shape of the pole is replaced by arc shape. The section of the quadrupole is shown in Fig. 3, the radius of inscribed circle is 25 mm, and the radius of the pole is 30 mm. The coils are wound by the TU2 with a dimension of φ3 mm-φ2 mm. Four coils are connected in series. The current is 43 A and the voltage is 5 V, the temperature rising is 16 . The well field region is 0-20 mm with a uniformity of 0.005 6.

Fig. 3 Section and magnetic field map of the quadrupole

3 x-y steering

There are two x-y steering magnets on the axial injection of the CYCIAE-100 cyclotron; one small circle x-y steering magnet is placed around the ground electrode of the ion source, which is used for correcting the center of beam from the ion source. There are four coils, and Figure 4 shows two coils of the x-y steering. The other two coils are also placed 180° symmetrically. These four coils generate the magnetic field for correcting beam in 360°. The other x-y steering magnet is located on the axial injection line shown in Fig. 1, which is used to adjust the center of injection beam. The coils are wound by enamel wire with φ1.8 mm. The width of yoke is 142 mm, the thickness is 10 mm, and the height is 56 mm.

At present all the elements, vacuum chamber, flanges and support frames of the axial injection line for the CYCIAE-100 cyclotron are being processed.


Fig. 4 Magnetic field map of the x-y steerings

Peak Detector Circuit for DCCT Improvement

WEN Li-peng1, GUAN Feng-ping1, Antonino Amato2 (1. Division of the BRIF Project, CIAE；2. INFN-LNS, Italy)

The DCCT（DC Current Transformer）system can be used to measure the DC component or average

current intensity (a very important parameter for the cyclotron and beam line) without disturbing the beam for long period. 1 Working principle of DCCT

The DC current transformer (DCCT) is a kind of zero magnetic flux transformer. The detector consists of a pair of magnetic rings with the same size and same magnetic parameters. There are two kinds of windings on the magnetic rings, one is the exciting winding, and the other is the feedback winding. The exciting winding is on two rings with the same number of turns in series but in the opposite direction. Low frequency square wave gets the magnetic rings into saturation. Verr is the signal from the middle of the exciting winding.

Charged particles passing through the detector can be equivalent to a current. When there are no charged particles getting through, the two magnetic rings are excited in opposite directions, the two magnetic rings get into saturation at the same time, the detector is in zero magnetic flux state, no second harmonic in signal Verr. If charged particles are getting through, according to the right hand rule, one magnetic ring gets into saturation first, and the other later, so the balance of the two magnetic rings is destroyed, and there will be second harmonic in Verr. This second harmonic is proportional to the average intensity of the beam.

Fig. 1 Working principle of DCCT


2 Peak detector circuit In the previous design, the sampling signal is used to sample a small portion of the Verr signal, and it is

equal to average the second harmonic peak over this small time portion. The sampling signal is obtained from a square wave around 1 kHz. The most critical parameter about the system accuracy is the synchronization between the Verr signal and the sampling signal. The peak detector circuit is sensitive to the peak value of the second harmonic, and is not sensitive to the peak position, which could improve the SNR significantly.

The slope on the output signal from the peak detector is determined by the value of the CH and the bias current of the amplifier. The detector of the DCCT works around 100 Hz, which is not a high frequency, so polyester capacitor with low leakage current and amplifier with small bias current should be chosen. AD712 is chosen for small bias current, with sufficient accuracy and speed. 1N4148 is chosen, but with a glass package, this diode is sensitive to light. This photoelectric effect will cause some error to the measurement. The 50 MΩ metal film resistor is chosen to prevent large slope during charging the CH.

Fig. 2 Schematics of positive peak detector

CH is sensitive to leakage current, so a guard is added to this circuit. The guard should be connected to a

low impedance point at the same signal input potential. In this configuration, the pin 6 (-IN) is chosen. This circuit is already tested. The result shows a better stability than the previous design and will be used

in the improvement of DCCT in the future.

Manufacture of the RF Cavity for CYCIAE-100

JI Bin, XING Jian-sheng, YIN Zhi-guo, ZHANG Tian-jue, LIN Jun, LI Peng-zhan (Division of the BRIF Project)

The RF cavity is a key component for the RF system in CYCIAE-100, the low power consumption

and the high stability must be considered in the design to meet the physical needs. It is required that the voltage at the central region is 60 kV and at the same time 120 kV at the large radius area. The structure with two stems for the special inner conductor has been adopted to address these problems successfully. But the difficulty in the manufacture comes with the special inner conductor.

The height of the cavity is about 1.3 meters, and the distance from the head to the radius of the cavity is about 2 meters. The components of cavity are made by the oxygen-free copper material. The large oxygen-free copper cavity has never been manufactured in China before, so lots of problems should be


solved by ourselves. One of the most critical problems concerns the welding. As a key component of the cavity, the cooling system includes the outer conductor, the Dee plate and the stems. For the cooling of the outer conductor, we use the method of silver brazing copper pipes outside the outer conductor in the atmosphere, between the copper pipes and the cavity fully welded at the same time, the thermal deformation of the cavity is acceptable. For the cooling of the Dee plate, the copper pipes are buried in the plate, the surface oxidation and the large deformation will occur if the welding is performed in the atmosphere. The vacuum silver welding has proved to be successful after many experiments. For the cooling of the stems, the core with cooling water spiral groove is used to solve the thermal problem by the RF power loss. The main difficulty deals with the welding between the inner core and the stem. The quality of the welding in the atmosphere is not ensured except the surface oxidation, through several experiments, and the problem is ultimately resolved by the method of electron beam welding to process requirements.

The fabrication of the two sets of RF cavities for CYCIAE-100 has been finished, and the size of its structure achieves the requirements of the drawings. The unloaded Q of the two cavities has been measured after it was pre-assembled in the factory, one is 9 434, and the other is 9 691. The results are very close to the design requirements. The volume of the cavity for CYCIAE-100 is becoming the biggest ever manufactured in China. A picture of the cavity is shown in Fig. 1.

Mechanical Design of the Injection Beam Line of Small Medical Cyclotron

SONG Guo-fang, YANG Jian-jun, YAO Hong-juan (Division of the BRIF Project)

The injection beam line is a key device for beam transport of the small medical cyclotron, giving

direct influence to the beam quality of the cyclotron. According to the medical needs of the cyclotron, the overall length of the injection beam line is as short as possible, the injecting beam must match with inflector and central region, and the injection beam line must be compatible with the main magnet and RF system. The structure design has been finished based on the results of simulation.

The overall structure of the injection beam line for small medical cyclotron is shown in Figure 1. Its components include the ion source vacuum chamber, Faraday cup, the buncher, quadrupole magnet etc. In order to minimize the length of the injection beam line, the x-y steering magnet is on the lower part of the ion source, the buncher on the middle of the injection line, and quadrupole magnet on the end of the injection line. The x-y steering magnet is used for adjusting the transverse position of the beam line. The buncher can focus the beam line in vertical direction. The quadrupole magnet is designed for transverse focusing of the beam line. In order to ensure high intensity beam and high injection efficiency, and to achieve the non-symmetric controlling of x-y direction for beam line, a dual quadrupole magnet is put into use. The vacuum requirement of the injection line is better than 5×10－6 mbar. There are 3 vacuum pumps on the side of the ion source vacuum chamber, two for the ion source, and one used to meet the

Fig. 1 RF cavity for CYCIAE-100


requirement of injection line pipes. Inside the ion source vacuum chamber, partitions and small hole for limiting the beam are used, making the ion source vacuum chamber into two parts so that the vacuum environment of the ion source can be ensured.

Fig. 1 Overall structure of the injection beam line

The machining of the injection beam line has been finished. And the assembly, adjustment and the

vacuum leak detection are completed. The result shows that the vacuum of the injection beam line meets the design requirements.

Mechanical Design of the Inflector and Central Region of Small Medical Cyclotron

SONG Guo-fang, YAO Hong-juan, YANG Jian-jun, YIN Zhi-guo


The inflector and central region are key devices of the small medical cyclotron, whose structure will give influence to the performance of the cyclotron. According to the needs of the small medical cyclotron, the inflecting voltage of the inflector is ±10 kV. The structure design has been finished based on the results of simulation.

The mechanical structure of the central region is shown in Figure 1, which is mainly composed by the Dee head, the central region flanges, cross bridge and its cavity. The two Dee heads are designed as an integral structure, which are fixed to the Dees with bolts. The upper and lower central region flanges are fixed and the fingerstocks are used on the connecting surface of other parts which effectively improves the electric conductivity. All the optimizations meet the electric conductivity requirements of central region and reduce the sparking phenomenon due to poor contact between the parts. The inflector is tilting in structure (k´≠0), as shown in Figure 2. The distance between the deflection electrode plates is non-uniform distribution along the particle track direction and deflection electrode plate spacing decreases gradually.


Fig. 1 Overall structure of the central region Fig. 2 Structure of the inflector

The machining of the inflector and central region has been finished. And a high power test has been carried out after the assembly with the RF cavity. The results show that the structure of the inflector and central region is reasonable and well-matched with RF system.

Measurement and Simulation of Beam Centering on CYCIAE-10

AN Shi-zhong, GUAN Feng-ping, YAO Hong-juan (Division of the BRIF Project)

The beam centering is very important for the compact cyclotron, especially for the cyclotrons with

the axial injection. It is critical that the cyclotron has a good beam centering to increase the beam current and reduce the beam loss. In the accelerating process, the beam size in the axial direction will be affected directly by the beam centering due to the transverse coupling. In general, at lease 2 radial probes are needed for the direct beam centering measurement. Only one probe is installed in CYCIAE-10 at present. The special radial probe with five fingers structure is designed and the beam off-center can be measured along the radial direction. The result of the beam centering in CYCIAE-10 is from the direct measurement with one radial probe together with the formula calculation. The result from the measurement is used to the beam centering simulation with the code COMA afterwards. The results are agreed very well. So the measurement result is credible.

Figure 1 shows the structure of the radial probe with five fingers. The head of the probe is combined with five separate probes. Some parts at the foreside of these probes are covered with another probe and they are insulated from each other. The radial probe in CYCIAE-10 is inserted along the radial direction at the center of the magnetic pole from the mid plane. The measurement result with the radial probe is shown in Fig. 2 and the results of calculation and simulation from the code COMA are shown in Fig. 3. The results are agreed very well between the calculation and simulation. The beam centering of CYCIAE-10 is less than 6 mm from the measurement and simulation.


Fig. 1 Structure of radial probe in CYCIAE-10

Fig. 2 Measurement results with the radial probe

Fig. 3 Beam centering results of CYCIAE-10 between measurement and simulation

Simulation on the Pulsed Beam Transport for Injection Line of CYCIAE-10

AN Shi-zhong, ZHANG Tian-jue (Division of the BRIF Project)

1 Introduction

The development of a 40 keV, 18 mA multi-cusp H－ ion source and beam pulsing system have been completed successfully at CIAE. The pulsed H－ beam with a repetition rate of 4.4 MHz and a pulse length of 9.6 ns has been obtained. In order to inject and accelerate the pulsed beam in CYCIAE-10, the DC beam injection line will be modified. The SQQ focusing structure is adopted for the DC beam injection line, as shown in Figure 1. The old H－ ion source will be replaced by the 18 mA multi-cusp ion source and an einzel focusing lens will be used at the exit of the ion source. The chopper system will be put at the beam waist poison which is focused by the einzel lens. The sine wave form with the frequency of 2.2 Mz will be used for the chopper. The ESQQ focusing structure will be adopted in the pulsed injection line for CYCIAE-10, and the SQQ focusing part in the DC injection will remain unchanged.

Fig. 1 DC beam injection line of CYCIAE-10


2 The simulation on the pulsed beam transport for the injection line of CYCIAE-10 For the injection condition of CYCIAE-10, the accepted beam parameters before the inflector are

±120 mrad/±4 mm, αx =4.86 in x-direction and ±40 mrad/±8 mm, αy=－1.98 in y-direction. The distributions for the chopped beam after the round slit can be obtained due to the simulation for the beam chopping process. Radial symmetric Gaussion distributions with RMS emittance of 6.22 πmm·mrad (50 πmm·mrad in total) are assumed as input distributions. For chopped beam, RMS emittance in y-direction is increased up to 25.62 πmm·mrad after chopper, but decreased to 20.19 πmm·mrad after round slit1, finally decreased to 18.5 πmm·mrad by solenoid. In x-direction, RMS emittance is conserved up entrance to the solenoid. Single particle tracking results are shown in Figure 2 & 3 for the chopped and unchopped beams from round slit to the cyclotron inflector, without changing the focusing strength in solenoid and quadrupole doublet. Total beam envelopes are shown for 8×RMS emittance, about 50 πmm·mrad for the unchopped beam, but changing for the chopped pulse due to transverse coupling of both phase space planes if the parameters of the focusing elements are the same for both chopped beam and DC beam in the calculation. The RMS emittance of the chopped beam in y-direction is decreased to 18.5 πmm·mrad in y-direction and increased by almost a factor 2 in x-direction due to the coupling caused by solenoid. The chopped beam sizes both in x-direction and in y-direction at the entrance of the inflector will be increased to 11 mm/10 mm and the total beam envelope can be controlled under 5 cm, even if the parameters of the focusing elements are the same. The chopped beam sizes both in x-direction and in y-direction at the entrance of the inflector can be controlled under 8 mm/16 mm by adjusting the focusing strength of the last 3 elements and it can be accepted by the inflector and be accelerated.

Fig. 2 Total beam envelopes from slit to inflector for chopped and DC beam (with the same focusing parameters)

Fig. 3 Phase space plots before the inflector for chopped and DC beam (with the same focusing parameters)


Insulation Consideration of the Cryo-vacuum System for CYCIAE-100

ZHANG Su-ping, PAN Gao-feng, XING Jian-sheng, ZHANG Tian-jue, LI Zhen-guo (Division of the BRIF Project)

A set of tailored cryopanel cooled by a stirling cryogenerator is being developed for the vacuum

system of CYCIAE-100. A 25m long transfer line is used to transport cold powder generated by stirling cryogenerator to the tailored cryopanel. Insulation is a key parameter for the transfer line for sake of reducing heat loss and improving transport efficiency.

Two insulation types are usually used in cryogenics, one is non vacuum insulation type, and the other is vacuum insulation type. High vacuum insulation, vacuum powder insulation and vacuum multilayer insulation are classified as vacuum insulation. The insulation types are listed in Table 1.

Table 1 Insulation type used in cryogenics

Type Parameters

Non vacuum insulation Foam glass, cork, PVC, polystyrene

High vacuum insulation 10－2-10－4 Pa

High vacuum powder insulation 10－2 Pa, and silica gel

Vacuum multilayer insulation 10－2 Pa and parallel shield

Multi low emissivity shield which is parallel to the cold surface is usually used to reduce radiation

heat, and low conductance spacer is placed between shields. Table 2 shows parameters of vacuum multilayer insulation in common use. And the relationship between average heat conductance and the density of insulation layer is shown in Fig. 1.

Table 2 Parameters of vacuum multilayer insulation material

Spacer Multilayer material Thickness /

cm Layer density /

cm－1 Vacuum /

torr Average heat conductance /

(kcal·m－1·h－1·－1)

0.15 mm fiberglass 0.02 mm molybdenum foil 3.0 16.7 1.7×10－6 2.10

0.05 mm fiberglass 0.01 mm terylene film

with molybdenum 2.54 26 1.0×10－1 1.42

0.025 mm fiberglass 0.003-0.004 mm aluminium foil

2.85 48.6 1.4×10－4 8.35×10－4

0.05-0.125 mm asbestos fiber 0.01 mm terylene film

with molybdenum 2.52 18.7 3.4×10－4 3.52

0.05 mm foliage fiber 0.01 mm terylene film

with molybdenum 2.55 37.0 1.7×10－1 1.59

0.01 mm polyurethanefilm 0.01 mm terylene film

with molybdenum 2.76 49.0 1.9×10－5 1.53

1 200 S thickness of nylon nets 0.01 mm terylene film

with molybdenum 2.55 34.0 3.0×10－5 1.13

0.004 5 mm capacitance paper 0.01 mm terylene film

with molybdenum 2.80 57.0 1.0×10－4 1.00

0.004 5 mm capacitance paper 1.67 72 － 5.00 0.05 mm molybdenum powder and 30% fiberglass 2.03 55.6 1.0×10－4 2.96

The average conductance for insulation layers is at minimum value when insulation layer density is


30 layers/cm as we can see in Fig. 1, and it will be at smallest value when 0.025 mm fibreglass and 0.003-0.004 mm aluminium foil are chosen separately as the spacer and the insulation shield. As a whole, 0.025 mm fibreglass and 0.003-0.004 mm aluminium foil are chosen separately as the spacer and the insulation shield with suitable layer density 30 layers/cm in the vacuum multilayer insulation transfer line for CYCIAE-100.

Fig. 1 Relation between average heat conductance and layer density

Concept Design of Multipacting Measurement Circuit With Nano-second Resolution

WANG Chuan, YIN Zhi-guo, ZHANG Tian-jue


Multipacting is the phenomena that an electron exerts impact on one surface or between several surfaces of the RF or microwave components under the influence of periodical electric field, and emits more than one electron, if the secondary emission coefficient of the surface material w. r. t the energy of the incident electron is larger than one. Under certain structures, frequencies and voltages, which meet the resonate condition, multipacting will cause multipactor discharge. This type of discharge usually occurs in the voltage range less than tens of kilovolts and in the frequency range from MHz to tens of GHz, and can be observed in various radio frequency (RF) or microwave components, like the RF system of particle accelerators, the RF/microwave payloads of spacecrafts or satellites. The measurement of the multipacting current with nano-second-time resolution, on the one hand, can provide the experimental data for benchmarking the newly developed multipacting theory and the particle tracking codes which can be used to optimize the design to obtain the multipacting free RF/microwave components, and on the other hand, can be used as a protection method from breakdown near the dielectric window.

Based on the above considerations, we designed a time resolved measurement circuit with nano-second resolution, which can be used to measure the multipacting current near the dielectric RF window of CYCIAE-100 cyclotron as well as the RF window of the PET cyclotrons. The sketch map of the circuit is shown in Fig. 1.

In 0, the positive bias voltage (B1) is used to gather the multipacting current (Is1). The low inductance resistor (R2) with Mega ohm resistance is used to convert the small current signal to voltage signal. The capacitor (C2) is used to isolate the measured signal from the DC voltage. The resistor (R3) is the input resistor of the oscilloscope (TPv1). C1 is the ground capacitance of the electron probe and R1 is used as the DC voltage divider. The electron probe consists of a standard RF pickup with vacuum feed


through and a copper shied with small hole matrix with tens of micron in diameter for each hole. All of the above components should be mounted within a metal box to suppress the RF field, background noise and maintain a very small inductance.

Fig. 1 Multipacting measurement circuit with nano-second resolution

We have performed a circuit simulation on the measurement circuit with spice code. The input of the simulation is the impact rate on either surface of a parallel plate system which is obtained from a multipacting simulation on parallel plates by using OPAL code, and is used as a current source of the measurement circuit. The simulated output on oscilloscope (TPv1) is shown in Fig. 2, which indicates that the designed multipacting measurement circuit has nano-second resolution.

Fig. 2 Output on oscilloscope by circuit simulation

Mechanical Improvements on the Main Magnet for CYCIAE-14

CUI Tao, LV Yin-long (Division of the BRIF Project)

The main magnet and main vacuum system of CYCIAE-14 have been installed and commissioned

successfully. On this basis, relevant engineering experiences have been summarized, and the improvements have been made to optimize the current mechanical design and construction, which would be instrumental for the future work.

1) The uniformity of magnet field is vital for the medical cyclotron. The key techniques that ensure uniformity are the same material and installation accuracy. At present, the mapping of magnet field has


been completed. After analyzing the result, it has been found that the uniformity at the central region is more sensitive than other areas. Given the fact that the shim bar will be installed and dissembled frequently, it is difficult to ensure the shim bar be installed exactly the same every time. Meanwhile it is difficult to machine the hole on the shim bar. After weighing the advantages and disadvantages, we conclude that it is necessary to modify the structure of shim bar and central plug, in order to improve precision and technics. We can integrate the central plug with the head of shim bar.

2) The installation of relevant equipments places high requirement on the function of the main vacuum chamber. The aluminium tank has a thin shell. If we adopt welding method, the disadvantages are bad distortion, more machining and more linking at seams. For these difficult technics, we can resort to the casting technics, which has been developed very well recently. If we adopt the casting technics for aluminium tank, there are quite a few advantages of adopting this method. For one thing, the distortion of the vacuum tank induced by the welding can be reduced, and next, the leaking at he seams can be avoided. In the meantime, the shape of vacuum tank is more complicated, which is featured with sound seams. For the casting tank the key technics are to improve casting quality and meet the requirement of vacuum.

3) We use the bolts with deflatable hole in the design, which provides favorable condition for the vacuum of cyclotron.

4) A separate design scheme is adopted for the main magnet, for which the clearance is 5 mm between the poles and vacuum tank. When the top half poles are lifted for the first time, the poles may bump vacuum tank. Therefore, an oriented device is employed to solve the problem.

Some improvements concerning CYCIAE-14 have been presented here. It will be instrumental for the future optimization.


China Reprocessing and Radiochemistry Laboratory

Progress of CRARL in 2011

CRARL Engineering Department In 2011, the CRARL project mainly in commissioning phase, engineering staff in the leaders of

support, in functional departments and the brother of unit under the assistance, under the leadership of general manager, by joint efforts to complete the main process equipment, water supply and drainage, physical protection, electric, heating, ventilation, radiation protection and so on various professional system commissioning work; Civil engineering, installation unit settlement third party audits, the annual construction goal. Now the main working summary is as follows. 1 The construction site 1.1 The civil construction

01 item: A complete the interior and exterior decoration etc all civil construction work; 00 item: Already in April 2011 to complete the outdoor road and afforest construction (project except

on the west). 1.2 Installation work

By now, complete all the professional items installation work, now is working with debugging work make corrections. 2 Purchasing items

1) By November 2011, complete all items procurement and the arrival of the engineering work. 2) Is in the process of debugging and procurement of items required commissioning in the relevant

items repair reconstruction work. 3) Items related data collection.

3 Commissioning work

1) In April, 2011, the national defense science and industry bureau military nuclear facilities nuclear safety technical evaluation monitoring center inspectors to spot debugging start conditions witness point check. Inspectors think: the debugging ready to meet the debugging startup conditions, grant project startup and commissioning work, mark commissioning work full official start.

2) Has now complete the main process equipment, water supply and drainage, physical protection, electric, heating, ventilation, instrumentation, radiation protection and so on various professional system commissioning; Testing found that the problem and debugging the rectification of the preparation of the report. 4 Quality assurance and quality control 4.1 “The defense science, technology and industry military nuclear facilities safety supervision and management stipulation” the execution

In 2011, engineering and construction units concerned the strict implementation of the national defense science and technology industry military nuclear facilities safety supervision and management

IMPORTANT NUCLEAR SCIENCE ENGINEERING·China Reprocessing and Radiochemistry Laboratory 53

regulation, national defense science and technology industry military nuclear facilities quality assurance provisions and other nuclear safety and regulatory requirements, in accordance with their respective quality assurance program management and construction, the whole year did not appear safety accidents and quality event. The engineering department strict implementation of quality assurance program related procedure, strengthen supervision and control during work, did not appear larger throughout the year and major non-conformances, project quality to be in control. 4.2 Military nuclear facilities of quality assurance system establishment and operation

In 2011, the engineering department of “testing site safety, fire control, security, emergency management regulation” and “system cold tone over complete management procedures”, “the interim acceptance interface management program”, “the debugging personnel and related personnel training and authorized”, “the testing license system”, “operation system and equipment during commissioning of the label of management procedure liters”.

Above the quality assurance files after compiling and up), further detailed the related management requirements and improve operational. At present the publication of the program can meet the engineering project management of use. 4.3 The supplier selection and evaluation

In 2011, four to choose the supplier after evaluation was listed in the “CRARL engineering the qualified supplier name list”, at present CRARL engineering department qualified supplier has 150. In addition, quality department participate the construction unit to choose the supplier assessment and evaluation of the construction unit shall supervise and witness, the construction units to participate in supplier evaluation (Wen careful) three companies. 4.4 Quality supervision

This year for debugging start work, April quality department organized the two surveillance activities, key check debugging site safety, security, fire control, cleanliness, and send it to the relevant units, strengthen the management requirements, rectification, went through the relevant units of hard work, the work has started testing conditions. 4.5 In site construction and equipment manufacturing validation

Organization of the quality of construction supervision department unit plan and supervise and inspect the implementation.

For construction units and equipment processing manufacturing unit plan click on quality and checked, witness and sign the release, engineering construction and equipment processing be in control. By now, the total shut down the quality plan 163 copies. 5 Engineering organization and management

According to the actual situation of the project progress, preparation, promulgated the engineering department 2011 annual work plan, according to plan a meeting system, monthly check engineering departments and check the quarterly construction units concerned work not complete schedule, the reason and take measures to make up for, coordinate to solve the problems, according to the annual work plan for adjustment; make and implement engineering’s 2011 investment plan; prepare and issue the completion acceptance work plan.

According to the actual work progress, and considering the overall construction project progress, CRARL engineering on 2012 engineering construction puts forward definite goal node. In June 2012 completion filing work, puts forward the archives for special acceptance. In October 2012 the final accounts of the completion of the report.


Radioactive Waste Renovating Projects

Progress on Radioactive Waste Treatment Facilities Construction

ZHANG Cun-ping, WU Jie, LI Mei-shan (Radioactive Waste Treatment Facilities Construction Engineering Department)

In 2011, five projects were undertaken by radioactive waste projects management department, which

are “Cold Commissioning of the Pilot Project on Radioactive Waste Retrieval and Conditioning (abbreviation ‘Pilot Project’)”, “Radioactive Ventilation Project Construction (abbreviation ‘Ventilation Project’)”, “Radioactive Liquid Temporary Storage Facilities Construction”, “Intermediate Level Liquid Waste Transportation system Construction (abbreviation ‘ILLW Project’)” and “Low Level Liquid Waste Transportation Pipeline Renovating Project (abbreviation ‘LLLW Project’)”.

All projects aims have been accomplished in time under Project Management Department’s well organization and regular management. The rate of utilization of every project funds has reached 100%.

The Pilot Project has completed reformation design and construction to the problems occurred during cold testing. The Ventilation Project has completed cold testing and operation permitting application. The No.163 has completed civil and installation of the main body construction and auxiliary project construction. The ILLW Project has completed volume measuring building, pipeline construction and Four Parties Acceptance. The LLLW Project has completed five volume measuring building’s structure construction and 2 000 m pipeline.

The department strengthened management of project quality and production safety. Last year two Quality Problems were well closed. Every projects quality is under controlled and no safety accident occurred.

The Project Management Department actively carried The Project on Very Low Level Contaminated soil Clearing, Transportation and Disposal forward. The proposal of the project has been assessed by the authority. The program of budget adjustment for the Ventilation Project has been compiled and reported the authority, which has paved the way for the next step work.

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 57

Nuclear Physics

Tensor Effect on Proton Bubble Structure of 46Ar

WANG Yan-zhao, GU Jian-zhong, ZHANG Xi-zhen

(Department of Nuclear Physics)

We have calculated the proton density distribution of 46Ar for different pairing interactions with

the Skyrme interactions SLy5 and SLy5+Tw (Tw is the tensor force, which was obtained by the G-matrix calculations and added perturbatively into the SLy5 interaction) in the framework of Hartree-Fock-Bogoliubov (HFB) approach by taking into account the tensor force. The calculated results are plotted in Fig. 1. As can be seen from Fig. 1, the proton density distribution of 46Ar with SLy5 interaction is not dependent on the paring interaction (t0′denotes the pairing strength). However, the SLy5+Tw interaction can make the density in the center of the nucleus decrease for different pairing interactions. This is because the SLy5+Tw interaction can lead to the inversion between the 2s1/2 and 1d3/2 proton single-particle states. As a result, the occupation probability of the 2s1/2 state drops sharply. In addition, we can see that the depletion in the nuclear interior becomes weaker and weaker with the enhancing of the pairing interactions. The occupation probability of 2s1/2 orbit increases with the enhancing of the pairing interactions, weakening the bubble structure of 46Ar. Thus it is not difficult to conclude that the bubble formation of 46Ar originates from the competition between the tensor and pairing effects.

Fig. 1 Proton density distributions of 46Ar for SLy5 and

SLy5+Tw interactions corresponding different t0′ values


Shell Model Study on the Proton Pigmy Dipole Resonances in 17, 18Ne

MA Hai-liang, DONG Bao-guo, YAN Yu-liang, ZHANG Xi-zheng (Department of Nuclear Physics)

The proton pygmy dipole resonances (PDRs) in proton rich nuclei 17, 18Ne have been investigated in

the framework of interacting shell model. The shell model with the self-consistent Skyrme-Hartree-Fock wave functions has well reproduced the experimental data of ground state properties. The proton PDRs in neighboring 17, 18Ne has been predicted. However, the detailed study involving transition densities and transition matrix components shows that the PDR in 17Ne is highly collective and due to the oscillation of the valence protons against the interior core, while in 18Ne the dipole resonance in the PDR region is noncollective and more likely the configuration splitting of the GDR.

Microscopic Effective Charges and B(E2) Values of Terminating States in Mirror Nuclei 51Mn and 51Fe

MA Hai-liang, DONG Bao-guo, YAN Yu-liang


The effective charges are commonly used in the restricted shell model calculations. In the pf shell, an agreement on the isoscalar part is reached to be around 2.0e, however the isovector part is still under the intense debate. Since wave function of terminating states is more pure, the effective charges can be extracted from the B(E2) values between these states experimentally. And by comparing the B(E2) values of mirror nuclei, the isovector part can be studied. To theoretically investigate isovector part, the microscopic effective charges in mirror nuclei 51Mn and 51Fe are calculated with the particle-vibration coupling model based on the self-consistent Skyrme-Hartree-Fock and continuum random-phase- approximation approach. The isovector parts are predicted to be around 0.15. The proton effective charges are around 1.25e, which is less than the empirical value ep

eff=1.5e. The microscopic effective charges in neutron rich 51Mn are about 10% less than its proton rich mirror. These effective charges are combined with the shell model to calculate the reduced electric quadrupole transition probability B(E2) values in 51Mn and 51Fe. It turns out that the microscopic effective charges have well reproduced the B(E2) values and its ratio in the terminating states.

Fusion Reactions of 16O+76Ge and 18O+74Ge Near Coulomb Barrier* JIA Hui-ming, LIN Cheng-jian, ZHANG Huan-qiao, YANG Feng, XU Xin-xing, YANG Lei, LIU Zu-hua


The fusion excitation functions of 16O+76Ge and 18O+74Ge at near-barrier region are measured, to


research the positive Q－2n effect on the fusion reaction. The properties of the lower excited states are similar for the two targets. For neutron transfer channels, Q－2n for 18O+74Ge is 3.75 MeV, but for 16O+76Ge no positive Qxn transfer channels exist. So an additional fusion enhancement is expected for 18O+74Ge compared with 16O+76Ge empirically.

The fusion excitation functions of 16O+76Ge and 18O+74Ge near-Coulomb barrier have been measured at the HI-13 tandem accelerator of CIAE with an electrostatic deflector setup. The beam energies were decreased from 60 MeV to 45 MeV, corresponding to 1.3VB to 0.85VB where VB is the nominal Coulomb barrier, monotonically in order to reduce the magnetic hysteristics, with energy steps of 2.0 and 0.6 MeV at the higher and the lower energy ranges, respectively. Typical beam intensities ranged between 5 and 20 pnA with q+=5.

The thicknesses of the targets, determined by the weighting method, were 74Ge 120 μg/cm2 with 99% isotopic enrichment and 3 mm in diameter, evaporated onto ~30 μg/cm2 carbon backing, and 50 μg/cm2 76Ge, 99% isotopic enrichment and 5 mm in diameter, evaporated onto ~20 μg/cm2 carbon backing, respectively. The carbon backings faced the beam, corresponding to beam energy losses less than 0.5 MeV.

Four monitors of two Si(Au) and two PINs were located at 20°, with 1 mm diameter apertures, relative to the beam direction to monitor the beam and normalize the fusion cross sections, respectively. The exit of the chamber diameter is 2.5 mm, with a distance of 19 cm, corresponding to an opening angle of ±0.38° and solid angle of ∼0.136 msr, with a 10 μg/cm2 carbon foil to reset the charge states of the passing particles to equilibrium states.

The reaction products were separated by using the different electrical rigidities and then identified by using an E-TOF method. The two sets of electrical plates were set at a distance of 3.0 cm. The optimal high voltages for the fusion evaporation residues (ERs) were calibrated with two different beam energies, then extrapolated to other energies. Two-micochannel plates (MCPs)+Si (Si triggers the VME acquisition system), in which MCPs offer the start times and Si offers the stop time and the total energy of the particles, were used to reduce effectively the spurious events from random coincidences as backgrounds for these more asymmetric systems. The total lengths of the telescopes were ≈60 cm from MCP1 to Si and ∼40 cm from MCP1 to MCP2.

The angular distributions for the ERs were measured at 45.4 MeV and 40.39 MeV for 18O+74Ge and at 44.38 MeV for 16O+76Ge from －5° to +13° in steps of 0.5° or 1°, as shown in Fig. 1. They can be fitted with single Gaussian distributions. No large shape changes for the two systems within the measured energy region, so they were combined to give an overall angular distribution, with a weighted angular deviation of ~4.3°. The fusion cross sections were calculated by the integral of the differential cross sections.

For the two systems, the ERs dominate the fusion processes for the compound nuclei at this energy region. The ERs were measured at 3° and then to get the fusion cross section by using the ratio of σfus/dσ(3°) obtained from the above angular distributions for the other energies. The experimental fusion excitation functions for the two systems are shown in Fig. 2. The experimental result of 16O+76Ge measured by Aguilera et al. is also shown for comparison. No obvious fusion enhancement emerges for 18O+74Ge due to the positive Q－2n neutron transfer channel compared with 16O+76Ge. The result is also similar for 16,18O+92Mo, in despite of the positive Q－2n (5.56 MeV) for 18O+92Mo. In conclusion, experimental fusion excitation function of 18O+74Ge has been measured near and below the Coulomb barrier for the first time. A new set of data with good precision has also been measured for 16O+76Ge. For 18O+74Ge no additional fusion enhancement emerges compared with 16O+76Ge below the barrier. Also the role of 18O excitation states for fusion enhancement is minor, although of the lower excitation energy. Our measurements bring forward a wish toward the comprehension of fusion dynamics in


18O induced fusion reaction with Q－2n>0 systems. Further theoretical calculations of relationship based on the available experimental results are now needed, although of plenty of relevant works have been done both experimentally and theoretically so far. More relevant systematical and theoretical analysis based on the coupled channels calculations is now in progress.

Fig. 1 Angular distributions obtained for ERs

of 18O+74Ge and 16O+76Ge

The solid lines denote Gaussian fits for integration purpose

Fig. 2 Experimental fusion excitation functions

for 18O+74Ge and 16O+76Ge

* Supported by National Natural Science Foundation of China (11005154, 11075216)

High-Spin States in 86Sr

LIU Jia-jian, WU Xiao-guang, YAO Shun-he, LI Guang-sheng, HE Chuang-ye,

WANG Zhi-ming, HU Shi-peng LI Hong-wei, WANG Jin-long (Department of Nuclear Physics)

The previous works for high spins states of 86Sr were very scarce. In the past, the spin of highest

level of 86Sr was 13ħ found by the reaction 84Kr(α, 2nγ)86Sr in 28 MeV. The current work updates the level scheme of 86Sr to get more information about high spin states in 86Sr.

The high-spin states of 86Sr were populated by the fusion-evaporation reaction 82Se(9Be, 5n)86Sr at the beam energy ranging from 40 to 53 MeV. The 9Be beam was delivered by the HI-13 tandem accelerator. There were two targets, while one was consisted of a 0.85 mg/cm2 of 82Se with 4.45 mg/cm2 of Au backing, another was consisted of a 0.91 mg/cm2 of 82Se with 3.11 mg/cm2 of Au backing. The detector array comprised 9 anti-Compton HPGe-BGO spectrometers, 2 planar-type HPGe detectors and 1 clover detector. The total of 6×108 γ-γ coincidence events were collected in the experiment in event-by-event mode in about 80 hours beam time. After careful energy calibration and gain matching of each detector, the γ-γ coincidence data were sorted offline into conventional Eγ-Eγ matrices.

These matrices were analyzed by using the RADWARE package based on a Linux-PC system. By analyzing the γ-γ coincidence, 29 new γ transitions were assigned to the new level scheme (Fig. 1).


Fig. 1 Level scheme of 86Sr established in present work

High-Spin States in 87Sr

LI Hong-wei, WU Xiao-guang, ZHENG Yun, YAO Shun-he, HE Chuang-ye, LI Guang-sheng, LIU Jia-jian, HU Shi-peng, LI Cong-bo, WANG Jin-long, WU Yi-heng


The number of protons and neutrons of nuclei in the A=80-90 region are between 28 and 50. The

nuclei in 38 protons have a large deformation shell. The structure of these nuclei shows some information about intense competition between collective motion and single particle motion. It is very complex and has a large deformation. Moreover, the quasi-particle driving effect performs significantly and configuration related deformation is investigated in this region. So the nuclei in A=80-90 region have been researched by attention in recent years.

The experiment was performed at the HI-13 tandem accelerator at the China Institute of Atomic Energy. The high-spin states in the odd A nucleus 87Sr were populated via the heavy-ion fusion-evaporation reaction 82Se(9Be, 4n）87Sr. A detector array consists of 9 HPGe detectors, 2 planar HPGe detectors and a Clover detector, they were placed to the beam direction around angles ~40°(140°) and ~90°. The target composed of 0.85 mg/cm2 enriched isotopes 82Se on a backing of 4.45 mg/cm2 of Au was used. We have done the


excitation function, the beam energies were 30, 40, 44, 48 and 52 MeV. At last we took 46 MeV and 53 MeV as the beam energy to accumulate the coincidence events, At the end of the experiment, The Ge detectors were calibrated for efficiency using the standard γ sources of 133Ba and 152Eu.

The coincidence data has been sorted into γ-γ coincidence matrix on off-line. These matrices were analyzed by using the RADWARE package based on a Linux-PC system. The 87Sr original level scheme was established by S.E.ARNELL et al. in 1974. By analyzing the γ-γ coincidence, 38 new γ transitions were assigned to the new level scheme (Fig. 1).

Fig. 1 Level scheme of 87Sr deduced from the present work

The newly observed transitions from the present work are marked by star

Fast Timing: Lifetime Measurements With LaBr3 Scintillators*

LI Cong-bo1, WU Xiao-guang1, HE Chuang-ye1, ZHENG Yun1, LI Guang-sheng1, YAO Shun-he1, HU Shi-peng1, LI Hong-wei1, WANG Jin-long1, LIU Jia-jian1, XU Chuan2

(1. Department of Nuclear Physics, China Institute of Atomic Energy; 2. Peking University)

The lifetime of the first excited 2+ state in well deformed nuclei of the rare earth region is typically in

the range of 1 nanosecond. A variety of experimental methods have been developed for such measurements. In addition to the recoil distance method (RDM) using so-called plunger devices and triple-βγγ coincidence method, a new experimental method with LaBr3(Ce) detectors in combination with


the power of the Ge array, has been developed to deduce state lifetimes in sub-nanosecond region in very recent years. The method is suitable especially for in-beam γ-ray spectroscopy measurements where it was applied in many cases. In this new method, triple-gamma coincidences are measured with an array containing both HPGe and LaBr3:Ce detectors. The high-energy resolution of the Ge detectors is used to select the desired γ-ray cascade, and the array of fast LaBr3:Ce to build the delayed coincidence time spectra for selected levels.

Finally the time spectrum was analyzed by the shape deconvolution method. Because the centroid and the FWHM of the prompt time spectra slightly change as a function of γ-ray energy, the lifetime of the 2+ state was determined by also fitting the position and the width of the corresponding prompt curve and finally deduced to be τ=508(16) ps, which well agrees with the value of τ=505(60) ps using recoil distance method reported in the literature.The modern fast timing technique used in the present experiment, however, gave much higher precision of the measurement.

Fig. 1 Delayed coincidence time spectra of the first 2+ state in 174Os

* Supported by National Natural Science Foundation of China (11075214)

Technique of Measuring Effective LET in Integrated Circuit (IC)

SHI Shu-ting, GUO Gang, LIU Jian-cheng, SHEN Dong-jun, GAO Li-juan (Department of Nuclear Physics)

LET is one of the important parameters in the ground single event effects (SEE) simulation

experiment results, the accuracy will directly affect the accuracy of evaluation of radiation ability of space-borne microelectronic devices. In past SEE experiments, due to a lack of measuring method, the effective LET value of the ions that passed through dead layers and reach the sensitive area of the device can't be measured. Therefore the approximate calculation value or surface values were used, which enlarged the error of the SEE experiments results.

In this work, the mechanism of charge collection and the Pulse Height Analysis (PHA) method to the pn junction is studied in SEE Irradiation facility of Beijing HI-13 tandem accelerator. According to the linear relationship between the LET of ion in the sensitive region and the channel value of the peak of charge collection spectrum, the measurement of effective LET is achieved. Furthermore, the LET equivalence between vertical incidence and oblique incidence ions is studied, to master the method of


calculation of effective LET of the oblique incidence ions. The ions and effective LET measurement result of the pn junction is shown in Table 1. Charge collection measurements spectrum and effective LET versus channel number at various LETs of the junction is shown in Fig. 1. From Table 1 and Fig.1, we can see that1)The measurement LET is fit well with the calculation LET(the error of the calculation date is about 8%) 2) the linear relationship between the effective LET and the channel number is well, thus the PHA method can be used for measuring the effective LET in the pn junction.

Table 1 The effective LET measurement result of n+p junction

Ions Energy/

MeV

Incidence

angle/(º) Calculation LET/(MeV·mg·cm－2) Channel

Measurement

LET/(MeV·mg·cm－2) Deviation/%

Cl 160 0 13.1 104 Scaling ion

Ti 180 0 21.4 183 Scaling ion

Cu 200 0 32.5 305 34.1 4.8

Cu 200 30 37.6 357 39.5 5.3

Cu 200 45 46 454 49.6 7.9

Cu 200 60 65 651 70.2 8.0

Fig. 1 Charge collection measurements and effective LET versus channel number at various LETs on a n+p junction

Study on p+28Si Reaction for Proton Single Event Effects Research

HE An-lin, GUO Gang, HAN Yin-lu, CHENG Quan, SHEN Dong-jun, LIU Jian-cheng, SHI Shu-ting, HUI Ning, CAI Li, GAO Li-juan, FAN Hui


Single event effects is the one of the most importance space radiation effects. Therefore, it is very

necessary pay a special attention to SEE. SEE can caused by a single heavy-ion traversing a semiconductor or semiconductor-based device (integrated circuit, power supply, etc), SEE can also be caused by the interactions (elastic, inelastic scattering or spallation) of the incoming particle proton, with


atoms in the device producing light particles such as (p, α, n, d, 3He, t) and heavy recoil nuclei such as magnesium, aluminium. Most of the recoil species are heavier than the original particle and have large ionization capabilities. Then, the recoil particles can also generate tracks of electron–hole pairs along their path (indirect ionization). With this reason, we come to calculation the cross sections for p+28Si reaction.

Cross-sections of proton-induced reaction, recoil nuclei production cross sections are consistent calculated and analyzed for p+28Si at incident proton energies below 200 MeV by using nuclear theoretical models code TALYS. The calculation of optical model is based on ECIS-97 in TALYS, and the optical model potential parameters is Koning-Delaroche form. With the fit of relevant experimental data of reaction cross sections and elastic/inelastic scattering angular distributions, the best proton optical model potential parameters can be searched. Theoretical calculated results are compared with existing experimental and evaluation data. The main recoil particles of p+28Si reaction include like this 10-13C, 12-15N, 14-16O, 16-21F, 17-23Ne, 20-25Na, 21-26Mg, 23-27Al, 25-28Si, 27-28P. The one of calculated results of p+28Si reaction recoil particles distribution is given in Fig. 1.

Fig. 1 The main recoil particles distribution of p+28Si reaction in 160 MeV proton

Immunofluorescence Detection of γ-H2AX Foci Induced by 7Li Ions and γ-rays Radiation

SUI Li1, WANG Yu2, ZHOU Ping-kun2, KONG Fu-quan1, WANG Xiao1,

ZHENG Jie-ying1, MA Nan-ru1, LIU Jian-cheng1 (1. Department of Nuclear Physics, China Institute of Atomic Erengy;

2. Institute of Radiation Medicine of Military Academy of Medical Science)

DNA double strand breaks (DSBs) are considered as the most critical type of lesions. Correct and complete repair of DSBs guarantees cellular survival, while incorrect repair and residual DNA damage may lead to cell killing, mutation or transformation. Following induction of DNA double strand breaks, the specialized histone protein H2AX becomes phosphorylated (denoted as γ-H2AX) and rapidly accumulates at the sites of DNA DSBs forming distinct γ-H2AX foci. So by detecting the γ-H2AX foci, the DNA DSBs can be quantified.

In this study, using the 7Li ions of 43 MeV and γ-rays, the human foreskin fibroblastoid (HFS) cells marked with red fluorescence in cytoplast, were irradiated evenly at the dose of 2 Gy in air. After irradiation, cells were fixed with paraformaldehyde in PBS at 0.5, 1, 2 and 24 h postirradiation and were


subsequently immunostained (Green fluorescence) with an antibody probe against the γ-H2AX by immunofluorescence technique. Then Labeled cell preparations were examined with laser scanning confocal microscopy.

For the cells irradiated with 7Li ions, the number of γ-H2AX foci decreased as the time increased from 0.5 to 1 h. At 2 h postirradiation, a significantly larger number of clustered γ-H2AX foci appeared and formed massive fluorescence. At 24 h postirradiation, the number of residual cells was few. These phenomena suggested that DNA repair might mainly appear before 1 h, after that the cells of incorrect repaired would die. For the cells irradiated with γ-rays, the number of γ-H2AX foci as the time changed in a same way with 7Li ions, but clusteredγ-H2AX foci not appeared and the state of cells was nice at 24 h postirradiation. Figure 1 shows the quantitative results of averageγ-H2AX foci count per cell as the time changed for 7Li ions and γ-rays. From the graph, we can see that a significantly larger number of fluorescent clusters in HFS irradiated with 7Li ions than that of γ-rays at every time, which indicate 7Li ions could much more effectively produce the DNA DSBs.

Fig. 1 Amount of γ-H2AX foci induced with 7Li ions and γ-rays radiation

Research of Fast Neutron Radiation Effect on Rats

ZHENG Jie-ying, WANG Xiao, KONG Fu-quan, SUI Li, MA Nan-ru (Department of Nuclear Physics)

In order to research the fast neutron radiation effect on rats，the 8 weeks Wistar male rats were

wholly irradiated by 14 MeV fast neutron with 5 Gy. In the experiment，the rats were divided into normal and irradiation group, and killed at 1, 7, 14 d after irradiation for blood and organs. With samples, we conducted blood routine, counted bone marrow nucleated cell, calculated organ coefficient (liver, testis, epididymis, kidneys, spleen, thymus) and so on. Blood test results show that WBC, RBC, HGB of irradiation group are all lower than the normal. While white blood cells were significantly reduced at the first day，which indicates that the immune system is injured by fast neutron; red cells and the hemoglobin decreased at the14 d with different time effect. In addition, bone marrow nucleated cells counted at 14 d of irradiation group are significantly less than the normal, showing that bone marrow hematopoietic system is injured and difficult to be repaired. Among the organ coefficient results, only the testicles, thymus and spleen coefficient of the irradiation group is significantly smaller than the normal，showing that these three viscera are more sensitive to fast neutron radiation.


Fig. 1 Blood routine result

a—WBC; b—RBC; c—HGB

Fig. 2 Bone marrow nucleated cell count

Fig. 3 Organ coefficient

a—Testicular coefficient; b—Thymus coefficient; c—Spleen coefficient

Test of RPC Detector by Cosmic Ray*

LI Xiao-mei, HU Shou-yang, BAI Xin-zhan, ZHOU Jing, YE Li, SHAN Chao, ZHOU Shu-hua （Department of Nuclear Physics）

RPC is a gas detector made of high resistive material, which aims at detecting the track and time of

high energy charged particles. The RPC tested in this report will be used in the RHIC/PHENIX set-up forward upgrade. In this test, cosmic muon is used as the radiation source for RPC. RPC is placed between two plastic scintillators of different sizes, with the smaller scintillator having the area slightly smaller than that of RPC readout strip, which guarantees that the cosmics from the two scintillators pass through the RPC. A double layer RPC is used in the experiment with its area as 29 cm×29 cm and resistivity as 1012 Ω⋅cm. The critical part of RPC consists of two gas chambers which are composed of the resistive plates, the underlaying plates (thickness of 2 mm) and the sealing strips. The surface of the gas chambers is covered with graphite which functions as electrode. The readout strips are placed between the two gas chambers with two layers of insulative mylar separating them. The readout strips are made of


copper membranes, having the width 18 mm and gap 2 mm. When muon passes through RPC and the two plastic scintillators at the same time, signals will be generated

in RPC and the scintillators. A time spectrum of RPC obtained by ROOT analysis is shown in Fig. 1. The time resolution achieved in this experiment is within 2 ns, which meets the requirement for relativity heavy particles collision experiments. This test also investigates the change of the RPC time resolution along with the change of SF6 gas flux and the working voltage. The time resolution first decreases with the increase of voltage and then goes up again. The minimum of time resolution shifted forward with the increase of the ratio of SF6.

* Supported by NSFC in China (10875174, 11020101060, 11175262)

Calculation for Single Spin Asymmetry of Neutral Pion in Polarized Protons Collision at 200 GeV*

HU Shou-yang, LI Xiao-mei, ZHOU Jing, YE Li, BAI Xin-zhan, SHAN Chao, ZHOU Shu-hua

（Department of Nuclear Physics）

The single-spin transverse asymmetry for neutral pions Run-08 pp has been measured. We consider

the recent RHIC data on the transverse single spin asymmetry (SSA) AN. The measurement is consistent with a vanishing SSA. The present preliminary results of π0 all measurements in polarized proton-proton collisions at s1/2 = 200 GeV from Run8 (2008). Analyze data is very much lower than run-02 analyze data. The improvements to our previous measurement come from two main factors: Inclusion of more datum from the 2008 RHIC run with higher beam polarizations than the earlier run. The results are compared to a Next to Leading Order (NLO) perturbative Quantum Chromo Dynamics (pQCD) calculation with a range of polarized gluon distributions.

* Supported by National Natural Science Foundation of China (10875174, 11020101060, 11175262)

GEM Detector Electric Field Simulation*

BAI Xin-zhan, LI Xiao-mei, HU Shou-yang, YE Li, ZHOU Jing, ZHOU Shu-hua


GEM (Gas Electron Multiplier) detectors have been widely employed in the experimental field of high energy physics and nuclear physics. As a successor to drift chambers, GEMs are much easier to fabricate and have a much higher spatial resolution; a 75 micron resolution has been reached by CERN. The key part of a GEM is some sandwich-like foil as shown in Fig. 1.

Fig. 1 Time spectrum of RPC


Several construction parameters should be carefully designed to acquire an optimized spatial resolution. We have simulated the electric field distribution on a GEM foil using Maxwell 3D of Ansoft Co. During our simulation, we tried different hole diameters and different hole arrangements. We found that a better field distribution always accompanies a hexagon arrangement of holes when the diameters are fixed; and the magnitude of electric field increases when the diameter decreases with a fixed hole arrangement. We cannot make the hole too small because we should let electrons pass these foils easily. A distribution of electric field has been shown in Fig. 2 when the diameters of holes were set to 70 microns.

Fig. 1 Ansoft GEM foil Model

Fig. 2 Electric field distribution along the line crossing the GEM foil in Fig. 1

* Supported by NSFC ((10875174, 11020101060, 11175262) in China are acknowledged

Progress in Measuring 238U(n, xnγ) Cross Sections With HPGe Detector Array

WANG Zhao-hui, HOU Long, SU Xiao-bin, WANG Qi,

LI Xia, YU Guo-liang, KANG Guo-guo, ZHANG Xiao-peng （Department of Nuclear Physics）

Since the detector system had run for several years, so we did a overall maintenance and repair in

order to optimize the performance. The frame of detector array was altered, so the detector can get closer


to the target. And the target header of the cascade generator was improved. In the following experiment, we utilized two CLOVER detectors and one planar detector which was 15-17 cm away from the target. Every detector was surrounded by BGO detector. We did nanosecond and microsecond pulse beam experiments. After optimizing the cascade generator and replacing the old TTi target, the neutron beam was obviously enhanced. The efficiency of detectors was significantly increased for the change of distance. By experiment on Fe target, we validated the whole detection system. We can observe the peaks of 238U(n,n’) and (n,3n) reactions in experiment of U target（Fig. 1）. The cross sections are consistent with others’ result by preliminary judgment. The detail analysis is carrying on.

Fig. 1 γ spectrum in experiment of U target

Design of Pre-collimator System for Neutronics Benchmark Experiment

NIE Yang-bo1, CAI Xing-gang2, BAO Jie1, RUAN Xi-chao1, LIU Jian-tao2, ZHOU Zu-ying1 （1. Department of Nuclear Physics, China Institute of Atomic Energy; 2. South University of China）

In order to carry out evaluation of neutron nuclear data, in the last “Five-Year” period, China Institute of Atomic Energy has developed a set of neutron nuclear data benchmarking test system, and used the time-of-flight technique to measure the neutron leakage spectra from 238U slab sample, Analysis of these experiments was performed and provided valuable advice to improve the 238U data of the CENDL3.1. Since the experiment did not design the pre-collimator system, the effect / background ratios of experimental results in the high-energy area were low, which had a serious impact on the statistical error in this energy region. In the present “Five-Year” period, we will vigorously carry out work similar to the benchmark test, and must optimize the system in order to obtain better quality data, especially for pre-collimator system optimization. Fig. 1 shows the design of the pre-collimator system (including the pre-collimator and the shadow cone), the background spectra were simulated under various conditions by


using the MCNP-code, the results shown in Fig. 2, and the pre-collimator system that we designed has a significant improvement.

Fig. 1 Pre-collimator and shadow cone

Fig. 2 Background spectra under various conditions (simulated by using the MCNP-code)

Study of Fast Neutron Background Detection at Deep Underground Laboratory

REN Jie, RUAN Xi-chao, LI Xia, HUANG Han-xiong, ZHOU Zu-ying


In order to detect very low flux neutron background at deep underground laboratory, a low

background fast neutron detector will be developed. The detector is a Gd loaded liquid scintillator


contained in a Φ30 cm×40 cm cylindrical container. The low background materials will be used. An electronics system to record the fast signal which is generated by the recoiled proton, as well as the slow signal which is a gamma signal by the thermal neutron capture of Gd is proposed. With the coincidence of the two signals, neutron events can be identified. The neutron energy spectrum and flux can be obtained from the measured spectrum. The MCNP and Geant4 codes are used to simulate and optimize the detector. The simulation includes: The detection efficiency of detector for fast neutrons ranging from 0.5 MeV to 10 MeV under different detection thresholds (see Fig. 1); the fast signal, the slow signal, as well as the time interval between them. Fig. 2 shows the results for 1 MeV neutron as an example.

Fig. 1 Detection efficiency

Fig. 2 Fast signal (a), slow signal (b) and time interval (c)

Calibration of Li-glass Detector Efficiency

ZHANG Qi-wei, HE Guo-zhu, RUAN Xi-chao, ZHOU Zu-ying, TANG Hong-qing, REN Jie （Department of Nuclear Physics）

Li-glass detector will be used to measure the flux of neutron beam in Gamma-ray Total Absorption

Facility(GTAF). We have calibrated the detection efficiency of Li-glass detector in 5SDH-2 accelerator. The beam of neutron was produced by the reaction 7Li(p, n)7Be, and we chose three energy values of neutron (En=144 keV, 250 keV, 565 keV). By comparing the counts of BF3 long neutron tube and the Li-glass detector, we calculated the absolute detection efficiency of Li-glass detection at three energy values of neutron after solid angle correction (see Fig. 1). As shown in Fig. 2, there were some differences between the experimental result and the simulation by using Geant4 and MCNP, which could be resulted in the large dead time of acquisition system.


Fig. 1 Electronics diagram of experiment

Fig. 2 Comparison between experimental result and simulation

Lifetime Measurement of Inner Shell in the Collision of Fe, Au Ions and C Foil

CHANG Hong-wei, ZHANG Yan-ping, DU Shu-bin


The deep study of matter structure problem is very important and becomes an important guarantee of performance of nuclear weapon. In our county, some groups have done the inner-shell study and obtained some progresses, however most results are concentrated in theoretical calculation or astrophysical application while experimental study related to national defence is few. In this work, the lifetime of inner-shell is measured and the producing mechanism of X ray is studied in the collision of Fe, Au ions with the energies of 100 MeV and 120 MeV and C foil. Firstly, the transition K and L lines from beam ions in the collision of Fe ion with energy of 100 MeV and Au ion with energy of 120 MeV and C foil were measured. Then, the peak area can be obtained by using Origin lab software to do fitting of multiple Gaussian peaks. Finally, the dependence of transition intensities of Fe Kα and Au Lα2, Lβ1 on TOF can be obtained and is shown in Fig. 1. The lifetime of inner-shell energy level can be obtained by using an exponential fitting to experimental data. The results are that the TOF of Fe Kα is (146±9) ps, Au Lα2 is (292.64±42.98) ps, and Au Lβ1 is (299.97±46.52) ps.


Fig. 1 Dependence of transition intensities of Fe Kα and Au Lα2, Lβ1 on flight time

Phase Stability of Intermetallic Compound Ce3Al in Mechanical Milling

ZHANG Yan-ping, CHANG Hong-wei, DU Shu-bin （Department of Nuclear Physics）

For many years, cerium-aluminum systems have been extensively studied because of their unusual magnetic behaviors. As atomic radii of cerium and aluminum differ greatly from each other, a solid solution is not obtained due to the Hume-Rothery rule. Therefore intermetallic compounds are usually studied, and the structural stability is crucial for further discussion of their physical properties. The present paper reports on high-energy ball milling of the intermetallic compound Ce3Al at room temperature. Fig. 1 shows the X-ray diffraction patterns of the obtained products by MM with different milling times. It was found that pure cerium and aluminum are obtained in the initial stage, and then the subsequent reaction between the two metals produced a non-equilibrium, super-saturated solid solution. The lattice constants for all samples can be determined from the data and were found to be 5.109 Å, 5.070 Å, 5.035 Å and 5.016 Å, for 12 h, 24 h, 36 h and 48 h samples, respectively. This means that the lattice shrinks 1%-2.8% compared with pure γ-Ce. As the lattice constants for pure γ-Ce and Al are 5.161 Å and 4.049 Å, respectively, one can estimate the solubility of aluminum by assuming Vegard’s law. It was found that the solubility of Al atoms (value of y in Ce1－yAly) is from 0.05 to 0.13. The solubility of aluminum was estimated as 0.05-0.13 from peak shifts of X-ray diffraction pattern.

Fig. 1 Milling time dependence of X-ray diffraction patterns


Renewal and Modified Evaluation Data of 233U in CENDL-3.1

YU Bao-sheng, CHEN Guo-chang, ZHANG Hua （Department of Nuclear Physics）

A complete set of evaluated neutron nuclear data of 233U was preformed before 2000, and released in

2009. The status of the published nuclear data 233U in CENDL-3.1 is in some cases not up to the requirements. As the recent experimental data and the new international standard fission cross sections are not included. Therefore, the differences and even sometime very large discrepancy with other evaluated ones exist. In order to meet very well the requirement of new energy source and nuclear science technology application, then the revised recommended data of 233U are needed. We firstly survived the present status of the measured and evaluated nuclear data of 233U, especial newly published ones. The renewal and improvement of 233U data in CENDL-3.1 were preformed based on evaluation and analysis of lately measured and evaluated data.

Th/U-233 fuel cycle is a potential material for nuclear energy improvement. The neutron nuclear data of 233U play an important role in the framework of studies concerning new fuels and nuclear wastes produced by reactors and in other applications. Now, the predictions of Benchmark calculations were compared with Benchmark testing. The promising results are obtained when the renewal evaluated data of 233U are used instead of original evaluated 233U of CENDL-3.1.

The renewal and improvement of 233U data in CENDL-3.1 are follows: 1) The resonance parameters are revised from ENDF/B-VII. Meanwhile, cross sections around the

joint bound of the smoothly energy region and resonance region were adjusted smooth jointed. 2) The neutron number of prompt (υp) and delayed neutron (υd) emission per fission event was

evaluated for 233U based on absolute measurements and measurements relative to the spontaneous fission υ of 252Cf. In addition to experiment data, some systematics was used. The prompt (υp) and delayed neutron (υd ) yields for 233U were recommended from 10-5 eV to 20 MeV.

3) The evaluated fission cross sections using relative to 235U ratio data were re-normalized to standards cross section of the 235U(n,f) reaction, which is recommended by IAEA/WPEC/CSEWG as a standard. And recent high-accuracy measurements of this fission cross section also were included. Now, the revised fission cross sections of 233U have large change comparing to one from CENDL-3.1. The revised data are shown in Fig. 1 and 2.

4) The inelastic scattering cross section of 233U was recalculated based reanalysis experimental data. Present inelastic scattering cross section is shown in Fig. 3.

5) Previous elastic cross section measured included inelastic scattering of some low levels in its elastic scattering peak. Presently the data measured with good energy resolution were adopted, then the elastic scattering cross sections were decreased. Meantime the relativity other cross sections also have been adjusted, especial, the elastic cross section can reproduce experimental data very well. Present evaluated elastic scattering cross section is shown in Fig. 4.

The newly evaluated data are compared with ENDF/B-Ⅶ and JENDL-4. The evaluated cross section of 233U(n,γ) reaction can reproduce the experimental very well and is shown in Fig. 5.

For 233U(n,inl) reaction, there is a very unusual shape below 1 MeV in ENDF/B-Ⅶ, which is very different from this work and other evaluations and is shown in Fig. 6. From a physical point of view, the behavior of 233U inelastic cross section is expected to be very similar to the 235U, both being fissile odd-neutron nuclei. The reason will need future investigation.

Meantime, the promising results are obtained from feedback information of the predictions of benchmark calculations, which compare with benchmark testing when the renewal evaluated 233U were


used of instead of original data in CENDL-3.1. The calculated values keff are consistent with measured ones of benchmark testing installations within 5‰ in general, except for the reflect layer of tungsten and beryllium construction is remain 500 pcm. The renewal and modified evaluation data 233U are more reasonable than original evaluated one of CENDL-3.1. Presently, the evaluation data 233U are better than ENDF/B-Ⅶ and JENDL-4.0 and can meet requirement very well for nuclear enginging.

Fig. 1 Comparison of evaluated and measured data for 233U(n,f) reaction

Fig. 2 Comparison of evaluated data for 233U(n,f) reaction

Fig. 3 Comparison of evaluated data for 233U(n,inl)

reaction measured data Fig. 4 Comparison of evaluated data

for 233U(n,el) reaction


Fig. 5 Comparison of evaluated and

experimental data for 233U(n,γ) reaction

Fig. 6 Comparison of evaluated data

For 233U(n,inl) reaction

Uncertainty Analysis for Neutron Leakage Spectrum of LLNL Pulsed Sphere Facility due to Fission Cross Sections of 235U

WANG Wen-ming, WU Hai-cheng


The uncertainty of basic nuclear data has become the main source for the uncertainty of integral

parameters of nuclear facility. Thus, the study of such uncertainty plays an increasingly important role in nuclear design and simulation, especially in the determination of design margin. In the past several decades, Laurence-Livermore National Lab (LLNL) has done a lot of benchmark experiment to test the reliability of nuclear data, of which the neutron leakage spectrum of pulsed sphere facilities is a significant part. Monte Carlo method was implemented to simulate the leakage spectrum of 235U LLNL pulsed sphere, whose uncertainty was also analyzed with MCNP perturbation tech and SENS1D code developed by China Nuclear Data Center (CNDC).

For an integer parameter R and nuclear data q, we can define the sensitivity of R to q as: d ( ) / ( )( ( )) d ( ) / ( )Rq

R q R qS q q q=ζζ ζ

（1）

Together with covariance data Cov(qj, qk), we can obtain the uncertainty of R as:

12

1 1

Cov( , )[ ]

j k

n nj kR

Rq Rqj k j k

q qS SR q q

σ= =

= ∑∑ （2）

In the latest MCNP5 code, perturbation card can be used to simulate the respond function of the target integral parameters due to the perturbation of input nuclear data. Taking the 235U pulsed sphere facility for example, with a perturbation of 1% for the cross section in any energy group, the respond vector for all energy group of neutron leakage spectrum can be calculated, which is illustrated in Fig. 1. The total multi-group sensitivity matrix can be generated by sorting these vectors by energy group.

In order to analyze the sensitivity and uncertainty of integral parameters, SENS1D code system was developed by CNDC. Combining the sensitivity matrix and multi-group covariance data of 235U fission cross sections, SENS1D can calculate the final uncertainty of neutron leakage spectrum by energy group,


which can be found in Fig. 2. Final results show that in the energy regions below 5 MeV and above 15 MeV, the uncertainty of

neutron leakage spectrum is greater than in other regions, yet below 0.5%.

Fig. 1 Sensitivity of the 10th group 235U fission data

for neutron leakage spectrum

Fig. 2 235U sphere leakage spectrum and uncertainty

duo to 235U fission data

Calculation of Prompt Fission Neutron Spectra for 235U (n,f)

CHEN Yong-jing, LIU Ting-jin, TAO Xi, SHU Neng-chuan, SUN Zheng-jun （Department of Nuclear Physics）

The prompt fission neutron spectra for neutron-induced fission of 235U at En<5 MeV are calculated

using the nuclear evaporation theory with a semi-empirical model, in which the non-constant temperature and the constant temperature related to the Fermi gas model are taken into account. The results show in Fig.1 and 2. The calculated prompt fission neutron spectra reproduce the experimental data well. For n(thermal)+235U reaction, the average nuclear temperature of fission fragment are calculated. The energy carried away by gamma rays emitted of each fragment is also obtained and the results are in good agreement with the existing experimental data.

Fig. 1 Average nuclear temperature

of fission fragment for n(thermal)+235U reaction

Fig. 2 Total prompt fission neutron spectra

for n(thermal)+235U reaction


Systematic Characteristics of Fast Neutron Fission Cross Sections for Actinide Nuclei

WANG Ji-min, DUAN Jun-feng, ZHANG Jing-shang


The neutron fission cross sections of actinide nuclei are important data for the design of nuclear

reactor and nuclear engineering, and so on. So far, there has been a certain amount of experimental data for the fission cross sections of actinide nuclei. However, the measured data are scarce and scattered for some nuclei or energy regions, because the samples are difficult to get for some nuclei or the limit of experimental conditions. Based on the existing measured data, to study the neutron fission cross sections of actinide nuclei by systematics method is significant for application of nuclear energy and realization of nuclear fission. Earlier works on systematics of the neutron fission cross sections of actinide nuclei were performed in the 3-5 MeV energy regions mainly include H.L.Smith (Phys. Rev., 125, 1329, 1962), P.H.White (J. Nucl. Eng. 21, 671, 1967), J.E.Lynn (AERE-R 7468, 1974), J.W.Behrens (Phys. Rev. Lett., 39, 68, 1977) and J.W.Behrens (Trans. Am. Nucl. Soc., 24, 770, 1980).

It is difficult to build the systematics formulae of the fast neutron fission cross sections of actinide nuclei, so that the systematic characteristics have been explored on the basis of the fission barrier parameter and fission model theory. Based on the CENDL-3.1, the correlations between the fission barrier parameter Vf and the mass number A can be expressed as simple functions, as follow:

Vf－Bn=a×A－b Where a=0.069 6, b=16.19±0.22,

Vf－Bn=－0.366±0.15 odd-N In the expressions above, the Bn denotes the neutron binding energy of fission nucleus, the even-N

denotes even neutron number and odd-N denotes odd neutron number. Comparisons of Vf－Bn between fitting results and parameters are given in Fig. 1. The values of Vf and Bn were taken from CENDL-3.1.

Based on the systematics of level density for fission saddle point state (Zhang Jingshang, Wang Shunuan, Albums of nuclear reaction theoretical method and application, P226, 1980), the code FUNF-2011 version has been developed. In the code, the global phenomenological optical model potential for nucleon-actinide reactions (Yinlu Han, et al., Phys. Rev. C81, 024616, 2010) was adopted. The preliminary fitting results are given in Fig. 2 and 3, the experimental data were taken from EXFOR.

Fig. 1 Fitting results for parameters of Vf－Bn

Open symbols denote the experimental data are nonexistent, and the solid denote the experimental data are existent


Fig. 2 Fitting results for parameters of cross sections

Benchmarking 232Th Evaluations With KBR and Thor Experiments

WU Hai-cheng, ZHANG Hua （Department of Nuclear Physics）

The n+232Th evaluations from CENDL-3.1, ENDF/B-Ⅶ.0, JENDL-3.3 and JENDL-4.0 were tested

with KBR series and THOR benchmark from ICSBEP Handbook. THOR is Plutonium-Metal-Fast (PMF) criticality benchmark reflected with metal thorium. KBR series benchmarks include one fast spectrum experiment namely KBR-22 (HMF068_1), one intermediate-spectrum benchmark namely KBR-23(HMI008_1) and four k∞ experiments referred as KBR-18-KBR-21. The criticalities of these experiments were calculated with Monte Carlo code MCNP5. The ACE libraries used in this work were prepared with NJOY99.

The comparison of C/E values of keff for the selected benchmarks calculated with CENDL-3.1, ENDF/B-Ⅶ.0, JENDL-3.3 and 4.0 is shown in Fig. 1 plotted against energy spectrum index EALF. The benchmarks of fast and thermal spectra are marked with rectangular separately. For fast and intermediate energy spectra experiment, obvious overpredictions of keff are observed in results of CENDL-3.1 and JENDL-3.3. The C/E values of KBR-18 and 19 which represented the transition from fast to intermediate energy spectrum are more than 3 000 pcm higher than expected. The C/E values for these two benchmarks calculated with ENDF/B-Ⅶ.0 are better than CENDL-3.1 and JENDL-3.3, but the results for KBR-18 is still overestimated by 1 300 pcm, and underestimation of KBR-22 by 560 pcm is found at the same time. The C/E values of KBR-21 are under predicted about 3 000 pcm consistently by four libraries.

To study the source of keff bias between calculations and experiments for CENDL library, simple substitution analysis is performed. The C/E values of these benchmarks were calculated based on CENDL except the data for 1H and 235, 238U replaced with ENDF/B separately, labeled as C31.B70H and C31.B70HU. The calculations based on ENDF/B with only 232Th data substituted with CENDL-3.1 were also performed. These calculated C/E values are compared in Fig. 2 together with the results of CENDL-3.1 and ENDF/B-Ⅶ.0. Through substitution analysis, the over prediction of the C/E values for fast and intermediate energy spectra due to 232Th evaluation can be concluded. Further improvement on the data for 232Th is needed.


Fig. 1 Comparison of C/E values

of keff for KBRs and Thor

Fig. 2 C/E results of KBRs and Thor substituted

with 1H, 235,238U, and 232Th evaluations

Study on the Processing Method for Resonance Self-shielding Calculations

LIU Ping （Department of Nuclear Physics）

We investigate a new approach for resonance self-shielding calculations, based on a straightforward

subgroup method, used in association with characteristics method. Subgroup method is actually the subdivision of cross section range for resonance energy range. Subgroup method avoids dividing many groups in resonance energy, but the precision of resonance calculations is similar to this of fine groups resonance processing.

We can define the subgroup cross section as:

( ) ( ) ( ), d / di i

x i xE E

E E E E Eσ σ φ φΔ Δ

= ∫ ∫

We can define the subgroup probability as: pi=ΔEi/ΔEg

According to the above definition of subgroup parameters σx,i and pi, the subgroup-characteristics equation is as follows:

, ,, , , ,

, ,

dd

B Bg m i B B

g m i g m ii g i

Qs

φφ+ =∑

The subgroup parameters σx,i and pi can be calculated by using the background cross section and resonance integral, and the subgroup transport equation will be solved using the relevant subgroup parameters.

In general, the neutron characteristic transport equation is as follows:

,, ,

, ,

dd

g ig i g i

t g iQ

sφ

φ+ =∑

The equation based on subgroup model is formally similar to the neutron transport equation. The combination of subgroup model with relevant neutron transport equation is a more precise and better applicability resonance calculation model.


Research on Nuclear Reaction Network Equation for Fission Product Nuclides

QIAN Jing, LIU Ting-jin, SHU Neng-chuan, SUN Zheng-jun


Nuclear Reaction Network Equation calculation system for fission product nuclides was developed.

With the system, the number of the fission product nuclides at different time can be calculated in the different neutron field intensity and neutron energy spectra. The groundwork is established with the system for possibly resolving the discrepancy on the fission yield data between the evaluated ones based on the experimental data and the data practically used by the user on-site test with considering the strong neutron field. Meanwhile, this system also can be used for calculating the decay γ intensity and energy spectrum of fission product nuclides. The purple red dot dash line in Fig. 1 and Fig. 2 show the difference of the number of the fission product nuclide 147Nd at different time between without neutron field and with strong neutron field intensity. Before 50 ns, lower cumulative yield for 147Nd was brought by the existence of strong neutron field.

Fig. 1 Number of fission product nuclides at different time without neutron field of 235U induced by thermal neutron

Fig. 2 Number of fission product nuclides at different time with strong neutron field of 235U induced by thermal neutron


Iso-spin Dependent Microscopic Optical Model Potential Based on Dirac Bruckner Haretree Fock Method

XU Rui-rui, MA Zhong-yu


The microscopic optical model is investigated in the Dirac-Brueckner-Hartree-Fock (DBHF) framework with Bonn B meson exchange potential. Both real and imaginary parts of isospin-dependent self-energies are derived from a strict projection calculation on Lorentz invariant amplitudes. We construct the central potentials (scalar and vector potentials) according to the self-energies, and the potentials of finite nuclei of equivalent Schrodinger equation are determined correspondingly through a local density approximation. In this paper, the potentials for neutron and proton scattered by 27Al are computed. The total cross sections, differential elastic scattering cross sections are both obtained and compared with the experimental data and non-relativistic phenomenological OMP calculation in Fig. 1-3. It is shown that a constant Gaussian factor of improved local density approximation can yield a good prediction for this scattering calculation with various incident energies.

Fig. 1 Elastic scattering angular distribution of n+27Al

Fig. 2 Elastic scattering angular distribution of p+27Al


Fig. 3 Total cross sections of n+27Al

Preparation of 64Ni-Gd-Cu Target

FAN Qi-wen, DU Ying-hui, ZHANG Rong (Department of Nuclear Physics)

The three-layer-sandwich targets of 64Ni-Gd-Cu needed in the physics experiment were prepared. The middle layers are thin ferromagnetic Gd layers of about 1.7 mg/cm2, recoil stopper layers are thick crystallized and defect-free Cu layers of about 12 mg/cm2. The thickness of the 64Ni target layers is about 350 μg/cm2, and the uniformity should be better than 90%.

In order to get crystallized and defect-free Cu recoil stopper layers, it is very critical to anneal the rolled Cu foils of 12 mg/cm2. The temperature of annealing was 1 000 K, and the annealing lasted 1 h, the vacuum kept better than 2×10－3 Pa during the annealing.

The good ferromagnetic Gd layers of 1.7 mg/cm2 have been deposited by the method of roasting-evaporating, the temperature of roasting substrate kept at 570 K, and the vacuum kept better than 1×10－3 Pa during the evaporating.

64Ni targets of 350 μg/cm2 have been prepared by using focused heavy ion beam sputtering, the parameters of sputtering are shown in Table 1.

Table 1 Parameters of sputtering

Ion type Acceleration

voltage/kV

Focused

voltage/kV

Pressure

of ion source/Pa

Pressure of sputtering

chamber/Pa Beam current/mA

Ar+ 10 1.0 5.4 8×10－4 0.25

Preparation of Super-Thin, Large-Area, Double-Sided Gold-Plated Mylar Film

ZHANG Rong, FAN Qi-wen, DU Ying-hui


Large-area multi-wire parallel plane avalanche counter (MWPPAC) is a kind of gas detector widely


used in nuclear experiments. MWPPAC is composed of front-window film, X wires, anode film, Y wires and rear-window film, which is mostly utilized to measuring the X, Y positions and timing signals of heavy-ions. The advantages are its large area and good timing as well as position resolutions. Thus, it is extensively applied for measuring the fission fragments, diagnosing of radioactive beams or weak beams. In order to minimize the energy loss in the film for heavy-ions, it requires that the thicknesses of front- and rear-windows as well as anode films are as thin as possible, which is the key point to make a good MWPPAC with perfect performances. For this purpose, we prepared super-thin, large-area, double-sided gold-plated Mylar films for the MWPPAC detectors.

The Mylar film with thickness of 0.5 μm was extended tightly on the aluminum frame with diameter of 26 cm (effective area of 530.66 cm2). Small holes will be engendered easily in the evaporation process because the film is so thin and the thermal capacity is so low, resulting in detector gas leakage. During the preparation, three approaches were adopted to reduce the small holes: 1) monitoring the gold evaporation rate by a thickness meter and controlling the rate less than 0.1 μg/cm2/s; 2) keeping the frame rotating in the period of evaporation; 3) using Mo evaporating boat and controlling the heating current I<120 A. Finally, 3 pieces of double-sided gold-planted Mylar films have been successfully produced with gold thickness of 20-25 μg/cm2.

A MWPPAC was manufactured using these double-sided gold-planted Mylar films. No obvious gas leakage was found at gas pressure of 10 torr under vacuum of 5×10－3 Pa. It is shown that there are no small holes in the films. Preparing of these super-thin, large-area, double-sided gold-plated films is quite successful.

Post Accelerator for Proposal of CARIF

PENG Zhao-hua （Department of Nuclear Physics）

CARIF is a new generation ISOL-like RIB facility which is based on CARR, will be used to generate

ions near n-rich line. Primary beam comes from CARR, separated and highly charged by ECRIS system, will be accelerated to 150 MeV/u, then works as bomb in a FR system to generate secondary beam which is near n-rich line.

Users ask for: Heavy ions(132Sn, 91Kr,…), beam energy >150 MeV/u, high beam transmission (intensity of primary beam is limited around 10－11 pps).

Multi-charge states acceleration is the key issue for this design, a compromise between cost and performance of CARIF.

Post accelerator for CARIF is design for beam with mass to charge ratio less than 6, it means, for single charge state acceleration, the total effective accelerating voltage is 900 MV. If beam is stripped to highly charged state at energy of about 20 MeV/u, mass to charge ratio will go up to 2.8, so the total effective accelerating voltage is around 490 MV, it means cost of CARIF will go down around 40%, but at the same time, beam intensity will lose around 75%.

In order to get more beam, SC resonators (QWR and HWR) will be used to accelerate multi-charge states beam in design, because SC resonators have bigger aperture to accept beam with bigger spots. If multi-charge states acceleration is used after beam energy greater than 20 MeV/u, beam loss will reduce to


about 30% from 75%. A further consideration is to accelerate multi-charge states beam from the beginning: a velocity &

phase equalizer system (Fig .2) will settle upstream of RFQ, this system will accept multi-charge states beam from beam analyzer which is just downstream of ECR, and adjust velocities of ions with different charge state as the same meanwhile phase of them are slightly different which will match charge states. After adjusting, all ions could be accepted and accelerated with same energy gain by RFQ. This consideration will get at least 100% more beam.

Considerations about SC resonators and cryomodules are listed in Table 1.

Table 1 Lists of SC resonators and modules

Value of parameters Parameters

Section 1 Section 2 Section 3 Section 4 Section 5

Type QWR1 QWR2 QWR2 HWR1 HWR2

Temperature/K 4.2 4.2 4.2 2 2

Frequence/MHz 80.5 80.5 80.5 322 322

Va/MV 0.81 1.62 1.62 1.9 3.7

Relativity speed 0.041 0.085 0.085 0.285 0.53

Ein/（MeV·u-1） 0.40 1.78 9.82 19.09 66.06

Number of cavity 12 36 54 80 80

Mass charge ratio 6.00 6 6 2.82 2.82

Phase －25 －25 －25 －25 －25

Eout/（MeV·u-1） 1.78 9.82 19.09 66.06 155.19

Number of modules 3 9 9 10 10

Number of solenoids 3 9 9 10 10

Post accelerator for proposal of CARIF will use SC resonators to accelerate multi-charge states beam in order to reduce cost meanwhile keeping high transmission. Totally there are 262 resonators which will be settled in 41 cryomodules.

Reliability Test of an ECR Ion Source for Accelerator Driven Sub-critical System (ADS)

CUI Bao-qun, TANG Bing, MA Rui-gang, HUANG Qing-hua,

MA Ying-jun, CHEN Li-hua, JIANG Wei-sheng （Department of Nuclear Physics）

The reliability of accelerator for ADS research is close to 100%, so the requirement for ion

source is very high. Due to the high heat power and complicated environment such as the strong electric field, magnetic field and unfavorable vacuum condition nearby the extraction area, the source is subject to failure from HV break down, melting of the extraction aperture and break of the microwave window. After recent year’s development, the last two issues are well resolved, and HV break down problem has been greatly improved. A reliability test has been carried out in the test


bench, which consists of a microwave ion source, vacuum system, beam stop, and control system. The setup is shown in Fig. 1.

Three availability tests have been carried out. An unique control scheme is adopted, so the reliability of ion source is improved. The details of these runs are tabulated in Table 1. At last test, the source is operated for more than 220 h at 75 keV, 100 mA extracted hydrogen current, 2 beam trips is recorded in the period, and uninterrupted operation time is about 150 h. The ion source is possible to fulfill the requirements of ADS research.

Fig. 1 Picture of test bench Fig. 2 Beam current vs the elapsed time in the 220 h run

Table 1 Detail of reliability run

Parameters Duration time/h Spark Trip Trip reason

75 keV@110 mA 25.3 21 8 microwave power supply failure

75 keV@110 mA 150 150 8 3 high voltage power supply failure

2 PLC failure

3 others (cooling water , primary pump)

75 keV@110 mA 220 8 2 microwave power supply failure

Development of ECR Ion Source for ADS

TANG Bing, CUI Bao-qun, MA Rui-gang, HUANG Qing-hua, MA Ying-jun, CHEN Li-hua, JIANG Wei-sheng


A high-current microwave proton ion source for ADS research is being developed at China Institute of Atomic Energy. The RFQ input beam requirements are 75 keV, 60 mA proton current, 0.20π mm·mrad rms normalized emittance, and the reliability close to 100%. At present, the ion source can produce over 100 mA dc hydrogen beam current with the required emittance as shown in Fig. 1. The gas consumption is about 5-10 sccm. Measured proton fractions are 85%-90% of the beam current, which is shown in Fig. 2. An unique technique to improve the reliability was adopted. The source was operated for more than 400 h at 75 keV, 100 mA extracted hydrogen current, uninterrupted operation time is about 150 h.


Fig. 1 Extracted current vs microwave power Fig. 2 Proton fraction vs extracted current

Installation and Trial Run of the Furnace

HU Rui, SUN Shuo, SUN Kai, LIU Yun-tao, CHEN Dong-feng （Department of Nuclear Physics）

In order to meet the demand of neutron experiment in the future, the neutron lab equips with extreme

temperature furnace (Fig. 1), the furnace is designed and produced by the professional producer-Scientific Products Ltd. The products installation and trial run have been finished. Temperature can be adjusted between 100 and 1 800 , the furnace is in PID control mode, and it can control temperature exactly. By the trial run, the furnace is ready for future neutron experiment.

Fig. 1 Picture of furnace

Progress in Neutron Texture Diffractometer at CARR

LI Mei-juan, LIU Xiao-long, TIAN Geng-fang, WU Zhan-hua, WU Li-qi, WANG Hong-li, SUN Kai, LIU Yun-tao, CHEN Dong-feng


The key components for neutron texture diffractometer (NTD) at CARR, such as the collimator, monochromator and the neutron beam limiting systems, have been finished in the year 2011. At the same


time, improvements of the detector shielding and controlling software were finished. In detail, the collimation system consists of the primary collimators and adjusting device. The

primary collimator restricts the divergence of neutron beam, and three collimators with different divergence locate on the adjusting device. By moving and rotating the adjusting device, we can select different collimators and adjust their attitude. Monochromator system consists of monochromators, which select the neutron beam with certain wave length, and their adjusting device which adjust attitude of monochromator by rotating, tilting and parallel moving.

To improve the resolution of diffractometer, a third Soller collimator with divergence of 30′ was located between sample table and detector. At the same time, the motion control software has been developed for neutron texture diffractormeter.

At present, the cold commission of the neutron texture diffractometer has been finished. In 2012, the adjustment with neutron will be carried out for this neutron texture diffracotmeter if it is permitted.

Fig. 1 Photo of neutron texture diffractometer at CARR

General Design for CARR Neutron Guide System

LIANG Feng, WANG Hong-li, HE Lin-feng, WEI Guo-hai, WANG Yu, ZHANG Li, LIU Yun-tao, CHEN Dong-feng


A neutron guide system has been designed and partly installed at the China Advanced Research

Reactor (CARR) to transport cold neutrons from the cold neutron source (CNS) to several instruments, which are situated in a separate guide hall of 30 m×60 m. The general design of CARR neutron guide system (CNGS) will consist of a specially designed cold neutron beam tube (BT-12) and four primary neutron guides, whose cross sections are 3 cm×15 cm (2 guides), and 5 cm×20 cm (2 guides), respectively. These neutron guides will be coated with either natural Ni mirror, or 2θc supermirrors. In the guide bunker of the reactor building, the primary neutron guides are connected to the curved guides in order to remove the gamma rays and fast neutrons. Two curved neutron guides are subdivided into up and down guides respectively by inserting two partitions mirrors and separated from each other by the opposite curved guides. All neutron guides are optimized by using the neutron guide simulation code.

At end of April, 2012, the installation work of bunker and the vacuum system will be completed.


Fig. 1 Layout of neutron guides and instruments in CARR

Experimental Software Design of the Neutron Texture Diffractometer at China Advanced Research Reactor

LIU Xiao-long, LIU Yun-tao, LI Mei-juan, TIAN Geng-fang, WU Li-qi, CHEN Dong-feng


Neutron scattering lab is building our country’s first neutron texture diffractometer, which will be

used for the texture measurement and analysis in the materials science and engineering applications. The sample table and its measurement and control system were introduced from the Julich neutron scattering center. Before the introduction, they were used for the measurement of crystal structure by the experimental software for four circle diffractometer. In order to apply these components for the texture measurement, the experimental software for CARR neutron texture diffractometer is needed to design.

Based on the principle of texture measurement by neutron diffraction and the motion control and data acquisition system of the diffractometer, the functions needed for texture measurement were proposed as follows.

1) Beam monitoring. To choose the measurement mode, continuously record the monitor counts for several times, and then check the stability of the neutron beam.

2) Detector counting. Input the measurement mode, time or calibration number of monitor, then collect the neutron counts of Helium-3 tube in current orientation.

3) Diffraction spectrum scanning. Input the start angle, step angle and end angle of 2theta axis, and the measurement mode, time or calibration number of monitor, then call the Detector Counting module at each 2theta angle, finally get the diffraction spectrum in the range of 2theta input.

4) Pole figure measurement. Input the 2theta angle, start angle, step angle and end angle of both chi and phi axis, and the measurement mode, time or calibration number of monitor, then call the Detector Counting module at each orientation.

The function modules above were realized by python in Linux system. The software was tested by the signal generator in stead of neutron beam. The result showed that the software flow ran correctly and the software satisfied the requirements of the texture measurement. The experimental software for CARR


neutron texture diffractometer has been successfully accomplished.

Floating Zone Growth of LiFePO4 Single Crystals*

TIAN Geng-fang1, HAN Wen-ze1, WANG Ji-yang2, LIU Yun-tao1, CHEN Dong-feng1 （1. Institute of Crystal Materials, Shandong University；

2. Department of Nuclear Physics, China Institute of Atomic Energy）

During the past few years the search for cathode materials of rechargeable lithium batteries has been

mainly focused on lithium metal oxides. Among them, lithium iron phosphate, LiFePO4, provides an attractive voltage of 3.5 V, high theoretical capacity (170 mA·h·g－1), low cost, ease of synthesis, and stability when used with common organic electrolyte systems, and becomes one of the most promising candidates.

LiFePO4 powders were synthesized by the solid-state reaction of stoichiometric composition. Single crystals were grown in an optical floating zone furnace (Crystal System Incorporation, Japan). The LiFePO4 polycrystalline powders were reground and shaped into cylindrical bars by pressing at an isostastic pressure of about 68 MPa to form feed rods. The rods were sintered at 800 for 10 h in Ar flow. After sintering about 20 mm long, rod was cut to serve as a first seed and thereafter the grown crystal was used as a seed. The sintering procedure may be neglected to avoid the compound decomposition whenever it is necessary. The feed rod and the growing crystal were rotated at 20 r/min in opposite directions. In an attempt to reduce the volatilization of Li and obtain stoichiometric large crystals, we applied various traveling rates of 5 mm/h under a pure argon flow of 100 mL/min throughout the growing procedure.


H310BO3/ZnS(Ag) Scintillator Screen for Thermal Neutron Radiography

WANG Yu, HAN Song-bai, HE Lin-feng, WEI Guo-hai,

WANG Hong-li, LIU Yun-tao, CHEN Dong-feng （Department of Nuclear Physics）

In 2011, neutron image team has completed the fabrication work of the scintillator screen for thermal

neutron radiography. The neutron converter screens consist of a dispersion of H310BO3/ZnS(Ag) particles

in epoxy binder. H310BO3/ZnS(Ag) screen with various thickness were fabricated by spraying method.

The neutron imaging detector characteristics was investigated in neutron radiography facility with accelerator neutron source using D-Be at Peking University of China. Its spatial resolution was measured to be 320 μm at 300 μm thickness and its luminescence efficiency is 1/4 of commercial 6LiF/ZnS(Ag) screen (Fig. 1). The experiment results indicate that H3

10BO3/ZnS(Ag) scintillator has potential application for thermal neutron radiography.


Fig. 1 NR image of indicator by H3

10BO3/ZnS(Ag) scintillator

Non-destructive-Testing of Nuclear Fuel Element by Means of Neutron Imaging Technique

WEI Guo-hai, HAN Song-bai, CHEN Dong-feng, HAO Li-jie, WU Mei-mei, LIU Yun-tao, WANG Hong-li


Nuclear fuel element is the key component of nuclear reactor. People have to make strictly testing of

the element to make sure the reactor operating safely. Neutron imaging is one of Non-destructive-Testing (NDT) techniques, which are very important techniques for inspecting nuclear elements. Compared with X-ray method, neutron imaging technique has a few advantages as follows. 1) Neutron has high penetrating ability, so it is possible to penetrate nuclear fuel elements (diameter about 10 mm) to inspect the pellet inside the clad. 2) The different isotopic behavior between 235U and 238U is very obvious in the interaction with thermal neutron. Due to the 60 times higher cross-section of 235U, it is very easy to distinguish between 235U and 238U. It is direct and easy to make certain the enrichment of 235U of the nuclear fuel element by neutron imaging technique. 3) Neutron has high sensitivity for light atoms such as hydrogen, a quantification of the hydrogen content can be made from the cladding by neutron imaging. 4) It is possible to make NDT for radioactive sample by indirect neutron imaging method with special neutron converter (metal foil) which is non-sensitive to radioactivity.

Due to those advantages in testing nuclear fuel element, neutron imaging technique is an powerful tool in testing the crack of element, making certain the enrichment of 235U, checking the hydrogen agglomeration in the cladding surface, and so on.

China Institute of Atomic Energy (CIAE) has built the special facility which is used to carry out the inspecting experiment of nuclear fuel element (15 cm long) by neutron imaging, and has primarily eatablished the indirect neutron imaging method.

Crystal Structure and Thermal Expansion Properties of Lu2-xFexMo3O12*

WU Mei-mei, ZU Yong, LIU Yun-tao, CHEN Dong-feng （Department of Nuclear Physics）

Low or zero thermal expansion materials have a lot of potential applications in space shuttle, microelectronic components, and optical mirrors et al. Polycrystalline samples Lu2－xFexMo3O12 have been prepared successfully by solid state reaction, and characterized by X-ray diffraction. Rietveld analysis


indicates that compounds with x≤1.3 exhibit orthorhombic structure with space group Pnca; compounds with x≥1.5 have monoclinic structure with space group P21/a. Phase transition from monoclinic to orthorhombic occurs at higher temperature. Variable temperature XRD indicate that the linear thermal expansion coefficients of orthorhombic phase vary from negative to positive with increasing Fe content. By carefully adjustment of Lu/Fe ratio, zero thermal expansion is observed in Lu1.3Fe0.7Mo3O12 in the 200-400 temperature range. The mechanism of negative thermal expansion in A2M3O12 family is attributed to the rocking motion of polyhedra based on the correlated transverse thermal vibration of oxygen perpendicular to A-O-M linkages. However, the rocking motions present only when the polyhedra can undergo some slight distortion. With increasing Fe content, the rigidity of Lu(Fe)O6 polyhedra is enhanced, as a result, the thermal expansion property varies from negative to positive.


Neutron Time of Flight Spectrometer for Velocity Selector Calibration

YU Zhou-xiang1, CHENG He2, LIU Yun-tao1, CHEN Dong-feng1

（1. Institute of Chemistry, Chinese Academy of Sciences；

2. Department of Nuclear Physic, China Institute of Atomic Energy）

Small angle neutron spectrometer on China Advanced Research Reactor (CARR) is located at

neutron guide hall and is installed on the end of cold neutron guide. Velocity selector which can purify white light neutron beam into monochromatic neutron beam with wavelength λ and resolution Δλ/λ (FWHM) to satisfy the demand of neutron scattering experiments is its key component. Adjustable wavelength range is 2.7-45 Å and adjustable resolution range is 8%-25%, which satisfy the small angel neutron spectrometer demands for selectable wavelength range 2.7-20 Å and selectable resolution range 10%-22%. Neutron time of flight spectrometer for velocity selector calibration is an experiment apparatus which is used for wavelength and resolution measurements of monochromatic neutron beam. According to the measurement results, the rotating speed and tilt angle of velocity selector are adjusted until specific wavelength and resolution decided by physics experiment are acquired.

Fig. 1 Sketch map of neutron time of flight spectrometer structure

As shown in Fig. 1, neutron time of flight spectrometer is composed by limit slit, chopper, single

tube detector and two dimension area detector. Limit slit width is 2 millimeter. The chopper slit width is 2 millimeter and its radial length is 5 millimeter, 120 millimeter from the center of chopper. Hardware flow chart of spectrometer detection system is shown in Fig. 2. Single tube detector is a low sensitivity helium


three detector. The active area is 120 millimeter long and has a diameter of 50 millimeter. The operating voltage is 1 300 volts. When the differential and integral circuit time constants are 1 microsecond, the width of amplifier pulse output is 25 microseconds. Its detection efficiency is about 4×10－4. The two dimension area detector is 30 meters far from the single tube and 30 meters is also the neutron flight distance. The sensitive gas is 3He and detection efficiency is 50% for 2 angstrom neutron. Its active area is 640 mm×640 mm and its spatial resolution is 5 mm×5 mm. Signals from its anode are acquired during measuring. The time flight spectra measurement uses multi-hit mode. Time multi-scaler MCS-PCI is the key component of detection system. It receives photoelectric switch signal as its start signal and receives two detector signals as its stop signal. The data is eventually normalized by period number.

Fig. 2 Hardware flow chart of detection system

Progress Report of Small Angle Neutron Scattering on CARR

ZHANG Li, LI Tian-fu, HE Lin-feng, WEI Guo-hai, WANG Hong-li, LIU Yun-tao, CHEN Dong-feng （Department of Nuclear Physics）

The project of small angle neutron scattering spectrometer (SANS) belongs to “building up the center for neutron scattering”. It’s one of the project “national science & technology infrastructure center”.

The building parts are already done in 2010. By the proposal one of the works of neutron scattering laboratory is the installation of shielding part from the end of the straight guide to the collimation part of SANS. The other work is to test the software of motion control with beam on.

As the request the shielding part should be mounted as soon as possible in this year. It were already finished from the connect part with the shielding part of guide to the part before the sample stage before July. For the software testing with beam on it has to be done next year because there was no neutron beam this year.

Fig. 1 Overview of SANS with shielding


Small Angle Neutron Scattering Study on Structure of PAMAM Dendrimer Encapsulation With Small Molecules in Aqueous Solution

LI Tian-fu, LIU Yun-tao, CHEN Dong-feng, WANG Hong-li, ZHANG Li,

HE Lin-feng, WEI Guo-hai, WANG Yu （Department of Nuclear Physics）

Dendrimers have very unique structural and physicochemical properties and many potential

important applications, such as drug delivery, and therefore have been attracting research interests. It is interesting and important to investigate the interaction of these dendrimers with small molecules in aqueous solution, both for the fundamental research and their application development. By using NMR, Y. Cheng and coworker have systematically studied the interaction of small drug molecules with PAMAM dendrimers. The encapsulation of some small molecules in PAMAM dendrimers has been revealed. SANS is very suitable for studying these systems and can provide us very useful information. Recently, we designed and performed some SANS experiments on these systems. By analyzing the data, we were able to quantify the small molecules associated to one dendrimer molecule. And detailed structure parameters were also extracted by model fitting. Further study on these systems is ongoing.

SANS is a very powerful tool in characterizing nanoscale structures in many fields. A SANS instrument have just been built at CARR neutron guide hall, which will be open to users. This will bring new opportunities to domestic scientists in related fields.

This work is done in collaboration with Professor Sung-Min Choi from Korea Advanced Institute of Science and Technology and Prof. Yiyun Cheng from East China Normal University.

Investigation on Crystal Structure, Magnetism and Colossal Magnetoresistance of Y2CrS4

*

LIU Rong-deng1, LIU Yun-tao 1, CHEN Dong-feng 1, LI Jun-hong 1, HE Lun-hua 2, WANG Fang-wei 2 （1. Department of Nuclear Physics, China Institute of Atomic Energy;

2. Institute of Physics, Chinese Academy of Sciences）

Ternary yttrium chromium sulfide, Y2CrS4, was well prepared by a solid state reaction of Y2S3, Cr,

and S. In this year we investigated its crystal structure, magnetism and magnetotransport properties. The X-ray diffraction pattern at 300 K was refined with the space group Pca21. The cell parameters

were a=12.51 Å, b=7.53 Å, and c=12.49 Å and the atomic coordinates were obtained. Bond lengths between Cr and S were calculated from the refined crystal structure of Y2CrS4. The four bonds for each Cr were shorter than the other two bonds, which indicated that CrS6 octahedra are distorted by Jahn-Teller effect of ground state of divalent chromium ions: d4 ion. An antiferromagnetic transition was observed at about 64 K. The effective paramagnetic moments was deduced from the Curie-Weiss fitting of the linear part of the corresponding reciprocal magnetic susceptibility curve in the 150-300 K temperature range, μeff=3.532μB. And a magnetic hysteresis loop detected at 4 K, shows remanent magnetization and coercive force also which indicats little ferromagnetic. Finally, we investigated the magnetotransport properties,


and observed negative colossal magnetoresistance reaching 2.5×102 and semiconducting behavor in compound of Y2CrS4. The activation energy was deduced from the thermally activated behavior （ρ=ρ0exp(E/kBT)）due to a mobility edge, fitting the corresponding In ρ curve in the 30-270 K reciprocal temperature range, E=33.6 meV. The reduction of spin-disorder scattering must be responsible for negative colossal magnetoresistive effect which is enhanced for low charge carrier densities possibly.

* Supported by National Basic Research Program of China (2010CB833102), and National Natural Science Foundation of China (10974244)

Study on Different Forms of Calcium Metabolic Behavior in Normal and Osteoporosis Rats by 41Ca Tracing

DOU Liang1, JIANG Shan1, HE Ming1, DONG Ke-jun1, WU Shao-yong1, LI Zhen-yu1, LI Heng1,2,

ZHENG Guo-wen1, HU Hao1, LIN De-yu1,2, XIE Lin-bo1,3, WANG Xiao-bo1,2 (1. Department of Nuclear Physics, China Institute of Atomic Energy; 2. Guangxi University；

3. Xiamen University)

Because of calcium deficiency,there were about 90 million Chinese people suffering from osteoporosis which caused a great calcium supplement boom in 2009. However, recent studies have shown that excess calcium supplement may cause some other diseases (especially for patients with osteoporosis). So, it will be very meaningful for the study of osteoporosis, if the mechanism of calcium metabolism is clear. There are some problems for the traditional biological tracing technique, such as poor distinction of calcium between endogenous and exogenous, lower sensitivity, radioactive damage from tracer elements and high-cost, etc. The metabolic behavior of different forms of calcium in normal and osteoporosis rats will be studied by high sensitivity of the 41Ca bio-tracing technique, which can be implemented with the Beijing HI-13 AMS system and labeling endogenous calcium. By standardization of experimental design, improved detector and sample preparation programs, the disadvantage of traditional biological tracing technique can be solved completely. In our work, we will get a further study on the mechanism of calcium metablism systematically for the application in prevention and rational treatment of osteoporosis, establishing the uniform standard of reference intakes for calcium.

Discussions of Chemical Extraction Methods for Iodine-129 Determinations Using AMS System

XIE Lin-bo1, LIU Guang-shan1, JIANG Shan2, DONG Ke-jun2,

WU Shao-yong2, LI Zhen-yu2, DOU Liang2, LI Heng3, ZHENG Guo-wen2, HU Hao2, LIN De-yu3, WANG Xiao-bo3

(1. Guangxi University; 2. Department of Nuclear Physics, China Institute of Atomic Energy; 3. Xiamen University)

As the longest-lived radioisotope of iodine with a half life of 15.7 Ma, Iodine-129 is widely used as a

tracer in various environmental practices such as monitoring of nuclear environmental safety, seawater


transport, and dating of geological events. Two natural processes responsible for natural background levels of 129I are spallation of cosmic rays on atmospheric Xe in the upper atmosphere and spontaneous fission of 238U, thermal neutron-induced fission of 235U and to a lesser extent the neutron activation reactions, 128Te(n, γ)129I and 130Te(n, 2n)129I, contribute to a pre-anthropogenic steady state concentration of 129I.

Determination of 129I/I ratios by Accelerator Mass Spectrometry (AMS) requires iodine being separated from water samples, purified and precipitated as silver iodide, three chemical extraction methods are now commonly used：1) Iodine in the solution is first oxidized and extracted by organic solvent and then back-extracted. AgNO3 was added to form AgI. 2) Anion exchange resin was utilized for a pre-concentration, and followed by extraction and back-extraction. 3) The samples are acidified with nitric acid, and silver powder is directly added into the samples and kept for 48 h in sealed containers to prevent the escape of volatile iodine.

The results suggest that method 1 has relatively higher yield than the resin extraction especially when the iodine input is higher than 1 mg, the average yield for the resin extraction is very close to that of chloroform extraction when the iodine input was below 1 mg. Method 3 can be used without interference. Consequently, the chloroform extraction method is suitable.

Superheated Droplet Detector Response for Temperature

HUANG Jin-feng1, NI Bang-fa2, GUAN Yong-jing1, ZHANG Gui-ying2, XIAO Cai-jin2, LIU Cun-xiong2, WANG ping-sheng2, SUN Hong-chao2, YUAN Guo-jun2, YANG Wei1

(1. Guangxi University；2. Department of Nuclear Physics, China Institute of Atomic Energy)

Superheated droplet detector has the following advantages: Used repeatedly, recording the

cumulative dose, using both indoors and outdoors, compacting; relatively low cost, direct reading of the bubbles using the naked eye, and working in gamma-neutron mixed-field well. More and more people’s attention is paid to it.

We have studied superheated droplet detector response to temperature under the 24 and 30 . The experimental result is shown in Table 1. From the table, when the temperature rises, the detector is more sensitive to the same neutron source.

Table 1 Response to temperature

Response Number

24 30

1 20 40

2 21 38

3 18 39

4 22 37

5 23 41

6 19 36


Key Issue of Ultra-trace Environmental Samples by 236 U/238 U-AMS Method

LIN De-yu1, WANG Xiao-bo1, JIANG Shan2, HE Ming2, DONG Ke-jun2, RUAN Xiang-dong1,

WU Shao-yong2, LI Zhen-yu2, DOU Liang2, ZHENG Guo-wen2, HU Hao2, LI Heng1, XIE Lin-bo3

(1. Guangxi University; 2. Department of Nuclear Physics, China Institute of Atomic Energy; 3. Xiamen University)

The accurate determination of uranium-236 in samples at ultra-low level is critical. Combined with

AMS , reducing the background effects throughout the experiment is quite necessary. Therefore, some advances on the determination of 236U by accelerator mass spectrometry (AMS) are established: First, in order to prevent the influence of carrier uranium, we use carrier-free method to prepare 236U target; Secondly, considering the simulation transmission of 238UO－ ion may cause background interference, it’s better to use substitute 232ThO－ combined with 208PbO2

－ to simulate transmission. The magnet maximum quality product is 200 MeV/u , so terminal voltage is set at 8.3 MV to optimize the transmission into charge state 11+, and the simulation of transmission parameters is shown in Fig. 1. In this study, the accurate measurement of 236U is essential for the application of environmental monitoring studies.

Table 1 232ThO－ analog transmission parameters

Charge

state Stripping

probability /% Energy/

MeV NMR/MHz

Analysis of magnetic

field/kg Analyzing magnet

current/A Switching magnet

current/A

9+ 19.57 82.091 73.502 84 17.263 910 323.706 156.430 10+ 18.639 9 90.391 69.416 98 16.304 247 305.712 147.734 11+ 14.225 0 98.691 65.940 69 15.487 758 290.403 140.336 12+ 8.9919 106.991 59.424 85 14.957 356 277.173 133.943

Suppression Factor of 182W for 182Hf AMS at CIAE

LI Zhen-yu1, HE Ming1, JIANG Shan1, DONG Ke-jun1, WU Shao-yong1, HU Hao1, ZHENG Guo-wen1, LI Heng2, DOU Liang1, WANG Xiao-bo2, LIN De-yu2, XIE Lin-bo3

(1. Department of Nuclear Physics, China Institute of Atomic Energy; 2. Academy of Physics, Guangxi University;

3. College of Ocean And Earth Sciences, Xiamen University)

Suppression factor of 182W is an important index in the measurement of 182Hf with AMS method.

This factor is defined as the value of 182W/180Hf in blank samples divised by the measured value of 182W/180Hf with AMS method. In order to satisfy a certain requirement of measurement sensitivity, the upper limit of tungsten component in measured samples should be estimated with the suppression factor of 182W, which is important to the chemical preparation of measured samples. Research indicates that, by choosing fitted chemical form as target meterial and extraction ions in ion source, the 182W is suppressed largely. Vockenhuber found a 182W suppression of about 6 000 can be achieved using HfF5

- ions. Forstner found a 182W suppression of about 36 000 was reported in the same laboratory. In their work, the 182W


suppression is just a relative factor which is different from the defination here. So far, there is no report about the suppression factor of 182W.

In our work, the blank samples were measured by ICP-MS method and the suppression factors were calculated, where the ratio of 182W/180Hf about 1.0×10－11 with AMS method for blank samples is used. Table 1 lists the data in detail. It is shown that the suppression factor of 182W is great than 108. Thus, the suppression factor was obtained firstly in experiments. However, it’s worth noting that, the value of 182W/180Hf with AMS method is obtained by a formula:

9

1910

1.60 10'I

nRT−

−××

=⋅

Where n is the count rate of 182W, and I denotes the 180HfF5－ current. T ′ is the transmission from 180HfF5

－ current at the image side of injection magnet to the current of 180Hf9+ at the AMS target chamber.

Because the 182W count rate is unrelevant to 180HfF5－ currents as mentioned before, the suppression

factor has negative correlation with the 180HfF5－ currents. The measured value of 182W/180Hf (1.0×10－11)

with AMS at CIAE is usually the typical one (the best one). So, the suppression factor lisited in Table 1 is actually the best one.

This result is important to the chemical preparation of measured samples.

Table 1 Suppression factor of 182W calculated using the values measured by ICP-MS

Sample Weight/mg Volume/mLMeasured component of W

with ICP-MS/ppm

Component

of W/%

Calculated 182W/180Hf

Suppression

factor

NH4HF2 81.4 50 0.022 2 0.001 4 －－

HfO2(99.9%) 83.4 100 1.508 0.181 1.36×10－3 －

HfF4* 121.0 100 1.939 0.160 1.20×10－3 1.20×108

HfF4 (commercial) 111.3 100 2.335 0.210 1.58×10－3 1.58×108

Note: HfF4* was obtained by multiphase synthesis from NH4HF2 and HfO2

Study on Different Samples in Measurement of Manganese-53 With AMS

HU Hao1, HE Ming1, JIANG Shan1, DONG Ke-jun1, WU Shao-yong1, ZHENG Guo-wen1, LI Heng2, XIE Lin-bo3, LIN De-yu2, WANG Xiao-bo2

(1. Department of Nuclear Physics, China Institute of Atomic Energy; 2. Guangxi University; 3. Xiamen University)

53Mn is mainly produced by nuclear reaction of cosmic rays on iron with a half-life of 3.7 Ma.

Because it has the potential to allow dating test range to >10 Ma, it is a very useful nuclide to determine various geomorphological parameters (such as exposure ages, erosion rates and so on) and achieve a further study on deep-sea manganese nodules.

We got standard samples with 53Mn/55Mn ratio 2.83×10－9 from the Munic group, and we prepared 53Mn target with three different levels, 4.34×10－10, 4.47×10－11 and 4.83×10－12 using chemical dilution (Fig. 1).

As mentioned in previous papers, using MnF－ ions can depress the isobar 53Cr, then chemical treatment on MnO2 is obtained to generate MnF2. The Manganese oxides were mixed with pure Ag


powder at ratio 1︰2 by weight, dissolved in conc. HF, and dried down at 100 .

Fig. 1 Chemical dilution

In our work, we have tried different sample forms and extraction ion forms to find out that MnF－,

instead of MnO－, can bring about a reduction of 53Cr interference by a factor of 2-3 (Table 1). So we consider using standard samples to extract MnF－ in future.

Table 1 Sample forms and extraction ion forms

Blank sample (Extraction) 53Mn counts 53Cr counts Measurement time/s 53Cr/ 53Mn counts rate

MnO2(MnO－) 203 601 620 1 800 2 963.6

MnO2+PbF2(MnO－) 127 363 845 1 800 2 864.9

MnO2+PbF2(MnF－) 11 14 007 600 1 273.4

MnF2(MnF－) 24 34 377 600 1 432.3

Design of Stopper of Prompt Gamma Neutron Activation Analysis Facility at China Advanced Research Reactor

SUN Hong-chao1, NI Bang-fa1, XIAO Cai-jin1, ZHANG Gui-ying1,

HUANG Jin-feng2, YUAN Guo-jun1, YANG Wei2 (1. Department of Nuclear Physics, China Institute of Atomic Energy; 2. Guangxi University)

The PGNAA facility consists of the filtered collimated neutron beam, the shielding of the whole

facility, the control system, the detecting equipment and the data acquisition and analysis system. The neutron beam is filtered by a mono-crystalline bismuth filter, which is deposited in the shutter. An outside collimator can further restrict the beam. After the sample is irradiated by the neutron beam, the stopper will moderate and absorb the neutron. The detecting equipment is placed perpendicular to the beam. The data will be analysis by some software. The chopped neutron beam can further expand the application of the PGNAA facility.


Beam stopper The beam stopper contains a 20 cm length, 14.4 cm diameter cylindrical recess which is lined with 6Li-loaded polymer to eliminate the low energy component of the neutron beam. The cylindrical recess is put into the borated polyethylene cubes, 30 cm each sided which are surrounded by 10 cm thick Lead. The simulation results show that gamma rays and neutrons escaped from the surface of the shielding are just 69 cm－2·s－1 (γ) and 22 cm－2·s－1 (n), respectively. Fig. 1 is the plan of stopper.

Fig. 1 Plan of the stopper

Three types of beam stopper were designed, as displayed in Fig. 2. Among them, the c-type stopper

should have the least contribution to background in theory, which is confirmed by the MCNP simulation results. On the cross-section of the beam tube 30 cm away from the stopper, the intensities of gamma rays back-reflected from the stopper are 20, 21 and 15 cm－2·s－1 (γ) for these three types of beam stopper a, b and c, respectively. However, in order to ensure gamma rays and neutrons escaping from the surface of the stopper shielding is small, we have to enlarge the volumn of the c-type stopper to insure the shielding materials are thick enough on each side because of the larger recess. After a comprehensive consideration of weight, volume, machinability, cost of the stopper and the effectiveness in lowering background, the a-type stopper is finally selected.

Fig. 2 Three types of stopper

Type a with a cylindrical recess, type b with a truncated cone recess, type c with a cavum


Preliminary Study on the Determination of 235U and 239Pu Using Delayed Neutron Counting Method

ZHANG Gui-ying1, XIAO Cai-jin1, YUAN Guo-jun1, SUN Hong-chao1, NI Bang-fa1,

TIAN Wei-zhi1, WANG Ping-sheng1, LIU Cun-xiong1, HUANG Jin-feng2, YANG Wei2 （1. Department of Nuclear Physics, China Institute of Atomic Energy; 2. Guangxi University）

The preliminary study on the fast measurements of 235U and 239Pu in samples containing 235U, 239Pu

and 235U-239Pu mixture using delayed neutron counting method is introduced. All samples were irradiated for 30 s using the 30 kW Miniature Neutron Source Reactor at China Institute of Atomic Energy, cooled for 2 s, and counted for 100 s using a delayed neutron detector. The detection limits of 235U and 239Pu are 0.14 and 0.18 μg for samples containing 235U and 239Pu, respectively. The detection efficiency for delayed neutrons is 0.013 00±0.000 25. The relative standard deviation of 235U and 239Pu are 0.8% and 6.9%, respectively, for a 235U-239Pu sample with the mass ratio of 235U over 239Pu, m(235U)/m(239Pu), of 1.2.

Radiation Effect of CLAM Steel by Triple Ion Beams Irradiation*

ZHENG Yong-nan1, ZHANG Peng2, ZUO Yi1, FAN Ping1, ZHANG Qiao-li1, CHEN Li-hua1, ZHOU Dong-mei1, MA Rui-gang1, CAO Xing-zhong2, CUI Bao-qun1,

JIANG Wei-sheng1, WANG Bao-yi2, YUAN Da-qing1, ZHU Sheng-yun1 (1. Department of Nuclear Physic, China Institute of Atomic Energy；2. Institute of High Energy Physics)

The CLAM steel is a self-developed low activation martensitc steel of china. Its alloy composition is Cr-8.91%, W-1.44%, V-0.20%, Ta-0.15%, Mn-0.49%, C-0.12%, S-0.003%, Si-0.29% and Fe balanced to 100%. This steel is considered as one of the candidate structural materials for the new system of nuclear facilities.

The CLAM steel samples used in the experiment were φ15 mm×0.5 mm and mechanically polished to a mirror-like surface. They were irradiated by the 70 MeV gold ions, 100 keV hydrogen ions and 200 keV helium ions simultaneously from the triple beam facility at China Institute of Atomic Energy. The distribution of displacement damage, hydrogen and helium calculated by SRIM program, is shown in Fig. 1. And the irradiated dose is given in Table 1.

Table 1 Irradiation dose

Ion Energy Dose 1/ cm－2 Dose 2/ cm－2

Hydrogen 100 keV 2.42×1016 4.84×1016

Helium 200 keV 7.89×1015 1.66×1016

Gold 70 MeV 5.37×1013 1.07×1014

The radiation damage is studied by the slow positron Doppler broadening technique on irradiated and

unirradiated samples. The S and W parameter was used to analyze the positron Doppler broadening


spectrum since the S parameter increasees and W parameter decreases when the defects become rich, they can be used to characterize various defects.

Fig. 1 Displacement damage (x) and atomic concentration (y) of hydrogen and helium

Fig. 2 Variations of S and W parameter with positron energy

In this experiment, the energy of slow positron ranges from 0.18 to 20 keV. The dependences of S

parameter and W parameter on positron energy are shown in Fig. 2 for the unirradiated and triple beam irradiated samples. It can be seen from Fig. 2 that the S parameter and W parameter quickly change when the positron energy was in low energy area. This result is due to the surface effect. With the irradiation dose increasing, the S parameter increases and the W parameter decreases. And as the energy of the positron increases, the S parameter and W parameter gradually close to the value of the unirradiated sample



Investigation of H-Pd, H-PdAg and H-PdY Alloy Systems by Positron Annihilation Lifetime Spectroscopy

ZUO Yi, ZHENG Yong-nan, HU Yong, FAN Ping,

YUAN Da-qing, ZHOU Dong-mei, ZHU Sheng-yun （Department of Nuclear Physics）

In present work the defects induced by hydrogen in Pd, Pd0.75Ag0.25 and Pd0.92Y0.08 (in weight) were

investigated as a function of hydrogen concentration by the positron annihilation lifetime method. The Pd, Pd0.75Ag0.25 and Pd0.92Y0.08 (in weight) samples were all annealed before hydrogen charging.

The hydrogen charging of the samples were carried out with a hydrogen charging device, the hydrogen concentrations (in weight) were 0, 0.2, 0.35, 0.55 for the Pd samples; 0, 0.11, 0.23, 0.3, 0.35 for the Pd0.75Ag0.25 samples and 0, 0.16, 0.24, 0.3, 0.38 for the Pd0.92Y0.08 samples.

The positron annihilation lifetime spectra were measured with the positron annihilation lifetime spectrometer. Two lifetime components τ1 and τ2 were used to fit the measured lifetimes for the Pd and Pd0.75Ag0.25 samples, and for the Pd0.92Y0.08 samples only one lifetime component τ was used.

Fig. 1 and Fig. 2 shows the positron lifetimes τ1 and τ2 for the Pd, Pd0.75Ag0.25 samples and positron lifetime τ for Pd0.92Y0.08 samples as a function of hydrogen concentration x. The intensities I2 of lifetimes τ2 as a function of H concentration x in the Pd and Pd0.75Ag0.25 were illustrated in Fig. 3.

Fig. 3 shows that the lifetime τ2 increases with the increasing of hydrogen concentration x, indicating the size of defects in the Pd and Pd0.75Ag0.25 samples increases with the hydrogen concentration x. Fig. 2 shows that the intensity I2 first increases and then decreases, indicating that at first the density of the produced defects increases and then decreases with the hydrogen concentration. The decrease of the defect density means that the defects are combined into bigger size defects.

For the Pd0.92Y0.08 alloy samples, the lifetime was well fitted by only one lifetime component, which approaches to the bulk lifetime. This result clearly illustrates that almost no defects are produced in the Pd0.92Y0.08 alloy samples.

Fig. 1 Positron lifetimes τ1 for Pd, Pd0.75Ag0.25 and lifetime

τ for Pd0.92Y0.08 as a function of hydrogen concentration x Fig. 2 Positron lifetimes τ2 for Pd, Pd0.75Ag0.25 and lifetime

τ for Pd0.92Y0.08 as a function of hydrogen concentration

The present results demonstrate that hydrogen charging created the defects in the Pd and Pd0.75Ag0.25 samples, the defect size in the Pd samples increases much faster than that in the Pd0.75Ag0.25 alloy samples and the size of the defects is larger in H-Pd than that in H-PdAg. No defects were produced by hydrogen


charging in the H-Pd0.92Y0.08 alloy samples. The Pd0.92Y0.08 alloy has the most excellent hydrogen embrittlement resistance property, and the Pd0.75Ag0.25 alloy shows a better resistance property compared with the pure Pd metal. The present results show the suppression of the defects by adding Y with a weight percent of 8%.

Fig. 3 Intensity I2 of lifetime τ2 as a function of hydrogen concentration x for Pd and Pd0.75Ag0.25

A SSS Spectrometer

LIU Yi-na, WANG Zhi-qiang, LUO Hai-long, LI Chun-juan, ZHANG Wei-hua (Radiation Metrology Division)

The SSS spectrometer, so called simple scintillation spectrometer, is made by BTI (Bubble

Technology Industries). The spectrometer can be used in the neutron energy range from 4.0 to 17 MeV. The SSS includes two sections: A probe and an analyzer module, MICROSPEC-2. The probe

contains a neutron detector, a photomultiplier, a light pulser driver, and a high voltage supply. The neutron detector is an array of small plastic scintillators, which dimensions have been selected by optimizing the neutron response function and the sensitivity of gamma radiation. The light pulser can be used to check the system. The MICROSPEC-2 includes a shaping amplifier, an analog-to-digital converter, a display, a keyboard, and a power supply. The software included in MICROSPEC-2 can automatically unfold the energy spectrum and acquire some dose information.

The photograph of the spectrometer is shown in Fig. 1.

Fig. 1 Spectrometer and MICROSPEC-2

Fig. 2 Test result of the spectrometer


The SSS spectrometer had been tested in 14.8 MeV monoenergetic neutron field produced by the T(d, n)4He reaction. The distance of the surface of the probe to the target is 20 cm. the measured neutron spectrum is shown in Fig. 2. In the measured neutron spectrum, a few scattering neutrons can be seen. The energy resolution for 14.8 MeV neutrons is about 10.1% which is better than the result of 15% provided by BTI.

The SSS spectrometer has been used in the establishment of a simulated workplace neutron fields.

Construction Design of Tissue-Equivalent Proportional Counter

ZHANG Wei-hua, LIU Yi-na, WANG Zhi-qiang, LI Chun-juan, LUO Hai-long

(Radiation Metrology Division)

Mechanical and electrical design of tissue-equivalent proportional counter is strongly interdependent. Each aspect of design places restrictions on the other, such as the selection of materials, detector reliability, performance characteristics, and assembly. The primary concern in mechanical and electrical design must be requirements of the detector application. The electrical design could be considered first, then it will be followed by mechanical design, each component materials, and fastening techniques. In order to optimize design, several characteristics should be preferred to consider, such as resolution, gain stability, noise and cost.

According to the foregoing review and primary study, there are usually three configuration designs: 1) In order to restrict the end electric field distortion near the end of anode wire, a helix should be held around the anode wire; 2) There are field tubes held at the ends of anode wire so that the distorted electric field lines will end on the field tubes rather than the anode; 3) There is a new method to establish a uniform electric field without the conventional field tubes, which is illustrated in figure 1. In this design, blue material is an insulator disc which partially compensates for the higher field at the end of anode, which work the same as the extension of the anode expansion tube (Fig. 1). The extension length of the expansion tube in the sensitive volume is a critical dimension that determined the overall uniformity of the electric field.

Fig. 1 Schematic diagram of the anode wire support system

Because of the complexity to hold a helix around the anode or to place field tubes which needed to add a voltage dividing resistance, the third design would be chosen.


Manufacture of Single 60Co Source Irradiation Facility

GAO Fei (Radiation Metrology Division)

Reference radiation filed produced by isotope source is necessary for calibration of radiation dose meter. According to the GB/T 12162.1-2002 “X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of phonton energy Part 1: Radiation characteristics and production methods”, there must be different activity isotope sources (for example: 60Co, 137Cs and 241Am etc.) in order to build different reference radiation filed.

The single source radiation facility is made up of shield, scatter cavity, collimation and shutter. The lead shield should be strong enough thick to hold a 60Co isotope source whose activity is 20 Ci and the leaked dose rate is less than 25 μGy/h on the surface of the facility. The analytical method and the Monte Carlo method were used to study the characteristics of the irradiation facility and calculate the thickness of the lead shield.

The results indicate that, 27 cm lead shield is thick enough to hold a 60Co source. So the thickness of the single irradiation facility is designed as 27 cm. As Fig. 2, a column whose dimension is φ80 mm×

100 mm is designed in the facility in order to reduce the scattered dose.

Fig. 1 Single 60Co source irradiation facility plotted by MCNP

Fig. 2 Single 60Co source irradiation facility

Recent Progress in Research on Microcalorimeter for Radioactivity Measurement of Tritium

CHEN Xi-lin, HE Chang-shui, XING Jian-sheng, HOU Shi-gang, YANG Hong-guang, YANG Qi-fa


A twin-cup heat-flow microcalorimeter is ongoing development for tritium measurement in frame of programme of TBM online production, measurement and analysis of tritium. In order to maintain stable temperature in the calorimeter cell, a vacuum system is constructed outside the calorimeter cell. Semiconductor sensors were used to measure the temperature difference between the sample cup and the


reference one. A computer is used to automatically record the measured data of temperature difference measured by a nano voltmeter and electric powers output by two DC sourcemeters. The software can dynamical alter the power on the reference cup by comparing the difference of the temperature between the two cups until an electric power is reached that can keep the temperature difference permanently close to zero.

At present, we just finish the design and manufacture of calorimeter setup in this first year, the detailed test experiments will be carried out in the next year.

Recent Progress in Liquid Scintillation Counting System for Absolute Radioactivity Measurement

LU Xiao-xia, CHEN Xi-lin, YAO Shun-he


The triple to double coincidence ratio (TDCR) method is an absolute activity measurement method in liquid scintillation counting, especially developed for pure β- and EC-emitters activity standardization. Such a liquid scintillation counting system is now on development at CIAE. Here is a report on the progress in 2011.

The basic block diagram of the electronics is shown in Fig.1. Three photomultiplier tubes are inserted into the cylindrical optical chamber spaced at 120° as shown in Fig. 2, the detection unit is positioned in a cylindrical lead shield to reduce background. Signals from three PMT anodes are sent to pre-amplifiers, discriminators and coincidence units, an integrated circuits unit functions as AND/OR gates. The outputs from this coincidence unit are the three single count rates, NA, NB and NC , three double coincidence count rates NAB, NBC and NCA , their logic sum ND and a triple coincidence count rates NT. The detection efficiency can be varied by changing the focusing potential on PMTs, which results in several efficiency points for each sample. The detection efficiency for triple coincidence εT and double coincidence logic sum εD is calculated from a physical and statistical model, and the radio activity A is calculated by A=ND/εD=NT/εT.

Fig. 1 Diagram of electronic system


Fig. 2 Schematic diagram of TDCR system

1—Optical chamber; 2—PMT; 3—Lead shield; 4—Sample changer; 5—Shutter

The whole setup was nearly completed in 2011. More experiments will be carried out in the coming

year.

Design of Radioactive Reference Barrels and Simulation Verification of Linear Source

XU Li-jun, YE Hong-sheng, LIN Min, XIAO Xue-fu


Shell source method was used to prepare radioactive reference barrel for the calibration of gamma scan device because filling method in normal ways produces “hot” points easily and decrease the safety in transportation of the barrel. The construction of the barrel was designed to make the radioactive source independent of barrel pack. The linear source was comprised of six ampoules, which hold same radioactivity of 152Eu aqueous solution. Different distance from the center of the barrel was reserved for the linear source, which can calibrate the gamma scan device in the method of shell source.

To verify the filling material, the construction of the linear source and the radioactivity of the reference barrel, calculation were made in two common Monte-Carlo packages of MCNP and FLUKA (Fig. 1). To simplify the simulation, only one ampoule of 152Eu solution in the center of the barrel was considered. The deviation of two results was 1%-7%, which can be referred in the further.

Fig. 1 The simulation result of Monte-Carlo


Study of Preparation of Large Area Standard Source

LIN Min, YE Hong-sheng, XIA Wen, YU Zheng-wei, CHEN Ke-sheng (Radiation Metrology Division)

With increasingly widespread application of nuclear technology, many large area contamination

detectors are used to measure the contaminated surface by α, β radionuclides in nuclear facilities and isotope production places. To solve the calibration problem of these detectors, a kind of large area source preparation device was designed and established, which was based on the conventional molecular plating and brush plating technology.

With controllable and well-regulated movement of a small anode operated by an automatic 2D travelling equipment, the uniformity problem of the large area source was effectively resolved. Some experimental parameters that influenced the deposition efficiency, such as deposition time, voltage and acidity of the solution, were investigated for preparation of large area 241Am source. The optimum experimental parameters were determined, which is 40 min for deposition time, 800 V for the voltage between the anode and the cathode, and 3.2×10－4 mol/L for the acidity of the solution, respectively.

With above determined optimum parameters, a batch of 241Am source was prepared. Among these sources, 5 pieces were picked out randomly for homogeneity measurement. A special bracket was designed with 9 holes on it with reference to the appendix B of JJG 788-1992. A calibrated surface contamination detector was used to check the homogenity of the sources. To assure of the reliability of the results, 5 times of measurement were performed to get the average value. Based on 9 average values of the counts, homogenity of each source was calculated, which are all better than 10% (seen in Table1).

Moreover, this device has been applied to preparation of 90Sr-90Y and 204Tl standard sources with active area of 100 mm×150 mm.

Table 1 Results of homogeneity measurement

Counts No.

1 2 3 4 5 6 7 8 9 Average u/%

1 752.3 722.7 721.7 758.7 754.3 769.7 726.3 717.0 714.7 737.5 2.8

2 527.7 571.7 610.7 522.7 518.7 616.0 657.7 617.3 637.3 586.6 9.0

3 704.3 715.7 771.7 749.3 713.3 684.3 755.0 781.3 710.7 731.7 4.6

4 702.3 866.0 807.3 865.7 777.7 703.0 799.7 857.7 796.0 797.3 7.9

5 659.7 731.0 790.0 760.0 738.3 684.0 788.7 787.3 820.3 751.0 7.1

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·High Power Laser and Accelerator 111

High Power Laser and Accelerator

Development of Nanosecond Short Pulse High Power KrF Laser System

GAO Zhi-xing1, XIANG Yi-huai1, TANG Xiu-zhang1, SZATMAR Sador2, BOHUS Janos2

(1. Department of Nuclear Technology Application, China Institute of Atomic Energy;

2. Department of Experimental Physics, University of Szeged)

Compression of short pulse laser is demanded by the physical experiments such as EOS for Heaven-I

system. A nanosecond short pulse high power discharge pumping excimer laser system was developed under the frame of Science and Technology cooperation between China and Hungary to take the place of LPX-150, which has worked as the front end for a decade.

The laser system consists of two part: a laser quenched ASE pulse seed named Variex and a high gain pulse amplifier. The varied pulse width excimer laser (Variex) has two separate channels. Both charging circuit is controlled by one thyratron and one common distributed magnetic switch to achieve a stable synchronization of the channels.

The Full width at half maximum of laser pulse from Variex can be compressed from 20 ns to 6-9 ns with laser quenching. Several mJ ASE pulse with a pulse width of 7 ns was achieved with Variex laser in ASE mode, Typically. A laser pulse encoding technique with beam polarizer was investigated for the short pulse laser amplification.

Experimental Study on Planarity of Shock Waves Driven by High Power Eximer Laser Pluses

LIANG Jing, TIAN Bao-xian, LI Ye-jun, WANG Zhao

(Department of Nuclear Technology Application)

For the two types of targets in these experiments, a one-dimension three-temperature hydrodynamic

simulation code HYADES was used to optimize the target parameters and to make sure the results of two types of targets can be compared with each other. Two sweep grades of the streak camera, 25 ns and 100 ns respectively, were calibrated, data recorded by them were compared with each other. Planarity of shock waves driven by high power excimer laser pulses in the single planar target and in the flyer planar target was measured respectively. Shock waves driven by lasers directly were more planar than those driven by the flyer indirectly. The results of planarity given by the faster sweep grade were better than those given by the slower one. The edge effects were reduced in faster one.


Energy Spectrum of Protons Driven by Ultra-short Laser Interaction With Thin Gold Foils

LU Jian-xin, LAN Xiao-fei, HUANG Yong-sheng, WANG Lei-jian,

XI Xiao-feng, TANG Xiu-zhang, YANG Da-wei (Department of Nuclear Technology Application)

Proton acceleration experiments by irradiation of an ultra-short laser with gold foils of 5 and 2.1 μm

thickness were investigated. The laser system produced pulses having energies of up to 11 mJ at a wavelength of 744 nm with a temporal duration of 120 fs, and the peak focal intensity remains around the 6×1016 W/cm2. A Thomson parabola ion spectrometer with CR39 plastic nuclear track detectors were used to observe spectra of the accelerated protons. The maximum energies and efficiencies of accelerated protons increased with decreasing the target thickness. These results were explained by energy loss and a geometrical effect on hot electron recycling.

Proton energy spectrum from ultra-short laser interaction with a 2.1 μm gold foil is shown in Fig. 1.

Fig. 1 Proton energy spectrum from ultra-laser interaction with 2.1 μm gold foil

Influence of Laser Prepulse in Ultra-short Laser-Driven Proton Acceleration

LU Jian-xin, LAN Xiao-fei, XI Xiao-feng, WANG Lei-jian, HUANG Yong-sheng, YANG Da-wei, TANG Xiu-zhang


Influence of laser prepulse in ultra-short laser-driven proton acceleration was investigated by the differences in spatial distribution and energy spectrum between different foil-targets. The laser system produced pulses having energies of up to 11 mJ at a wavelength of 744 nm with a temporal duration of 120 fs, and the peak focal intensity remains around 6×1016 W/cm2. Proton amount increased with decreasing the target thickness, but the divergence angle also increased with decreasing the target thickness as a result of the target surface-shape destroyed by the laser prepulse. The energy spectrums recorded by a Thomson ion spectrometer were also influenced by the decrease of hot electron recycling attributed to the destroyed surface-shape. The divergence angles are shown in Fig. 1.


Fig. 1 Divergence angels of different target thickness induced by laser prepulse

Proton Acceleration Drived by High-intensity Ultraviolet Laser

LU Jian-xin, LAN Xiao-fei, HUANG Yong-sheng, XI Xiaofeng, DAI Hui, WANG Lei-jian, YANG Da-wei, TANG Xiu-zhang


The generation of energetic protons from a solid thin-foil by the interactions of ultra-short and intense laser pulses is investigated in numerous experiments in the last decade. The energetic proton beams are promising candidates for proton fast ignitor (PFI) , which offers effective control of the ignition beam production and transport as well as high efficiency of the beam energy deposition in the fuel. The parameters of the proton beam for the PFI are as follows: beam intensity of about 1020 W/cm², proton pulse duration of 10-20 ps, mean proton energy of 3-5 MeV. Two methods of proton acceleration driven by intense laser interaction with thin foil targets are usually used：target normal sheath acceleration n(TNSA) and radiation pressure acceleration (RPA). Proton energy can match the PFI requisition but the beam intensity still requires great efforts make great.

Some particle-in-cell simulations show that a short-wavelength short-pulse laser driver can produce much more intense ion beams than the commonly used long-wavelength ones. Proton acceleration induced by a high-intensity ultraviolet laser interaction with a thin foil target was studied on an ultra-short KrF laser amplifier called LLG50 in CIAE. The ultraviolet laser produced pulses with high-contrast of 109, duration of 500 fs and energy of 30 mJ. The p-polarized laser was focused on a 2.1 μm gold foil by an off-axis parabola mirror at an incient angle of 45°, and the intensity was 1.2×1017 W/cm2. The maximum energy was 400 keV higher recorded by a CR39 detector covered with a 4μm aluminum foil. The ultraviolet laser acquires relatively low hot electron temperature ascribed to the proportional relation of Iλ2, but a higher electron density because of the higher laser absorption and laser contrast.

Plasma Expansions With Time-Dependent Electron Temperature

HUANG Yong-sheng, WANG Nai-yan, TANG Xiu-zhang


The fundamental of ion acceleration from the laser-solid interactions is the theory for describing


plasma expansions into a vacuum. In the time interval of tens of femtoseconds after the laser pulse reaches the target, the plasma reaches local-thermal equilibrium and then hydrodynamic equations are available. However, it cannot reach macro-thermal equilibrium and does not satisfy Boltzmann distribution. The plasma is non-quasi-neutral and a strong charge separation exists. In fact, the electron temperature is time-dependent and the changing law is governed by the energy transfer between electrons and ions.

In this paper, an analytical solution is obtained for plasma expansions into a vacuum to describe the ion acceleration with a time-dependent electron temperature. It is obtained that the dependence of the plasma density on the potential is different from Boltzmann distribution in the time-dependent case. The time-dependent electron temperature also induces the unsteady ablation rate of the ablation plane, which is defined as the interface between the plasma and the solid (or liquid or gas). The electric field is also obtained and discussed in detail.

The particular solution is given to show the influence of the time-dependent electron temperature on the laser-ion acceleration in a particular case: the electron temperature is proportional to the square of time. From that, it is concluded that laser-ion acceleration is more efficient in the time-increasing electron-temperature case than that in the isothermal case. The time-dependence of electron temperature comes from the time-dependence of laser intensity and induces the different efficiency of the laser-ion acceleration. At the ablation plane, the electron density and velocity are also predicted and explained.

Investigation of Isotope Separation Utilizing Spontaneous Magnetic Field of Ultra-Short Laser Pulses

LI Ye-jun


A piece of boron (B) film grows on copper (Cu) floor along the normal of B target in the interaction of solid B target with Infrared laser of 120 fs pulse duration and 7 mJ energy. Analyzing B isotope distribution on Cu floor by SIMS (second ion mass spectrum), measuring results show the spontaneous magnetic field separated B isotope in interaction of ultra-short laser pulse with B plasmas. Enrichment factor of once is about 33%. According to enrichment factors, spontaneous axial and toroidal magnetic fields generated within laser-induced plasmas come to MG level. Boron enrichment ratio is shown in Fig. 1.

Fig. 1 Boron enrichment ratio


Calculation for Improvement of 350 keV Electron Accelerator

LI Jin-hai (Department of Nuclear Technology Application)

The main problem of the 350 keV electric accelerator is that the accelerator can not output 20 mA for a long time otherwise the vacuum become bad. The reason is that part of the beam bomb on the scanning box and increase the temperature immediately, and then lots of gases and particles are released.

We first simulate the beam envelope by PBGUN code according to the mechanical structure. The calculation result show that the beam halo is induced by the nonlinear field of the electron gun and it is very difficult to focus and control. The beam loss on the scanning box is part of the beam halo. Moreover, the beam spot at the output of the accelerator is too large because the accelerator is too long and then the focus strength is not enough.

Two methods are used for the improvement. Firstly, the shape of the cathode plane is change for less nonlinear effect and the beam halo is not appeared any more. Secondly, the beam spot at the output of the accelerator decrease after the permanent magnetron provide more focus strength.

Research of Elements for Beam Redistribution

LI Jin-hai, REN Xiu-yan (Department of Nuclear Technology Application)

Particle beams with uniform and well-confined intensity distributions are desirable in some high power beam applications to prolong the target lifetime or to improve the beam utilization. Three kinds of elements had been proposed for the beam homogenizing, such as octupole, pole-piece magnet, and step-like nonlinear magnets. We proposed the new type of elements called heteromorphic quadrupole and focus sextupole for the beam redistribution. The Gaussian-like multiparticle beam redistribution by the octupole, heteromophic quadrupole, step-like nonlinear magnets, and focus sextupole has been simulated by the POISSON and LEADS code. The best redistribution result is obtained by the focus sextupole, and one of the solutions of redistributing beam with big halo can be that of using the focus sextupole and the heteromorphic quadrupole.

Dynamics Calculation of CH-DTL

LI Jin-hai, MA Yan-yun (Department of Nuclear Technology Application)

CH-DTL is a new development of accelerator structure, which has high shunt impedance and simple structure. The beam dynamics of CH-DTL is based on KONUS method, whose characteristic is that the


longitudinal focus is small or none, the transverse defocus is small and the bunch is accelerated at 0 synchronous phase which induce the high microwave utility efficiency.

According to other article, we design and calculate a CH-DTL cavity, which is divided into two parts. There are 11 accelerator gaps in the first part, and 12 gaps in the second part. Three quadrupoles are arranged between the two parts for transverse focus. The E-M field calculated by CST is import into TraceWin. The cavity is about 1.6 m and accelerates the proton from 3 to 7 MeV. The main problem of the calculation is that the beam emittance increase too large.

Dynamics Calculation of Spoke

LI Jin-hai, MA Yan-yun


Compared with ellipse cavity, the spoke cavity has many advantages, especially for the low and medium beam energy. It will be used in the superconductor accelerator popular in the future.

Based on the spoke cavity, we design and calculate an accelerator from 7 to 600 MeV. Five type structures are used, such as 0.14, 0.21, 0.33, 0.47 and 0.63 structure. The 0.14 structure is used to accelerate the proton from 7 to 15 Mev, the 0.21 structure is to 40 MeV, the 0.33 structure is to 100 MeV, the 0.47 structure is to 200 MeV, and the 0.63 structure is to 600 MeV. The dynamics calculation result is good, and the self focus of high energy accelerator structure is found.

Dynamics Calculation of Travel Wave Tube

LI Jin-hai, MA Yan-yun, GUO Xing-kun


During the dynamics calculating of the travel tube, we must obtain the field map in the tube. The field map can be affected by not only the beam loading, but also the attenuation coefficient. The calculation of the attenuation coefficient is that the dispersion curve is calculated first, and then the velocity can be obtained, at last the attenuation coefficient can be obtained by Q value of the resonance cavity. To calculate the dispersion curve, only two modes are needed, but the number of the cavity mode is infinite in theory. There is a question: are these dispersion curve obtained by different mode identical? The results show that they are not identical. The reason is that the dispersion curve is a kind of approximation. So, when we calculate the attenuation coefficient, the two frequencies are more adjacent, the result is more accurate.

After obtaining the attenuation coefficient, we can take the dynamics calculation. The input power of microwave is 4.6 MW. The different beam energy can be obtained by changing the input beam current. The output beam energy is inverse proportion with the input beam current. Output beam power is proportion with the square of input beam current. Output beam power is greatest when output beam energy is about 6 MeV.


Calculation of Uniform of Beam Scanning

LI Jin-hai


For the electron beam application, it is always scanned by a dipole magnet. The uniform of the scanning has great influence for some application, such as the irradiation of the thyristor. There are two methods for improving the scanning uniform: the first is to improve the drive waveform of the scanning magnet, the second is to improve the magnet field or the margin field of the magnet.

According to the calculation, the effect on the scanning uniform of the triangle waveform is same with that of the exponent waveform. So it is no effect to change the time coefficient of the exponent waveform. Because the beam spot is too large, the cost is too large if we improve the magnet field or the margin field of the magnet. The proper method is to design the drive waveform as the superposition of the triangle waveform and the sine waveform. We propose a new superposition method, which is easy for not only the circuit but also the tuning of the ratio between the two waves, so it is very convenient for the beam commissioning.

Design of Cavity for 10 MeV Electron Irradiation Accelerator

MA Yan-yun1, HATTORI T2, PENG Zhao-hua1, LI Jin-hai1 (1. Department of Nuclear Technology Application, China Institute of Atomic Energy;

2. Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology)

This article describes the 10 MeV high-power electron irradiation accelerator. This accelerator can output varied energy electron beam which the highest energy is 10 MeV or shooting target produce X-rays for industrial radiation processing.

The main accelerating cavity has been simulated by CST MICROWAVE STUDIO. The accelerating principle is different from the usual S-band (2.856 GHz) 10 MeV accelerator. The accelerating cavity equipped with two ridge-type electrode which mounted opposite. Along the radial direction of ridge electrode there is the beam channels. Deflection magnets set up outside of the cavity. Electron beam injected along the channel into the cavity. There is the accelerating field between the ridge electrodes. After accelerated by the field, electron beam drift out of the cavity. Then the electron beam deflected back to the cavity by the 180° magnet. In the appropriate phase the electron beam is injected into the cavity again, and so forth, according to the number of bending times, availability of different energy electron beam.

Cavity design is optimized with CST in order to reduce the maximum electric field, increase shunt impedance and Q factor.


Research of Quick-Response Protective System for Klystron of Multi-Energy Electron Linac

TU Rui, WU Qing-feng, ZHU Zhi-bin, WANG Xiu-long


Multi-energy electron linac could be widely used in nondestructive testing, vehicle inspection, industrial

irradiation and other fields. One of its key components is a klystron which is very expensive. In commissioning or operation, the wave-guide window of the klystron may be breakdown while terminal load matching badly or sparking in waveguide. Once the internal klystron is exposed to the atmosphere in the working condition, cathode material, heater and the surface of bunching section will be rapidly oxidized, which causes permanent damage to the klystron. Therefore, a vacuum protector, arc arrester or short pulse protecting device is usually applied to protect the klystron. But these measures have some shortcomings, such as their response time being not fast enough, unstability, etc. A quick-response protective system for the klystron of multi-energy electron linac protects the klystron by monitoring the VSWR, which makes response time less than 3 micoseconds and enhances anti-jamming capability. This system laid the foundation for the safe operation of multi-energy electron linac.

UHV Vacuum System R&D of Multi-energy Electron LINAC

YIN Meng, HAN Guang-wen, HUANG Jun (Department of Nuclear Technology Application)

The multi-energy electron LINAC was an experimental device developed for irradiation metrology, the

vacuum system is a main part of the device to maintain a low pressure. The accelerator tube is made of copper and the vacuum chamber is almost entirely made of stainless steel.

The vacuum system is completely oil free and most of the vacuum components are all metal type. The main goal of the vacuum system is to maintain a mean pressure of 5×10－5 Pa.

The design of the pumping system is optimized in order to install the required pumping speed at the required position. Four sputter ion pumps are used. They are the sputter ion pump near the exit of the klystron, the sputter ion pump near the entrance of the accelerating tube, the sputter ion pump near the exit of the accelerating tube and the sputter ion pump on the scan horn. There is also prepump jaw and vacuum gauge on the system. And a gate separates the accelerating tube and the follow system when the titanium foil is changed.

The system is running very well and the LINAC is under testing now.

Self Shielding System R&D of 350 keV High-Voltage Electron Accelerator

YIN Meng, HUANG Jun, HAN Guang-wen (Department of Nuclear Technology Application)

A 350 keV high-voltage electron accelerator was developed for irradiation of plastic film products. The


accelerated electron beam is extracted into an atmosphere through the titanium outlet window to the plastic films on the pipeline. For the X-ray beam is harmful to human body, it should be shielded.

To achieve the miniaturization of high-voltage electron accelerator, we designed a self shielding system mainly made up of lead. For the lead is very soft, it was enveloped by steel. The self shielding system consisted of six boards to shield the X-ray beam of six directions. There is a circle hole on the top board to let the beam go down, two square holes on the front and the back board let the pipeline flow into and flow out of the self shielding system, a shielding door on the left board let people and other devices go into the self shielding system, a square hole on the right board let cold wind go into the self shielding system to control the temperature of the titanium foil, the bottom board connect all the boards to make them a whole system.

The outside of the self shielding system is antisepticised, and accord with the radioprotection standard. This high-voltage electron accelerator is on stream now and makes a lot of benefit.


Science and Technology of Reactor

Nuclear Fuel Solution System Transient Analysis

YU Chao, ZHOU Qi, ZHU Qing-fu (Department of Reactor Engineering Research and Design)

The fissile material exists as solution in the process of the nuclear spent fuel reprocessing. The

dissolved fissile material is well moderated and usually the system can be critical with limited amount of fissile material; solution can be changed to any shape and the fissile material concentration can be changed in the process. It can be seen that most of the criticality accidents happened before involved the fuel solution system. It is meaningful to study the mechanism and source item of the criticality accident for the prevention and mitigation of the accident. We have developed a transient analysis code GETAC based on the cylindrical storage with the point kinetics equation and thermal conduction equation and simulated the transient of the SILENE facility. Three kinds of reactivity insert have been simulated in our study.

Fig. 1 Reactivity step induced with extern neutron source

Simulating results agree with the experimental data and the results of JANES code in the power

excursion, and the error between the simulating and the experiment data is little than 30%, similar with that of JANES. At the same time, the power peak and the time access to the peak simulating in our study is better than the JANES code.

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Science and Technology of Reactor 121

Consultative Report on NPP Improving Loading Factor

LV Niu (Department of Reactor Engineering Research and Design)

Compared with other advanced nuclear power plants about operation performance, we analyze the

critical factor that have the negative impact in improving the loading factor of the nuclear power plants that belong to China Nuclear Union Company and summary the experience. We give advice in order to improve loading factor of the nuclear power plants. Table 1 lists the loading factor of nuclear power plants for China Nuclear Union Company in 2010.

Table 1 Loading factor of nuclear power plants for China Nuclear Union Company in 2010

Qinshan second NPP Qinshan third NPP Tianwan NPP Qinshan NPP

No.1 No.2 No.1 No.2 No.1 No.2

83.99% 93.45% 88.71% 91.92% 94.19% 92.13% 87.11%

The loading factor is the ratio of actual electric energy divided by the rated electric energy for the

statistical period, it is decided by several factors consisting of fuel cycle period, the time of refueling and overhaul and the ratio of service power.

There are a lot of work to do which will improve the loading factor of nuclear power plants belong to China Nuclear Union Company. Because China Nuclear Union Company has several kinds of nuclear power plants, we must analyze detailed every nuclear power plant and give special advice for a special nuclear power plant.

Study Report of Design Guide for Tube Arrays in Cross Flow

XUE Song-ling (Department of Reactor Engineering Research and Design)

Part of fluid energy transfers to the cylinders, when the fluid flows away the cylinders, and creates

the vibration of them. The vibration of cylinders caused by the cross flow is much more violent than that caused by axial flow. So the sufficient concern should be given to the structural vibration of tube array during design process.

Whether or not, vortex shedding existing depends on the tube arrangement and other system parameters. The method of determining the Strouhal number associating with vortex shedding frequency is presented. Other questions like the excitation mechanism of acoustic resonance and methods in preventing it in heat exchanger tubes are also introduced. The mathematical models of fluid elastic instability have been analyzed, and various stability criteria and stability diagrams, which are at the base of experimental data, are proposed. According to the dimensionless parameters and stability criteria, the component can be determined to locate at the stability region or instability region.


Study Report of Design Guide for Single Circular Cylinder in Axial Flow

XUE Song-ling (Department of Reactor Engineering Research and Design)

The vibration of a flexible cylinder in axial flow is random, so the quantities of interests are the

root-mean-square value of the response and the amplitude distribution. This design guideline presents a relationship for calculating the root-mean-square displacement of a

flexible rod or tube in axial flow. The relationship is based on the results of a parameter study; it is valid for component/systems which have parameters in specified ranges and which can be approximated as beams with either simply-supported or fixed-fixed ends.

The relationship is given in terms of rod natural frequency, damping factor, and intensity of the near-field spectrum in the low-frequency ranges. All three are functions of mean axial flow velocity. With these relationships and empirical expressions of damping, which are associated with flow velocity, an empirical equation for RMS displacement is then written as functions of mean axial flow velocity.

A tool is then developed for predicting the root-mean-square displacement of a flexible rod or tube in axial flow. Since the equation is based on experiments involving a smooth rod in flow with minimal entrance effects, the predicted displacement is not conservative.

Study Report of Design Guide for Single Circular Cylinder in Turbulent Cross Flow

XUE Song-ling

(Department of Reactor Engineering Research and Design)

There are many structures similar as circular cylinders in cross flow in reactors and strong fluid

excitation may exist. Therefore the associated response must be accounted for in fatigue or fretting and wear design.

The character and influence factors of lift force component and lift force spectral density in vibration excitation mechanism have been studied, as well as the fluid-structure interactions of left direction and drag direction. The response equation can be greatly simplified because of the design restriction imposed to avoid fluid-structure interaction.

At the base of several methods of response analyze and databank describing the fluid forces, a design procedure is proposed for predicting the dynamic structure response of a circular cylinder in turbulent cross flow in the study report. The procedure is based on the data for a stationary, rigid cylinder and on existing information. The procedure is not applicable to conditions where the wake vortex shedding frequency locks in to a structure natural frequency.

The procedure developed herein for prediction of dynamic structural response of a circular cylinder in turbulent cross flow has shown that very small amplitudes of motion can be expected for typical reactor components, unless lock-in occurs. The use of the procedure is prohibited for those conditions where lock-in has been observed in relatively nonturbulent flow.


Numerical Model Analysis of Fluid-Elastic Instability of Thin Rectangular Plate Due to Overflow

LI Xiang1, ZHAO Min-fu1, XUE Song-ling1, LI Xiao-xuan2, ZHANG Guo-xin1

(1. Department of Reactor Engineering Research and Design;

2. China Experimental Fast Reactor Engineering Department)

A circular thermal baffle weir is located close to the main vessel of liquid sodium cooled pool type

fast breeder reactors (fast reactor for short thereafter). During operation of the fast reactor, a little part of liquid sodium flows from bottom to up in the gap between the circular thermal baffle and main vessel. Liquid sodium will fall down into the cool-sodium pool due to overflow, when the liquid level is higher than the top of the weir. A thin rectangular plate was assigned for a simplified subject investigated and numerical models of motions of plate and fluid were discussed to analysis fluid-elastic instability due to interaction of thin walled structure and fluid during overflow. The motion of the thermal baffle can be predicted by structural dynamics finite element transient response method. The motion of fluid can be predicted by conservation equation of mass and overflow empirical correlations.

Figure 1 shows a thin rectangular plate weir configuration located in a cuboid water pool. The weir is a flexible plate with clamping supported in three directions except the top of the weir. The pool is divided into two parts, a feeding plenum of which fluid flows in from the bottom and a restitution plenum of which fluid exhausts at the bottom.

The plate weir was divided by 3-D eight nodes incompatible isoparametric elements. The natural frequencies and modes are calculated by quasi wave-front subspace iteration method. The stiffness matrices and mass matrices of elements are calculated by two-point Gauss integral method. The motion equations of the whole weir structure can be described by Hamilton theory. An addition of vibration modes method is used to calculate the transient response of a finite element system.

The physical parameters of fluid are considered constant. The mass is conservation in the system，as well as the volume flux in the whole flow course. The height and the velocity of the overflow fluid can be calculated by fall-film theory and horizontal motion at different overflow rates.

The hydrostatic pressures close to the weir are calculated by the liquid level in the two plenums. When the forces at every nodes of weir are obtained, the main coordination values at the next time can be worked out by structure dynamics finite element transient response equations. The volume rates in the two plenums can be calculated by transformer in a time step. The change of flow rates result in the change of the liquid levels of plenums as well as the force acting on the weir. The recycle above can construct a fluid-elastic instability numerical calculation model of fluid discharge over a thin rectangular plate weir in a cuboid water pool.

The results show that decreasing the liquid level gap between the feeding plenum and the restitution plenum, the oscillating amplitude of the liquid level increases, the deformation of the monitoring point at the top-middle of the plate weir decreases but the oscillating amplitude increases, and the frequency decreases slightly (shown in Fig. 2). When the density of weir increases, the frequency decreases and the oscillating amplitude of the monitoring point increase. When the Young’s module decreases, the deformation of the monitoring point increases and the frequency decreases, but the oscillating amplitude shows decrease at first and increase later.


Fig. 1 Scheme of thin rectangular plate weir Fig. 2 Development of deviation of liquid level

in restitution plenum

Small Punch Test on Before and Post Irradiated Domestic Reactor Pressure Steel

ZHONG Wei-hua, TONG Zhen-feng, ZHANG Chang-yi, QIAO Jian-sheng, YANG Wen


Problems may be caused when applying the standard specimen to study the properties of irradiated reactor materials, because of its big dimension, e.g.: The inner temperature gradient of the specimen is high when irradiated, the radiation ray emitted from the irradiated specimen is high, and the irradiation experiment fee is high, etc. In order to solve those problems, the small punch (SP) test technology is developed. Now, the SP is considered as a promising test technology applied in material irradiation effect study.

The specimen of SP is a thin disk with the dimension is φ3 mm×0.3 mm. The process of SP test can be described as follows: Firstly, obtaining the Load-deflection curve of material by punching the specimen through a shot iron, and then calculating out the standard properties through various data transformation models.

The SP test have been well developed among the world since it is invented, however, the SP study on the irradiated specimens have not been carried out in our country. In this paper the small punch test device

Fig. 1 Schematic of SP test device


is established, the schematic of the test device is shown in Fig. 1, then the SP test is carried out on the before and post irradiated A508-3 steel, the test temperature range is from room temperature to －150 , with 10 intervals, at last, the fracture surfaces of the specimen are studied through SEM. The main outcomes are as follows.

1) The Py and Pm, which are extra form the SP curve and can be related to the Yield Strength (YS) and ultra tensile strength (UTS), increased with the decrease of temperature; a good linear relation can be found between Py/Pm and YS/UTS.

2) The SP fracture energy decrease with the temperature decrease when test below a certain temperature, the temperature value is －80 for unirradiated specimens, and －20 for the irradiated specimens; the before and post irradiated domestic A508-3 steel have changed from ductile to brittle when test in the temperature range of －80-－150 and －20-－150 , respectively.

3) For the irradiated A508-3 steel, the Py/ Pm is increased and the fracture energy-temperature curve is shift to the right when comparing to the unirradiated one; the phenomenon indicates that the irradiated embrittlement has occurred on the irradiated domestic A508-3 steel.

This work is supported by the Major State Basic Research Projects (2011CB610503)

Status of R&D on Tritium Permeation Barrier Coatings for Tritium Breeding Blanket of Fusion Reactor*

YUAN Xiao-ming1, ZHAO Wei-wei1, ZHAN Qin1, HU Yong1, CAO Jiang-li2,

LI Tao3, LI Shuai3, YANG Hong-guang1 （1. Department of Reactor Engineering Research and Design;

2. University of Science and Technology Beijing; 3. General Research Institute for Nonferrous Metals）

The paper overviewed the recent progress in the application of several typical tritium permeation barrier (TPB) coatings and their corresponding fabrication technologies for tritium breeding blanket of fusion reactor. According to the design requirements of CN HCCB-TBM and DFLL-TBM, China Institute of Atomic Energy (CIAE) and cooperation units have made great progresses in TPB coatings on the Reduced Activation Ferritic/Martensitic (RAFM) steel substrate. Some typical TPB coatings, such as FeAl/Al2O3, Er2O3, Y2O3 and Al2O3, have been prepared by pack aluminizing plus pre-oxidizing, Sol-Gel and MOCVD processes. The results show that all major properties, including micro-properties, gas permeation reduction factor, electrical insulation properties etc., meet basically the requirements.

* Supported by National Magnetic Confinement Fusion Science Program (2009GB109005)

Failure analysis for JNK Boracic acid Tank Room of NPP

QIAN Jin, CHU Feng-min, PENG Shun-mi, LIU Feng-hui (Department of Reactor Engineering Research and Design)

The JNK Boracic acid Tank Room is important safety equipment for Nuclear Power Plant. Corrosion,


crack and leaked Boracic acid were found on the some welding area of the liners of the JNK Tank Room during operation.

In order to find out the reasons of the crack, a 200 mm×200 mm sample which comprise of upside-liner, underside-liner and weld was cut around a failure area of the JNK Tank Room. A failure analysis work was completed by Macroscopic examination, SEM analysis for the fracture, metallographic examination for the part of crack area and base metal of the liners, EDS, micro-hardness test, intergranular corrosion test, composition analysis for base metal and weld, XRD analysis for corrosion product, etc. Conclusions are as follows:

1) Crack sources start at the gap between the strengthing liner and upside-liner; 2) The crack which was perpendicular to the weld grown from outer to inner of the tank room, the

crack feature is intergranular cracking like branch; 3) The reason of failure of the JNK tank room is SCC; 4) Cl－ was found in gaps of crack; 5) The composition of base metal and weld are normal, the intergranular corrosion was not observed.

Piping Stress Analysis of Secondary Cooling Water System in CARR

DAI Shou-tong, HAN Zhi, WANG Jun, JING Dan (Department of Reactor Engineering Research and Design)

Some piping valves of China Advanced Research Reactor (CARR) cannot maintain the leak

tightness when debugging. Because the valves need to be exchanged, the stress analysis and evaluation should be made for the piping with new valves in order to make sure whether the new piping can keep structural integrity when operating. The purpose of the calculating is to testify the mechanics capability of the secondary cooling water system under the concerned loads.

The secondary cooling water system piping in CARR is not a security level piping, the seism category is seism Ⅱ, the analysis code is ASME volume (1995), the calculⅢ ating loads contains the weight, the internal pressure, thermal expansion and the seism etc. The types and the locations of the supports follow the previous setting, it is not necessary to change them except the essential location. The piping analysis software PEPS1.0 developed by DST company in Switzerland and TRACTEBEL company in Belgium is used for calculating. The results on each condition can be seen in Table 1.

Table 1 Stress results

Guide level Formula Case number Node Allowable limits Stress ratios

Design 8 10 T1 195 0.274

10 20 703 195 0.643

11 400 70 325 0.424

10 21 703 195 0.902

A and B

9 500 T1 234.2 0.559

Test 9 30 T1 310.5 0.192

The node stress ratios of the model of secondary cooling water system piping in CARR are all below 1 according to the results of the software. The node stress ratios of the piping model all accord with the


concerned requirements of the design code ASME, which shows that the mechanical properties of the piping are fairly well on all the conditions. The supports of the previous design need not be changed, added or reduced.

Stress Assessment of Security Injection Tank


The purpose of the calculating is to make the stress assessment of the security injection tank

according to the requirements of the code and the designing on the basis of the gained results of the static, the seism and the thermal stress in order to judge if the tank has the ability to withstand the required loads or not.

According to the structural character and the code requirements, the assessment contains design, normal, abnormal and test condition, each condition corresponding to the descriptions of level O, A, B and test respectively. Due to the demands of elasticity analysis in section C3280, the concerned assessment requirements are listed in Table 1.

Table 1 Stress assessment contents and results data

Case Guide

level Loads Location

Stress

classification

Stress

intensity/MPa

Stress

values/MPa

Stress

limits/MPa

Stress

ratios

Pm Sm 111 184 0.6 Vessel

Pl+Pb 1.5Sm 169 276 0.61

Pm Sm 83 137 0.6

Design O Weight, Inter-

nal pressure,

Nozzle loads Supports

Pl+Pb 1.5Sm 87 190 0.46

Vessel Pl+Pb+Q Sm 286 552 0.52 Normal A Weight,Inter-

nal pressure,

Nozzle loads,

Thermal

expansion

Supports

Pl+Pb+Q Sm 118 381 0.31

Pm 1.1Sm 113.5 202.4 0.56

Pl+Pb 1.65Sm 171.5 303.6 0.56

Vessel

Pl+Pb+Q 3Sm 262.5 552 0.48

Pm 1.1Sm 93.7 139.7 0.67

Pl+Pb 1.65Sm 103.4 209.6 0.49

Abnormal B Weight,

Internal

pressure,

Nozzle loads,

Thermal

expansion,

Seism OBE

Supports

Pl+Pb+Q 3Sm 194.4 381 0.51

Pm 0.9Sy 166.5 311 0.54 Vessel

Pl+Pb 1.35Sy 253.5 465.8 0.54

Pm 0.9Sy 124.5 193.5 0.64

Test Test Test pressure

Supports

Pl+Pb 1.35Sy 130.5 290.3 0.45


All the stresses are summed using absolute value method, the maximum stresses which happen at different locations are considered as that happen at same location, the primary membrane plus bending stress on design condition are deemed as the value of normal condition, which can all be conservative.

The stresses of the security injection tank can accord with the concerned requirements of the design codes with all of the loads. The supporting skirt can accord with the concerned requirements of the buckling analysis. The anchor can accord with the concerned requirements of the intensity check. The stress of the security injection tank can accord with the concerned requirements of the code RCCM on all conditions.

Thermal Stress Analysis of Security Injection Tank


The purpose of the thermal stress analysis of the security injection tank is to make sure whether the

tank can withstand the concerned thermal load or not on all the conditions conforming to the concerned code prescripts and the design requirements.

The three-dimensional entity element is used for the analysis, the intact model is made (left in Fig. 1) for calculating because of the asymmetry structure of the tank. The cladding of the tank is considered in the emulation model in order to think over the influence of the cladding on the thermal conduction accurately. If the bottom plane of the supporting skirt is restricted completely, the results will be anamorphic seriously because the thermal expansion is completely limited. When calculating the bottom supporting plate is divided into four blocks averagely along two vertical planes, only the vertical direction is restricted on the bottom plane, the x and y direction are restricted on the two opposite section respectively, so the thermal expansion is released rationally. The bottom restricting model can be seen on right in Fig. 1.

Fig. 1 Finite element model and bottom restricting

Because the thermal stress distortion is removed in reason due to the effective method, the credible

results are gained. The thermal stress intensity of the main vessel is 351 MPa, which lies in the end of the cladding on the inside wall of manhole. The thermal stress intensity of the supporting skirt is 91 MPa, which lies in the welding on the top of the support, the thermal stress intensity distribution can be seen in Fig. 2. The thermal stress results are the values on the most rigorous condition (accident condition) which


can envelope the results of the other conditions.

Fig. 2 Thermal stress distribution

Anchor Stress Checking of Security Injection Tank


The intention of the calculating is to check the anchor stresses of the security injection tank to know

whether the stress is satisfied the code requirements on the basis of all the reaction forces gained in the static, seismic and thermal stress results.

The security injection tank has a tower-type structure, which is fixed on the ground with 18 anchors, the anchors distribute along the horizontal direction averagely which the type is M45×180. It is not impossible for the anchors to be destroyed when withstanding the shearing loads from the horizontal vibration due to seism and the common reaction from the other loads. The loads values are from the most vigorous condition, that is to say the accident condition, the concerned loads contain the combination of the static, the seism and the thermal load, the total value of the load is the summation of the absolute value of each load, the values can be seen in Table 1. According to the requirements of the code, the types of checked stresses contain tensile stress, shearing stress, combination stress of tensile and shearing and supporting stress etc.

Table 1 Load value endured by single anchor

Load category Fx/N Fy/N Fz/N

Static 22 962 8 805 28 381

Dynamic 28 878 30 430 71 439

Thermal 7 585 7 585 44 986

Summation 59 425 46 820 144 806

The calculating stresses of the anchors are less than the allowable valves under the conservative

summation of the static load the seism loads and the thermal loads of the security injection tank. The calculation shows that the stresses of the anchors of the security injection tank are all satisfied with the concerned requirements of the design codes under all the conditions.


Static Stress Analysis of Security Injection Tank


The static structural analysis of the security injection tank is made to make sure whether the tank can

withstand concerned loads or not on all conditions conforming to concerned code prescripts and design requirements. The tanks are made up of four different materials, the capabilities are listed in Table 1.

Table 1 Mechanics capability of material

Material Temperature/ Elasticity

module/GPa

Yield

strength/MPa

Tensile

strength/MPa

Limiting

values/MPa

Stress

intensity/MPa

20 197 345 552 138 －

50 195 －－－ 184

18MnNiMo

150 192 －－－ 184

20 204 215 410 103 －

50 203 －－－ 137

20R

150 200 223 410 103 127

20 － 173 483 －－

50 －－－－ 115

00Cr19Ni11

150 200 207 340 85 115

42CrMo 20 －－ 862 172 －

The intact model static analysis for the tank is made using the entity element model, the calculating

model adopt the 20-node three-dimensional entity element SOLID95. In order to improve the results precision the static pressure is simulated through applying the grads loads on the inside surface of the tank. The nozzle loads of the ejecting opening is fairly great, the loads are applied averagely to each node of the nozzle opening avoiding the results distortion because of the stress concentration due to the applied centralized loads. The finite element model born by software ANSYS is in Fig.1, the stress intensity distribution is in Fig. 2.

The thickness of the man hole has been optimized according to the results, at last the static stress and displacements of the vessel and the supporting skirt of the security injection tank are gained, which are satisfied with the requirements of the design codes.

Fig. 1 Finite element model Fig. 2 Stress intensity distribution


Seism Analysis of Security Injection Tank


The purpose of the seism analysis of the security injection tank is to make sure whether the tank can

resist the concerned dynamic loads or not on all the conditions according to the concerned prescripts of the code and the design requirements.

The security injection tank is full of plentiful liquid, and the hydrodynamic pressure is a key problem in dynamic analysis. Because the liquid sloshing in the tank is slight, the rigid wall theory basing on the HOUSNER model is at last adopted through contrasting and researching different methods, only the impulse pressure is considered while the convection pressure is neglected. The equivalent density of the tank is gotten using the conservative methods, so the problem of the hydrodynamic pressure is solved by affixing mass to the tank wall.

The mode analysis to the tank is made using the software ANSYS. The finite element model is born using the three-dimensional 20-node entity element SOLID95, the block Lanczos method is used to pick-up the anterior 3 mode shapes (Table 1) of the tank, and the main mode shapes are the critical BEAM shape (Fig. 1) which means that the mode analysis results accord greatly with the structural characteristic of the structure.

Table 1 Anterior 3 mode shape

Step Frequency/Hz Mode shape

1 25.1 Swaying along vertical plane containing manhole point

2 25.2 Swaying along vertical plane orthonormal to that of step 1

3 49.4 Distortion

Fig. 1 Structural mode shape


According to the results the maximum seism stress is 16.7 MPa, the maximum primary membrane stress intensity is 10.7 MPa, the maximum primary membrane plus bending stress intensity is 16.4 MPa. It can be seen that the seism stress level is rather low, the security injection tank has a big security margin, and the seism capability of the tank under the concerned conditions is fairly well.

Buckling Analysis of Supporting Skirt of Security Injection Tank


The purpose of the calculating is to make a structural buckling analysis according to the code rules and the design requirements in order to judge whether the security injection tank have the ability to resist the buckling failure or not on the condition with the design loads, the weight, the internal pressure, the seism, the hydraulic pressure, nozzle loads.

The liner buckling analysis is made, the unit loads are applied downwards to the nodes on the upper top plane of the supporting skirt, the bottom plane of the supporting skirt is fixed on the floor. The finite element model born by ANSYS can be seen in Fig. 1, in which the red arrows are the symbol of the applied buckling loads. The eigenvalue buckling analysis is used for buckling mode calculating, the first step buckling mode shape is shown in Fig. 2.

Fig. 1 Finite element model Fig. 2 First step mode shape

The first step amplifying factor f is 0.197×106，the calculating critical loads is 94.56×106 N，the safety factor is 4，the allowable loads is 23.6×106 N，the calculating loads are conservatively assumed as the summation of the vertical loads of the seism, the thermal and the weight, the calculating loads F=2.8×106 N。

The calculating loads of the supporting skirt is less than the critical bucking loads under the conservative superposition of the static loads the seism loads and the thermal loads of the security injection tank. The calculation shows that the buckling of the supporting skirt can not happen, it is to say that the security injection can keep stability under all the conditions.


Radiation Measurement for Ji’Nan MNSR Decommissioning

PENG Dan, LU Jin, ZHANG Yong-ao (Department of Reactor Engineering Research and Design)

Ji’Nan MNSR is an under moderated reactor of pool-tank type, UAl with high-enriched 235U as fuel,

beryllium as reflector, and light water as coolant. It was built in 1989, and shutdown in 2008. It operated 840 times, the total operation time is 3 194.9 h and accumulative flux is 10 581.49×1015 cm－2。

The decommissioning scope of Ji’Nan MNSR includes the related systems and the operating waste. The final decommissioning target is that the site will be used without limit. Fig. 1 shows the site and sampling point.

Fig. 1 Workshop and soil sampling point

Radiation monitor and measurement include environment γ dose measurement and sampling analysis

inside and outside site. The data is shown as Table 1, 2 and 3.

Table 1 γ dose

dose/(μSv·h－1) dose/(μSv·h－1) Location Measure number

Max. Ave. Location

Measure

number Max. Ave.

Reactor hall 16 0.09 0.08 Other rooms 30 0.10 0.09

Transportation alley 4 0.11 0.10 Gate 1 0.10 0.10

Waste pin 2 0.11 0.10 Total 53 0.11 0.09

Note: Other rooms include rabbit A, rabbit B, bathhouse, Monitor, air compress and water production rooms

The background γ dose before decommissioning is 0.08-0.13 μSv/h. The γ dose after decommission-

ing gets background level. The sampling analysis results show that Ji’Nan MNSR site can satisfy the object for the unrestricted use.


Table 2 Sample activity

Rooms Parameter

Reactor hall Rabbit B Water purify. Rabbit A Air comp. Bathhouse Trans. alley Waste pit

Sample number 37 12 19 13 7 3 17 5

137CS － 1.8 － 2.4 －－－－

60Co 2 4.4 － 6.5 －－－－

Activity(Max.)/

(Bq·kg－1)

65Zn －－－－－－－－

Note: Detection limit: 137CS, 1.4; 60Co and 65Zn, 1.7 Bq·kg－1

Table 3 Soil activity

Sampling point Parameter

East of workshop (1) North of tram road (2) West of workshop (3) South of tram road (4)

137Cs －－－－

60Co －－－－

90Sr 1.16±0.17 1.54±0.46 8.14±0.39 1.53±0.07

Activity

/（Bq·kg－1）

65Zn －－－－

Note: Detection limit: 137CS, 1.4; 60Co and 65Zn, 1.7 Bq·kg－1

Preliminary Design of Special Unloading Tool for Miniature Neutron Source Reactor

HAO Qian, PENG Dan, LU Jin


In recent years, MNSR (Miniature Neutron Source Reactor) LEU conversion is appreciated by IAEA and the related country, and CIAE is also carrying out this work. In the process of MNSR LEU conversion, unloading for the HEU fuel is an important work, this paper introduces preliminary design for special unloading tool for MNSR.

The core of MNSR is composed by fuel elements and the grid frame. Fuel elements are arranged in concentric circles with a total of ten laps, and the size of φ4.3 mm× 256 mm; the grid frame formed by the upper and lower grid plate is connected by four rods. The core size is φ230 mm× 230 mm, the total weight is 6.5 kg, see in Fig. 1. The core has a control rod guide tube, the original long-handled tool can load fuel assembly into the reactor core, the original tool is a stainless steel tube of the length 6 m and diameter 5 cm. When unloading, due to the high radioactivity of the fuel assembly, the existing tool can not be used, so the special unloading tool, its structure is shown in Fig. 2. The MNSR special unloading tool includes of the top plate, spring, catheter and center rod, the total length is 230 mm. The diameter of top plate is 40 mm and thickness is 2 mm. The center rod is 5 mm in diameter and 230 mm in length, with the top plate connection, distributed the guide bar and the cross connection device. The spring is about 30 mm in length between the top plate and the catheter. Catheter internal diameters are 8 mm and 15 mm respectively, 35mm in length, the tube slotting is 20 mm in length and 4mm in width.


Fig. 1 MNSR core structure Fig. 2 Special unloading tool design

The MNSR special unloading tool combined with the original long-handled tool can be implemented

unloading. The unloading tool can be fixed with the core by using the long-handled tool connected through the top plate of the unloading tool, and then remove the long-handled tool. The cross device can be matched with the original core mechanical structures, spring is used to fixation, the catheter guide slot ensure spring action along the axial direction, and the catheter bottom protects the core interface to avoid distortion and increase security. Special tool connected to the rope can complete the fuel unloading by the top of reactor vessel, this process can prevent secondary pollution, avoid the destruction of the reactor container, and meet the application requirements of MNSR LEU conversion.

DAQ System of Current Based on MNSR

HONG Jing-yan, PENG Dan, WU Xiao-bo (Department of Reactor Engineering Research and Design)

The flux or power should be acquired using the detector in the operation of MNSR. As usual, the

signal of detector is current, and it is very width range with 10-11-10-6 A. It is hard to satisfy the linearity to amplify this signal by using fix gain amplifier. As this reason, a gain-programmable amplifier should be designed; it is consisted of primary amplifier, gain control system, second amplifier, A/D convert system and communication system. The gain is controlled by a MCU. The digital current data is transferred to the computer, and the flux (or power) or reactivity is demonstrated in the computer.

The principle of this system is illustrated in Fig. 1.

Fig. 1 Principle of system

The gain-programmable amplifier is consisted of Chopper-Stabilized Op Amps, ICL7650; the A/D


convert and gain controlling is accomplished by a Soc, C8051F020; the detector is γ compensative ionized chamber; a DAQ software is programmed in the computer.

The system is to convert the analog current signal of every gain range to digital signal, transient these signals in the computer and acquire the flux (or power) or reactivity.

The results of MNSR test is shown in Fig. 2.

Fig. 2 Current change in reactor startup and shutdown

The result is accord with the flux change and shows that the design is proper. Next, the precise flux

(or power) will be acquired after the calibration of detector.

Preliminary Research of Neutron Energy Spectrum of Thermal Neutron Beam Port for IHNI

LU Jin, WU Xiao-bo, ZHANG Jin-hua, ZOU Shu-yun, PENG Dan, HONG Jing-yan,

HAO Qian, LIU Xin-ling (Department of Reactor Engineering Research and Design)

IHNI with 30 kW is specially designed for Boron Neutron Capture Therapy (BNCT), it is the pool-tank

reactor, UO2 with enrichment of 12.5% 235U as fuel, beryllium as reflector, light water as moderator and coolant. There are two neutron beams in the opposite side of the reactor core, one is thermal neutron beam, the other is epithermal neutron beam. The neutron spectrum is an important data for BNCT. The paper introduces the thermal neutron spectrum measurement at the port of thermal neutron beam.

The neutron spectrum at the port of thermal neutron beam of IHNI (In Hospital Neutron Irradiator) was measured by multiple foil activation technique. SAND-II method is used to unfold neutron spectrum. Foils details are given in Table 1. Foils are irradiated in the same position in different reactor power; then γ rays are measured by HPGe. Finally the activities are normalized in full power situation per nucleus.

Neutron spectrum of 642 energy groups, calculated with MCNP program, was used as initial spectrum input files of SAND-II. In the third iteration, the results was coincident with the iterative criterion, and is shown on Fig. 1.

Conclusion: the neutron beam is fully moderated; over 95% of all neutrons are thermal neutrons, while fast neutrons are about 1%. The neutron beam is to fit for BNCT (Neutron Boron Capture Therapy).


Table 1 Details of foils

Foils Reaction Half life Diameter/mm Thickness/mm γ energy/MeV Activity Remarks

Au 197Au(n, γ)198Au 2.695 d 10 0.005 0.411 8 2.342×10－13 Pure metal

W 186W(n, γ)187W 23.72 h 10 0.1 0.685 8 7.191×10－14 Pure metal

Lu 176Lu(n, γ)177Lu 6.734 d 10 0.1 0.208 4 8.165×10－12 Pure metal

Mn 55Mn(n, γ)56Mn 2.579 h 4 0.1 0.846 8 1.158×10－14 Pure metal

In 115In(n, γ)116Inm 54.41 m 4 0.1 0.416 9 3.737×10－13 Pure metal

Co 59Co(n, γ)60Co 5.271 a 10 0.1 1.173 9.690×10－14 Pure metal

Ni 64Ni(n, γ)65Ni 2.56 h 10 0.1 1.115 1.336×10－17 Pure metal

Dy 164Dy(n, γ)165Dy 2.334 h 8 0.1 0.094 7 3.686×10－13 Dy-Al alloy

Cu 63Cu(n, γ)64Cu 12.70 h 10 0.1 0.511 1.616×10－14 Pure metal

Fig. 1 Results of MCNP AND SAND-Ⅱ


Radiochemistry and Nuclear Chemistry

Study on Anode Process in Molten Salt Electrolysis of CeO2

LIN Ru-shan, YE Guo-an, HE Hui, TANG Hong-bin (Department of Radiochemistry)

The electrometallurgical treatment of spent metallic fuel, which is the most promising pyrochemical

reprocessing process, was pursued intensively. In order to extend the electrometallurgical treatment technology to spent oxide fuels, a head-end process is necessary to convert oxides to metal. A primary study on the electrode process of actinide and lanthanide in molten salts was done for the molten salts electrolytic process.

CeO2 was selected as a model oxide, and the anode processes of CeF3-LiF-MF2-CeO2 (M＝Ba, Ca) system on a graphite anode were studied using cyclic voltammetry and chronoamperometry. The results show that the anode processes of the above systems were highly irreversible and related to the discharge of anions firmly, while cations in the melts had little effect. The potential of anode effect was measured as 4.6 V vs. Li+/Li electrode, and has little effect on the potential scanning rate and temperature.

Concentration Determination of Tetravalent Uranium by Direct Spectrophotometric Method

WANG Liang, HE Hui, ZHANG Qiu-yue

(Department of Radiochemistry)

The traditional concentration determination method of macro amount of tetravalent uranium in

aqueous solution is potassium dichromate titration which is simple to operate with high accuracy and big volume of effluent. In order to simple the analysis procedure which can reduce the volume of effluent and the disturbance of other factors, direct spectrophotometric determination of U(Ⅳ) in the medium of H2SO4 is used in this paper.

The specific absorption of U(Ⅳ) in aqueous solution is near 650 nm, which maybe varies with different acidity of medium. As shown in Fig. 1, during the medium of HCl, HNO3 and H2SO4, the absorbance of tetravalent uranium at the wavelength of 650 nm in H2SO4 is a constant when the acidity of it is changed, so the 1.0 mol/L H2SO4 was chosen as the analysis medium. The relationship between the absorbance of U(Ⅳ) at 650 nm and the concentration of it is A＝0.20cU( )Ⅳ , R2＝0.998. The molar extinction factor of U(Ⅳ) at 650 nm is ε650 nm＝0.20 L·g－1·cm－1. When the volume of sample is less than 10% of the whole volume of the system, the sample acidity effect on the analysis can be ignored. The determination limit of this method in aqueous solution for U(Ⅳ) is 1.0 g/L.

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radiochemistry and Nuclear Chemistry 139

Fig. 1 The change of absorbance on different concentration of acids, pure water as reference

Three disturbance factors on the analysis result is studied in this paper, i.e., U(Ⅵ)/U(Ⅳ), the

concentration of nitrate and hydrazine. When the U(Ⅵ)/U(Ⅳ) is less than 10, the concentration of nitric acid is less than 10 mol/L and that of hydrazine less than 2.0 mol/L, the concentration determination accuracy for U(Ⅳ) in the sample is greater than 98%.

Determination of α Dose Rate of 238Pu Solution

LIU Jin-ping, SONG Peng, CHEN Hui, HE Hui, WANG Liang (Department of Radiochemistry)

In order to study the radiolysis effect of α particles to reagents and understand the chemical process

in reprocessing process, we measured the α dose rate of 238Pu solution by the method of Fricke dosimeter. The absorbing dose can be calculated by the formula:

2 1[1 0.007( )]AD

Gl t tε ρΔ

=+ −

The results are showed in Fig. 1. They indicate that the dose rate of per unit concentration of 238Pu was 40.0-43.1 Gy·L·min－1 (Table1). Calculating by the energy of α particles emitted by 238Pu, the absorption energy of 238Pu solution is 32.4 J·L－1·g－1, that is 32.4 Gy·g－1·min－1. The experimental values have a good agreement with calculation value.

Fig. 1 The absorption of Fe3+ vs time under deferent concentration of plutonium


Preparation of Uranous Nitrate by Membrane Electrolysis

YUAN Zhong-wei, SHUANG Hong-ying, YAN Tai-hong, ZHENG Wei-fang (Department of Radiochemistry)

U(Ⅳ) is a main reductant used in the Purex process. Electrochemical method is a sound way to

prepare U(Ⅳ) due to it is easy to control and monitor the produce process and not using other additives. However, in traditional electrochemical method, U(Ⅳ) yield is usually between 60%-70%.

In order to enhance U(Ⅳ) concentration and preparation rate during electrochemical process, taking 72 cm2 Ru/Ir coated Ti net as anode and Ti net as cathode, a membrane electrolyser was setup, and the performances of two different membranes were compared. The scheme of the electrolyzer was shown in Fig. 1.

Fig. 1 The schematic diagram of the electrolyzer

The results show that the apparatus runs well with 120 mA/cm2 current density, and the two different

membranes (Nepem-417 and Aciplex-F4112) have no remarkable effect on electrolysis. After 180 min electrolysis, U(Ⅳ) yield can achieve 93.1% (500 mL feed, U(Ⅵ) 199 g/L). During the electrolysis, hydrazine concentration decreased from 0.52 mol/L to 0.30 mol/L, HNO3 concentration decreased from 2.20 mol/L to 0.70 mol/L, cell voltage varied between 3 V and 3.6 V, catholyte and anolyte temperature was below 45 (room temperature was 28 ).

Research of Trend of Technetium in U/Pu Partition Step of APOR Process

WANG Hui, WEI Yan, LIU Fang, JIA Yong-fen, LIU Zhan-yuan (Department of Radiochemistry)

In U/Pu partition step of APOR process (1B tank), where monomethylhydrazine (MMH)- dimethyl-

hydroxylamine (DMHAN) are adopted as reductants, most of technetium flows into 1BP, but the reason


remains unclear. Our work explains this phenomena through the reaction kinetics between Tc(Ⅶ) and MMH or DMHAN, the results of multi-stage extraction experiments and continuous mixer-settler experiments. Experiment results show that, technetium is reduced to unextractable low valent state by MMH, and this reaction will be greatly accelerated in the presence of uranium. This is the main reason for the trend of technetium in 1B tank. The difference in the trend of technetium in multi-stage extraction experiment and mixer-settler experiment is also explained here. In a multistage extraction experiment, aqueous phase was totally transferred to the next stage, and the reaction between Tc(Ⅶ) and MMH was always staying in the inducing period, thus most of Tc existed as extractable Tc(Ⅶ). While in a mixer-settler experiment, aqueous phase was not totally transferred to next stage, and the progress of the reaction between Tc(Ⅶ) and MMH accumulated during the experiment, and finally the reaction entered the fast-reaction period, during which Tc(Ⅶ) was quickly reduced to unextractable low valent state, leading that most of Tc flew into 1BP.

Extraction of Np(Ⅳ, Ⅴ, Ⅵ) Ions From Aqueous Nitric Acid Solutions With TODGA and DHOA

ZHU Wen-bin, LI Feng-feng, YE Guo-an, LI Hui-rong


Two novel extraction reagents, N, N, N′, N′-tetraoctyl diglycolamide (TODGA) and N, N-dihexyl-

octamide (DHOA) have been used as extractants for extraction Np(Ⅳ, Ⅴ, Ⅵ) ions from aqueous nitric acid solutions. The effects of concentration of the nitric acid, salting-out agents in aqueous and the extractant in ordanic phase on distribution ratios are examined. The results show that the TODGA and DHOA can well extraction Np( ) and Np( ), and the Np( ) is hardly extractioned by TODGA and Ⅳ Ⅵ Ⅴ

DHOA. The order of distribution ratios of Np(Ⅳ, Ⅴ, Ⅵ) ions by TODGA and DHOA is Np( )Ⅳ ＞Np( )Ⅵ

＞Np( ). DHOA can also restrain the extraction of Ⅴ Np(Ⅳ,Ⅴ,Ⅵ) by TODGA. The extraction equation of Np(Ⅳ, Ⅴ, Ⅵ) ions by TODGA have also been studied, The result is as followed: Npaq

4++4NO3－

aq+ 3TODGAorg→Np(NO3)4·3TOGDAorg for Np( ), Ⅳ NpO2

+aq+NO3

－

aq+TODGAorg→NpO2(NO3)·TOGDAorg for Np( ), Ⅴ NpO2

2+aq+2NO3

－

aq+2TODGAorg→NpO2(NO3)2·2TOGDAorg for Np( ).Ⅵ

Valance Adjustment of Np and Pu in 1AF Fluid of Pilot Plant

ZHU Wen-bin, LI Feng-feng (Department of Radiochemistry)

The influence of temperature and time on Np( ) and Pu( ) percent in 1AF fluid had been studied, Ⅵ Ⅵ

the constitute of 1AF fluid was followed as: c(HNO3)=2 mol/L, ρ(U)=225 g/L, ρ(Pu)=2.4 g/L, ρ(Np)= 0.129 g/L, which was in accord with the pilot test plant 1AF fluid. The results suggested: 1) If the NaNO2 was only added to 1AF fluid in the first stage of adjustment, the percentage of Pu( ) was increasing with Ⅵ

the increasing temperature and time, meanwhile, the producement rate of Pu( ) was increasing with Ⅵ

increasing temperature, possible reason was that NaNO2 was rapidly decomposed with the temperature


hoisted. In the same condition, the percentage of Np( ) was slowly increasing with the increasing Ⅵ

temperature and time, and in the range of studied temperature, the percentage of Np( ) was only Ⅵ

10%-20%. 2) If the NaNO2 was periodically added to 1AF fluid, the percentage of Pu( ) wereⅥ less than 5%, when the temperature were not exceeded 80 . So in this condition, the value of Pu( ) in 1AF fluid Ⅵ

was up to the mustard, but the percentage of Np( ) was only about 10%.Ⅵ

Study on Extraction Performance of Tri-iso-amyl Phosphate

JIANG De-xiang, HE Hui, TANG Hong-bin, ZHU Li-yang, LI Feng-feng (Department of Radiochemistry)

The distribution performance of HNO3, Pu( ), Pu(Ⅲ Ⅳ) and Np(Ⅳ) in the two phase system of

Tri-iso-Amyl Phosphate(TiAP) and aqueous, the influence of the concentration of extractant, nitric acid and Al(NO3)3 on the distribution ratio of Pu( ), Pu(Ⅲ Ⅳ) and Np(Ⅳ) were studied, the result is that the extraction ability of TiAP/kerosene is better than TBP/kerosene for Pu(Ⅳ) and Np(Ⅳ) but Pu(Ⅲ), when the HNO3 concentration in aqueous is below 5mol/L, the distribution ratio of Pu(Ⅳ), Np(Ⅳ) and Pu(Ⅲ) between TiAP/kerosene and aqueous are increase with increasing concentration of HNO3 in aqueous and/or Al(NO3)3 besides that, the capability of TiAP in extracting Pu(Ⅳ) and Np(Ⅳ) was increased when the salting-out agent is in the system. The extraction complex structure of HNO3·TiAP, Pu(NO3)3·3TiAP and Np(NO3)4·2TiAP are gained by slope method. In order to be used for flow sheet design, the extraction performance of FP are studied at the same time such as Y, Mo, Ru, Ag, Cs, La, Ce, Pr, Nd, Sm, Eu and so on. The result is that the distribution of the FP extracted by TiAP/kerosene is extremely low when the HNO3 concentration is between 0.1 mol/L and 7 mol/L.

It can be concluded that TiAP is an alternative extractant to TBP for extraction and separation actinide elements, especially for the system of heavy dosage of irradiation.

Catalytic Reduction of U(Ⅳ) With Hydrazine in Nitric Acid Solutions

LI Bin, HE Hui, ZHANG Qiu-yue, DING Bo-fa, HUANG Xiao-hong (Department of Radiochemistry)

Preparation of U(Ⅳ) in heterogeneous-catalytic processes is a potential method that can react in

normal temperature and pressure and the process is very simple. The reduction of U(Ⅵ) with hydrazine catalyzied by platinum black or Pt/SiO2 in HNO3 solutions was studied by investigating the influence of hydrazine concentration, acidity, catalyst amounts and temperature on the reaction.

Results show that the reduction rate of U(Ⅳ) is mainly determined by concentration of HNO3. The higher conversion can be obtained by controlling initial concentration of HNO3 between 0.75 mol/L and 0.92 mol/L. Reaction temperature only affects reaction rate but nearly doesn’t affect the conversion rate, the higher of temperature can enhance the rate of the reaction. Using platinum black as a catalyst, the reduction ratio of U(Ⅳ) can achieve 99% when the initial concentration of uranium, nitric acid and hydrazine is 0.90 mol/L, 0.80 mol/L and 1.0 mol/L respectively and solid-to-liquid ratio is 1/250 (g/mL) at


60 . Using Pt/SiO 2 as a catalyst, the reduction ratio of U(Ⅳ) is about 90% only at the same reaction conditions. The change of the mass transfer process is considered the main reason. The reduction ratio can raise to 98% when the reaction temperature is 40

Fig. 1 Relationship of U(Ⅳ) reduction ratio

vs the reaction time at various catalyst Fig. 2 Relationship of U(Ⅳ) reduction ratio

vs the reaction time at 40 and 60

Determination of Trace Plutonium in Uranium Product by ID-ICP-MS

JIN Hua, SU Yu-lan, YING Zhe-cong, ZHAO Sheng-yang (Department of Radiochemistry)

Plutonium is strictly limited in the uranium product of spent fuel reprocessing. The analysis of

plutonium in uranium product is the key point of product quality control. Plutonium concentration is limited below 7.2×10－9 g·g－1U. Because of large sampling volume and time-consuming, conventional measurement methods were too complicated to meet the requirement. Inductively coupled plasma mass spectrometry (ICP-MS), with the advantages of small size sample needed, high throughput measurement and low determination limit, has been widely used in the area of trace actinides analysis.

In this work, a method for separation and determination of plutonium in uranium product has been developed. Two separating columns using TBP resin and TEVA resin were combined together to strengthen the decontamination of uranium, and ID-ICP-MS was used to determine plutonium.

A simulated sample consists of uranium, neptunium and plutonium in 2.0 mol/L nitric acid medium was prepared for method testing.

Two samples were weighed, and 242Pu spike was added accurately. After isotopic exchange came into equilibrium, the nitric acid concentration was adjusted to 3 mol/L, and ferrous sulfamate (0.1 mL 0.5 mol/L) was added to reduce plutonium to Pu(Ⅲ). The sample solution was introduced onto TBP resin column. 10 mL 3 mol/L HNO3 was used to elute plutonium further. Then NaNO2 (0.1 mL 2 mol/L) was added to the eluted solution to oxidize Pu(Ⅲ) to Pu(Ⅳ), which was absorbed on TEVA resin and deabsorbed with 0.02 mol/L HNO3-0.02 mol/L HF (3 mL) after uranium was eluted with 3 mol/L HNO3 (9 mL). The plutonium isotope abundance was determined by ICP-MS.

After the separation procedure, decontamination factor (DF) of uranium from plutonium is above 106. The uranium kept in plutonium fraction will not affect the determination of plutonium isotopes by


ICP-MS. The analytical results of the simulated sample demonstrated that the method could be applied in the determination of plutonium in uranium product of nuclear fuel reprocessing.

Determination of Micro U, Np, Pu by Highly Oriented Pyrolytic Graphite Pre-diffraction EDXRF

SONG You, ZHENG Wei-ming, LIU Gui-jiao, WU Ji-zong, CHEN Chen


Based on the prototype of Highly Oriented Pyrolytic Graphite Pre-Diffraction EDXRF, a new device was constructed after optimizing of hardware including high voltage supplier, detector, sample bracket, and software of data processing. The new instrument was installed on the glove box, with the sample bracket located inside and others parts outside, which could be used to measure radioactive samples and maintained convenienly.

The performance of the sealed apparatus was tested. The minimum detection limits (MDL) of uranium, neptunium, and plutonium were in the range of (0.18-0.24) μg/mL. The precision (RSD) of the method was less than 3%. The measurenment linearity range of neptunium, plutonium and uranium were from five times of MDL to 1 mg/mL, which basically covered the concentration with three orders of magnitude. The device could measure samples from many process points in reprocessing plant.

The variation of voltage and current would influence the uranium correlation curve that could be corrected through scattered X-ray by stannum located at the back of the sample as inner standard. The study of influence of zirconium, sodium nitrite on the uranium correlation curve showed that when the concentration of then was lower than 1 000 μg/mL, the change of exciting parameters can be ignored. The instrument had been used to measure concentrations of U and Pu in samples from the pilot reprocessing plant; the results are in good agreement with that obtained by other means.

Analytical Instrument of X-ray Fluorescence Determine Concentration of U and Pu in Organic Solution at the Same Time

SONG You, ZHENG Wei-ming, LIU Gui-jiao, CHEN Chen, WU Ji-zong

(Department of Radiochemistry) An instrument is developed to measure the concentration of U, Pu and the intensity of gamma ray in

samples of 1AP organic phase at the same time. The Ag cold cathode is used to excite L series X-ray fluorescence of U and Pu. The Si-pin detector is used for X-ray detection. The intensity of gamma ray is measured by NaI(Tl) detector.

For the usage in reprocessing plant, the instrument is designed to be sealed partly in glove box through the geometry arrangment of X-ray tube, sample room, and detector. The X-ray tube and the detectors were placed outside of the glove box, and isolated with the sample room which was sealed in the glove box. The incident X-ray and emit X fluorescence transmit through silver window which is not only as the sealed material, but also as energy filter. The performance of the instrument is tested. The uranium


linearity range of working curve is from 20 mg/mL to 100 mg/mL, with the precision (RSD) of 1.7%. And the plutonium linearity range is from 0.6 to 2 mg/mL. For plutonium with the concentration of 1 mg/mL, the precision (RSD) is 3.5%.

U(Ⅳ) Preparation by Method of Electrolysis

FU Jian-li, LIU Huan-liang, ZHANG Li-hua, WANG Tie-jian, WANG Ling (Department of Radiochemistry)

U(Ⅳ) is prepared by electrolysis of U(Ⅵ) in nitric acid, as showed in Fig. 1. A circular-sheet osmotic

film is fixed at the middle of electrolytic cell. Osmotic film can urge the electron transfering from one pole to another, but electrolyte can’t penetrate. A magnetic stirrer is used to mix cathode electrolyte uniformly. In the process of electrolysis, U(Ⅴ) are formed firstly around cathode, and then U(Ⅴ) disproportionate to form U(Ⅳ) and U(Ⅵ).

Fig. 1 The apparatus of electrolysis

The current of electrolysis is 400 mA. The color of cathode electrolyte is yellow and light yellow

near anode electrolyte during the forepart of electrolysis. Along with the delay of time, cathode electrolyte turns green gradually. Aliquot nitric acid can form nitrous acid in the process of electrolysis, and nitrous acid could oxidize U(Ⅳ) to U(Ⅵ) again. In order to keep the electrolysis in nitric acid media, a small quantity of hydrazine was added to destroy nitrous acid. Result shows that U(Ⅳ) is oxidized to U(Ⅵ) if the concentration of hydrazine is too small when electrolysis approaches end point, the optimal concentration of hydrazine is 0.3 mol/L. The course of electrolysis is monitored by sampling at regular intervals to check the absorption peak of U(Ⅵ). The absorption peak of U(Ⅵ) at 414 nm disappears gradually, and absorption peak of U(Ⅳ) at 480 nm augments gradually along with the time, as shown in Fig. 2. After about 4 hours, the peak of U(Ⅵ) is disappearing, that means the electrolysis comes to the end. The concentration of U(Ⅳ) is about 140 g/L in the final solution.

Fig. 2 The absorption spectrogram of U(Ⅵ) and U(Ⅳ)


Separation and Purification of Fissiogenic Ruthenium From Irradiated Uranium

CHANG Zhi-yuan, ZHANG Ji-long, ZHAO Yong-gang


Ruthenium is an important fission product. Its isotopic composition may reflect the burnup or the initial uranium enrichment of nuclear fuel. So the separation and purification method of fission products of Ruthenium from irradiated uranium was studied and established.

Ru was there as the species of [RuNO]3+ when spent fuel dissolved in nitric acid. Due to its complicated complex behavior, [RuNO]3+ can form various complexes with nitrate and nitrite. Under high concentration of nitrite in diluted nitric acid, some complex anions of [RuNO]3+, which can be extracted by quaternary ammonium, would be exist. Because of the interference of Pd with the isotope determination of Ru, decontamination of Pd from Ru should be taken into account at the same time. To separate Ru from irradiated uranium, the following procedure was adopted:

1) Irradiated uranium was dissolved in 6 mol/L HNO3, and U, Pu were extracted by 30%TBP/OK; 2) The raffinate was evaporated nearly to dryness, then the residue was dissolved by 0.1 mol/L HCl; 3) Mo, Pd were extracted by trioctylmethylammonium chloride (TOMA)-xylene twice; 4) The aqueous of 3) was dried, and redissolved by 0.05 mol/L HNO3, a certain quantity of sodium

nitrite was added; 5) Ru was extracted by trioctylmethylammonium chloride-xylene; 6) The organic was washed by 0.05 mol/L HNO3 twice, and then Ru was back-extracted by 10 mol/L

HNO3; 7) To refine Ru by repeat 2)-6) once more. In order to test the separating ability of the procedure, extracting experiments of Ru was studied,

including the concentration of nitric acid and nitrite, contacting time, the concentration of extractant, and the stripping condition. A simulated experiment was also performed by using simulated high level liquid waste (HLLW), the decontamination factors for Sr, Pd, Mo and yield of Ru were obtained.

At high concentration of nitric acid, NO2－ was unstable, and NO3

－ can not form complex anions with RuNO3+, so the partition of Ru in organic phase was reduced. 0.05 mol/L HNO3 was selected as extracting medium accordingly. The extraction of Ru reached equilibrium within 5 min.

From the extracting result of Ru under various concentration of TOMA, a straight line was fitted between ln D(Ru) and ln c(TOMA), with the slope of 1. So, 1﹕1 complex formed during the extraction.

With the increasing of NO2－, D(Ru) increased. A fitted straight line was obtained between ln D(Ru)

and ln c(NO2－ ), with the slope of 2.79, which mean that Ru was extracted in the species of

RuNO(NO3)2(NO2)2－ and RuNO(NO3)(NO2)3

－. Stripping experiment showed that 7-10 mol/L HNO3 can back-extract Ru from organic phase

effectively. The separating result for simulated HLLW sample shows that the decontamination factors for Sr, Zr,

Pd are more than 1 000, except for the relatively low DF of Mo. The yield of Ru is more than 50% after the procedure.


Development of an Analytical System for Determination of Free Acid via a Joint Method Combining Density and Conductivity Measurement

FAN De-jun, ZHANG Li-hua, WU Ji-zong, SHAO Shao-xiong, LIU Huan-liang


Determination of free acid plays an important role in spent nuclear fuel reprocessing. It is necessary to develop a rapid analytical device and method for measuring free acid. A novel analytical system and method was studied to monitor the acidity in solutions of Purex process by a density-electric conductance joint measurement, in which electric conductivity and temperature were determined with an electrodeless conductometer, density was measured with a densitometer. The acidity of solution was calculated according to the relation between acidity and conductivity, and density.

1) Measurement of density Density was measured by a Meiteler-SICS-BA-e-11780711C balance with detection limit of 0.1 mg.

Volume of sample was always 1 mL. 2) Electrodeless conductometer for small volume of sample Commercial electrodeless conductometers have the following disadvantages: (1) at least 150 mL

solution is needed for once measurement due to the bigger sensor, which leads to produce much more liquid waste for rinsing probes, thus especially not being suitable for measurement of samples with radioactivity. (2) Signals can,t be directly sent to the computer, which takes longer measuring time. A commercial electrodeless conductometer was modified with smaller volume of sample (1 mL).

Sensor of typical electrodeless conductometer consists of two insulated big ring coils. To accurately measure conductance, the two ring coils have to be wholly immersed in solution, which leads to consume bigger volume of solution, and to rinse the coils between each measurement. These disadvantages are not suitable for determination of radioactive samples.

In this work, a typical electrodeless conductometer was modified, and a special sample box and a special sample cell was designed, in which body of sample box and upper cover and bottom of sample cell are all stainless steel, thus forming a closed circuit. Sample cell filled with solution was put into ring coils vertically. Because the measured solution did not contact with ring coils, it is not necessary to rinse the ring coils. Volume of the measured solution is also lowered to 1mL.

Mixed uniform design was adopted, 30 samples with 0-90.0 g/L U( ) and Ⅵ 0-90.0 mol/L nitric acid were prepared. Using multivariate data regression technique, a model between density, conductance and concentration of nitric acid was built.

Development of an Analytical System for Rapid, Remote Determining Concentration and Valence of Uranium and Plutonium

LIU Huan-liang, FU Jian-li, WANG Ling, ZHANG Li-hua


Concentrations and valence of U and Pu directly shows whether the Purex process is under normal conditions or not. It is necessary to monitor concentrations and valence of U and Pu in real-time.


Purposes of this work is to develop an analytical system designed to measure concentrations and valence of U and Pu in real time and remote way, which will create good conditions for building analytical methods of U and Pu in the future.

This system consists of light sources, spectrometers, multi-way light switcher, fiber optic cables, sample cell, and controlling computer. Light sources containing LED and halogen-tungsten emit 400- 17 00 nm light continuously at steady intensity. The composed light is transmitted to sample cell by a Y-type fiber optical cable. After sorption by sample, the transmitted light is collected by another Y-type fiber optical cable, transmitted light signal is acquired by a VIS multi-channels spectrometer and a near infrared spectrometer. The light route is shown in Fig. 1. The performance of the system is tested.

1) Accuracy of wavelength: Difference between characteristic wavelength of standard material measured by this system and wavelength showed by the certificate is less than 0.5 nm in the range of 400-900 nm, and less than 1.0 nm in the range of 900-1 700 nm.

2) Repeatability of wavelength: The maximum standard deviation of heights at characteristic band is less than 0.08nm in the range of 400-900 nm, and less than 0.02 nm in the range of 900-1 700 nm.

3) Repeatability of absorbance: The maximum standard deviation of absorbance at characteristic band is less than 0.003 A in the range of 400-900 nm, and less than 0.001 A in the range of 900-1 700 nm.

4) Spectral range: The spectral signals are acquired in the range of 400-1700 nm. 5) Resolution of wavelength: The resolution of wavelength is better than 0.2 nm. 6) Straightness of baseline：The maximum vibration of absorbance in the range of 400-1 700 nm is

less than ±0.01 A. 7) Stability of the system: The maximum drift is 0.009 nm among 8 bands (414, 440, 476, 480, 564,

831, 1 300, 1500 nm) in 2 hours. All performances meet requirements, which build solid foundation for study on analytical methods in

the following days.

Fig. 1 System for rapid and remote determination of concentration and valence of U and Pu

Study of Multi Total Reflection X-ray Fluorescence Spectrometer

KANG Hai-ying, QIAO Ya-hua, HUANG Qing-liang (Department of Radiochemistry)

A total reflection X-ray spectrometer was set up, in which Mo tube was used as excitation source, Zr

with the thickness of 100 µm was as filter, and λ/20 glabrous silicon was as reflector, λ/100 glabrous


silicon was as sample carrier. The “AXIL”, a software recommended by International Atomic Energy Agency, was choosed to process experimental data. Before reaching the sample carrier, X-ray had been reflected totally for many times, which not only shorten the distance between X-ray tube and the sample, but also enhanced the primary X-ray, thus improved the excitation efficiency and measurement sensitivity.

Under the excitation current of 10 mA, and excitation voltage of 25 kV and 45 kV, the detection limits and sensitivities of Ca, Ti, V, Cr, Mn, Fe, Ni, Cu, Ga, Y, Sr were tested, and shown in Table 1.

Table 1 Detection limited (DL) and sensitivity (S)

Excitation

voltage/kV Element

Character

spectrum S/μg－1 DL/ng

Excitation

voltage/kV Element

Character

spectrum S/μg－1 DL/ng

45 Ca Kα 0.025 2234 25 Ca Kα 0.012 3823

45 Ti Kα 0.14 407 25 Ti Kα 0.016 3231

45 V Kα 0.2 297 25 V Kα 0.039 1553

45 Cr Kα 0.21 266 25 Cr Kα 0.043 1390

45 Mn Kα 0.2 336 25 Mn Kα 0.061 996

45 Fe Kα 0.38 177 25 Fe Kα 0.071 947

45 Ni Kα 0.61 108 25 Ni Kα 0.13 498

45 Cu Kα 0.33 192 25 Cu Kα 0.12 596

45 Ga Kα 0.35 289 25 Ga Kα 0.13 620

45 Y Kα 0.26 963 25 Y Kα 0.10 1007

45 Sr Kα 0.21 954 25 Sr Kα 0.04 1074

A series of reference solutions with various concentrations of metal ions were prepared. 20 µL reference solution and Ga solution were pipetted onto a carrier and dried under infrared lamp. Then the loaded carrier was determined by the spectrometer. The plotted working curves, with good linearity for each element except for Ca, were shown in Fig. 1. A sample contained 2 µg metal ion was measured repeatedly for six times, the relative standard deviation was between 5%-16%.

Fig. 1 Working curves


Study Progress of On-line Monitoring Device for Uranium and Plutonium by XRF

KANG Hai-ying, ZHENG Wei-ming


An X-ray fluorescence spectrometer was designed and set up, which was used to determine uranium and plutonium on-line in reprocessing process stream.

Uranium in aqueous and organic phase, plutonium in aqueous were measured by using the device, the correlative factors R2 were 0.999, 0.998 and 0.999, respectively. For the aqueous samples of uranium with concentration lower than 20 g/L, and of plutonium lower than 0.5 g/L, the determined error was more than 10%. For aqueous uranium of 40-100 g/L and plutonium of 0.9-24 g/L, the determined error was less than 10%. 6 times repeated determination of 0.9 g/L plutonium aqueous solution showed the RSD was 0.8%.

For the mixture of uranium and plutonium, due to the interference of spontaneous X-ray of plutonium on X-ray fluorescence of uranium, further study should be focused on the method to reduce the influence of plutonium on uranium by improving the device and determination method.

Study on Radiochemical Separation and Measurement of Half-life of 88Kr

YANG Zhi-hong, ZHANG Sheng-dong, YANG Lei, DING You-qian, SUN Hong-qing, MA Peng (Department of Radiochemistry)

88Kr is one of the important gaseous fission products for determining the burn up of nuclear fuel with a short half-life, high fission yield and high branch ratio of γ-ray. Due to the more uncertainty of evaluated data and rare experimented data, its half-life can not satisfy with the practical demand. It is essential to measure the value with high accuracy.

Analyzing the related decay chains of 88Kr, the measurement will be interfered with 138Xe, 135Xe and 135I if the gas part was taken directly from the irradiated uranium target. Focusing on this work, the separation between Kr and Xe was studied, and the half-life of 88Kr was determined.

Based on the literature investigations, a plan of separating Kr and Xe was made by using active carbon adsorption under low temperature, The separation conditions were studied by using 85Kr and 125Xe radioactive tracers, and the results showed that the active carbon can adsorb Xe completely under the temperature of 0 but the Kr can not be adsorbed, thus the Kr and Xe can be separated quickly. The

recommend 88Kr radiochemical separation procedure was given through optimizing the separation conditions. A set of equipment was designed which have a main part of column separation. It has characters of simple and compact configuration, well sealed and easy to be controlled and operated. Using this equipment, real samples was separated from the irradiated uranium target. The chemical yield of Kr is more than 90% and the decontamination factor of Xe is better than 104. The whole procedure can be finished in less than 5min, which can totally meet the needs of the half-life measurement, and no Xe and I character γ-ray was found in the γ spectra of the product.


For 88Kr sample extraction, uranium targets were irradiated in the reactor, non-radioactive Kr gas was added in 88Kr separation procedure as carrier and long-life 85Kr isotope were added as tracer at the same time. Thus, the separated 88Kr sample contains 85Kr that can monitor the air-tight properties and can be the inner- standard in the 88Kr data processing.

The continuous trace was done to three radiochemical purity samples of 88Kr by single digital HPGe γ-detector and double detectors in these measurements. The linear equations were calculated by count rate method, internal standard method and external reference method in respective experiment data processing. Further data processing was done by recursive method. The half-life of 88Kr was determined as weighted average of the three experiments. Lastly, (2.796±0.006) h which is a high accuracy experiment data, was recommended as half-life of 88Kr.

A Method for Determination of 99Tc in Soils Using TEVA Resin

YANG Su-liang, SONG Zhi-jun, DING You-qian, MAO Guo-shu, YANG Zhi-hong, SHU Fu-jun, YANG Lei, ZHANG Sheng-dong


99Tc is an artificial long-lived pure beta emitter with maximum beta particle energy of 292 keV. It is

produced with high yield (~6%) during nuclear fission of 235U and has a radiological implication and environmental risk. In aqueous solutions, where no reducing agents are present, 99Tc exists as a pertechnetate ion, TcO4

-. Technetium in this form is very mobile in soils, ground and surface waters. Technetium behaves as a nutrient analogue and may enter biosphere easily. Since the seminar on “The Behavior of Technetium in the Environment” organized by the Commission of the European Communities in 1984, 99Tc has become one of the most concerned radionuclides in environment. Analyses of environmental samples should be therefore routinely performed near nuclear facilities to monitor the concentration of 99Tc in the environment. The aim of this study was to prepare a radiochemical analysis method suitable for the separation and determination of 99Tc from environmental soil samples. The key of the method is a careful chemical separation from any other β-emitter.

The soil samples are leached with 1 mol/L nitric acid and separated using TEVA Resin prior to liquid scintillation counting. The procedures are as follows:

1) Soil sample pretreatment. If necessary, grind the sample or use pulverizer to homogenize sample. The samples are dried by oven at a temperature of 80 .

2) Soil sample preparation. Weigh up to 10 grams of the soil sample on an analytical balance. Transfer the soils to a 250 mL flask using 10 mL of 1 mol/L HNO3. Analyze each sample with and without adding Tc-99 spike to determine chemical recovery.

3) Extraction of 99Tc from soil sample using HNO3. Add 40 mL of 1 mol/L HNO3 and 1 mL 30% H2O2 to each beaker. Put the flasks on a hot plate and heat under reflux to 80 for 4 h. Remove each

flask from the hotplate and allow to cool. Transfer the solution and solids to a centrifuge tube and centrifuge for approximately 10 min at 2 000 r/min. Decant supernatant into a 150 mL beaker. Add 10 mL 1 mol/L HNO3 to the centrifuge tube. Vortex and centrifuge for 5 min at 200 r/min. Add supernatant to the 150 mL beaker. Discard solids to the appropriate waste stream. Add 1-5 mL 30%H2O2 and heat to 80

with stirring until the effervescence disappears. If necessary, filter the samples using Super-450 filer paper.


4) Adjustment of pH. Adjust pH to 2 slowly and with stirring using 4 mol/L NH4OH. 5) Eichrom TEVA Resin column separation. Place a TEVA Resin column (φ8 mm×40 mm) in a

column rack. Pipette 5 mL of 0.01 mol/L HNO3 into each TEVA Resin column to condition the resin and allow to drain. Transfer each sample leachate to the TEVA Resin column, allow the leachate to flow through. Pipette 25 mL 0.01 mol/L HNO3-0.5 mol/L HF solution into each column, allow to drain.

6) Preparation of measurement source and the liquid scintillation counting. Pipette 20 mL of 8 mol/L HNO3 to the columns. Collect the effluent and heat to near dry on a hot plate. Dissolve residue using up to 3 mL 0.1 mol/L HNO3. Transfer the dissolution to a 20 mL liquid scintillation vial and add 15 mL scintillation cocktail to the vial, cap, and shake well. After standing in dark places for several hours, the measurement source is counted using a liquid scintillation analyzer.

In conclusion, the whole analysis process prepared in this study is quite simple and fast. The chemical recovery of 99Tc is greater than 90%. With the quantity 10 g and counting time 1 h, the minimum detectable concentration was 3.5 Bq/kg and quite qualified for most environmental samples. The presence of 90Sr-90Y, 137Cs and natural Uranium doesn’t interfere with the method. Moreover, the TEVA Resin could be applied repeatedly and the cost could be considerably reduced consequently.

A Convenient Method for Synthesis of 2-allyloxymethyl-18-crown-6

YANG Su-liang, SONG Zhi-jun, YANG Jin-ling, DING You-qian, ZHANG Sheng-dong (Department of Radiochemistry)

Extraction chromatography has been proven a sufficient method for the isolation of 90Sr from large

quantities of inactive matrix constituents and from a number of interfering radionuclides. The commercial Sr-SpecTM resin was made of 4, 4′, (5′)-di(t-butylcyclohexano)-18-crown-6 (DtBuCH18C6) adsorbed in the pores of the inert polymeric material XAD-7. The interaction between DtBuCH18C6 molecule and XAD-7 was intermolecular forces, i.e., van der Vaals forces, which can hold non- or weak-polar molecules together. Insignificant leakage of DtBuCH18C6 in acid solution was expected. A novel extraction chromatography material based on silica , in which 18C6 was grafted to silica with covalent bonds, is expected to give improved qualities and better chemical resistance. In this study, a convenient method for preparing 18-crown-6 ether bearing substituent includes pendent groups which could be used to form a covalent bond with surface Si-OH is described.

Fig. 1 Synthesis of 2-allyloxymethyl-18-crown-6


As can be seen in Fig. 1, allyloxymethyl oligoethylene glycols (3), starting materials for the cyclization, were prepared in one step from allyl 2, 3-epoxypropyl ether (1) and pentaethylene glycol (2) in the presence of potassium hydroxide. Potassium hydroxide was dissolved in 2 under stirring at 80 .

To the resulting wine-red solution, 2 was added dropwise over a period of 2 h at the same temperature. The crude glycol product, obtained as viscous brown liquid, is possibly composed of two isomers (3 and 3′). It was purified without mixture separation by thin-film molecular distillation after neutralization with dilute sulfuric acid, because both isomers should afford the same substituted crown ether by intra- molecular cyclization. Cylization of the glycols 3 to 2-allyloxymethyl-18-crown-6 (4) was accomplished using p-toluenesulfonyl chloride as catalyst in the presence of pulverized potassium hydroxide in dioxane. The crude product was purified by molecular distillation under reduced pressure to give a GLC-pure 4: 1H NMR (CCl4): δ 6.0 (m, ＝CH, 1H); 5.2-5.3 (m, CH2＝, 2H); 4.0-4.1 (d, C＝CCH2O, 2H); 3.6-3.9 (m, OCH2CH2O, OCH2CHCH2OCC＝C, 25H). Anal. Calcd for C16H30O7: C: 57.47; H: 9.04. Found: C: 56.73; H: 8.88.

The method gave good yield of more than 60% without attempt to optimize the reaction conditions.

Determination of Stability constant of Coordination Reaction of 2-allyloxymethyl-18-crown-6 with Sr2+ in Water

YANG Su-liang, SHU Fu-jun, SONG Zhi-jun, YANG Lei, LIANG Xiao-hu,

DING You-qian, ZHANG Sheng-dong (Department of Radiochemistry)

Strontium-90 is one of the most concerned radionuclides in environmental radiochemistry.

Numerous methods have been described for the determination of radiostrontium in biological and environmental samples. An essential step in all of these methods is the selective separation of strontium, both to remove radionuclides which may interfere with subsequent β-counting and to free it from the large quantities of inactive substances typically present. 18-crown-6 ether and its derivatives are well known as selective ligands for Sr2+ ion. In this work, the coordination reaction of 2-(allyloxymethyl)-18-crown-6 with Sr2+ ion has been studied by conductometric titration and computer fitting. The stability constant of coordination compound was obtained.

18 mL 2.5 mmol/L Sr2+ solution was added to a closed 25 mL glass flask with inlet for electrode. Put the flask in a (25.00±0.05) water bath. A magnetic stirrer was used for the measurements. 0.05 mol/L

2-(allyloxymethyl)-18-crown-6 solution was added from a micrometer burette through a springe needle. Each reading of conductivity was obtained till complete equilibrium after each addition. The experimental data show that molar conductivity of the solution decreases considerably as the crown ether concentration rises. The reason of this phenomenon is that the mobility of coordination compound is lower than that of the hydrated Sr2+ ion. Fig. 1 demonstrates that molar conductivity of the solution does not reach a flat even with CL/CM above 2.

With computer fitting from the data of Table 1, the stability constant obtained of the coordination compound in water is 355, which illustrates that 2-(allyloxymethyl)-18-crown-6 has a considerable coordination ability with Sr2+ ion even in water.


Fig. 1 Curve of Sr(NO3)2 titrated by 2-(allyloxymethyl)-18-crown-6

Study on Performance of EmporeTM Technetium Rad Disks

YANG Su-liang, LIANG Xiao-hu, YANG Lei, MAO Guo-shu,

DING You-qian, ZHANG Sheng-dong (Department of Radiochemistry)

EmporeTM Technetium Rad disks produced by 3M Company contain GD-1 sorbent loaded on

particles that are embedded in an inert PTFE matrix. In this study, several experiments have been accomplished to evaluate the performance of EmporeTM Technetium Rad disks.

The effect of flow rate was evaluated by vacuum filtering spiked DI water through the Tc RAD disk. The extraction efficiency was more than 99% at flow rates up to 240 mL/min using a solution volume of up to 2 L. Disk was loaded with as much as 700 nCi of 99Tc, with no apparent breakthrough.

A test was performed to look at the effect of acidity on the performance of the Tc RAD disks. A series of samples with different pH values spiked with a known amount of 99Tc were passed through Tc RAD Disks at a flow rate of 25 mL/min. The effluent was subsequently counted by liquid scintillation counting. The results demonstrated that Tc retention on the Tc RAD disks was more than 99% for all samples with pH value from 0 to 14.

We next design a experiment to evaluate the effect of water volume passed through the Tc RAD disk versus retention of 99Tc. 10 L DI water spiked with a known amount of 99Tc was passed through the Tc RAD disk at a flow rate of 25 mL/min. Collect the effluent in 200 mL fractions. 99Tc in all fractions was measured by liquid scintillation counting. The results show that 99%+ of the 99Tc was retained on the disk in all fractions, implying the retention of 99Tc was not affected by volume of water processed up to 10 L.

Another test completed on the Tc RAD disks to look at the discrimination of the Tc RAD disk against other beta emitting radionuclides which may interfere with the liquid scintillation counting of 99Tc. DI water (250 mL) spiked with either 137Cs or 90Sr-90Y was passed through the Tc RAD disk at a flow rate of 25 mL/min. The disks were then counted by liquid scintillation counting. 5.7% of the 137Cs, 10.9% of the 90Sr-90Y were retained by the Tc RAD disk.

And the counting efficiency of 99Tc on DI water disks by liquid scintillation was greater than 85%.


Study on Performance of EmporeTM Strontium Rad Disks-Ⅱ

YANG Su-liang, SONG Zhi-jun, LIANG Xiao-hu, YANG Lei, DING You-qian, ZHANG Sheng-dong


EmporeTM Strontium Rad disks produced by 3M Company contain a strontium-selective crown ether

extractant loaded on silica particles that are embedded in an inert PTFE matrix. The disks allow aqueous solutions to pass through in high flow rate. It makes them especially suitable for the analysis of environmental aqueous samples with large volume. The method is more effective and less time- consuming compared to traditional radiochemical analysis method.

In a previous work, the effect of different acid type and acidity on the 90Sr uptake efficiency in solutions has been evaluated and its Sr adsorption capacity has been determined. In this paper, several experiments have been accomplished to evaluate further the performance of EmporeTM Strontium Rad disks.

The excellent dynamic character is the most distinct advantages of the solid phase extraction disk method. But the performance of the disks under fast flow rate has to be validated. The effect of flow rate was evaluated by vacuum filtering 90Sr-90Y spiked 2 mol/L HNO3 through the Sr Rad disk. The flow rate tested was 20 mL/min to 100 mL/min. The effluent collected was subsequently counted by liquid scintillation counting after 4 weeks. The results showed that Sr retention on the Sr RAD disks was consistently more than 99% for all samples at flow rate up to 100 mL/min, indicating a quantitative extraction by Sr Rad disk.

3M Corp. recommends that the disks should be counted by either proportional or liquid scintillation counting. The two methods have both been proven effective. But the counting efficiency of the proportional counting may vary a lot with different drying condition. Liquid scintillation counting is simpler and has a lower detection limit. In this study, the counting efficiency of 99Sr on Sr rad disks by liquid scintillation has been determined. The results showed that the counting efficiency was close to 100%, indicating that the self-absorption by the disks doesn’t interfere with the counting efficiency.

Other than 90Sr-90Y, natural uranium, 137Cs and 99Tc could often be found in environmental samples. We next designed a study to look at the discrimination of the Sr Rad disk against these radionuclides. The results demonstrated that only 0.3% of natural uranium and 1.2% of 137Cs were retained on the disk. The retention of 99Tc is much higher, reached 6%. So, the effect of 99Tc is not neglectable with the samples that contain considerable amount of 99Tc.

Sequential Separation of U, Np and Pu From Environmental Samples

WANG Xiu-feng, DING You-qian, ZHANG Sheng-dong, SUN Hong-qing, MA Peng, MAO Guo-shu (Department of Radiochemistry)

Affected by nuclear testing and nuclear reactor accidents, the release of radioactive substances into

the environment, especially long-lived radionuclides including U, Np and Pu can cause great harm to the


environment, ecology and human health. As U, Np and Pu in the environment at low levels, the analysis needs to consider isobaric interference, so we need to sequential separate U, Np and Pu before the measurement.

The digest method of environment sample, the method to extracte U, Np and Pu from matrix elements and the method to separate U, Np and Pu by HPLC from each other were studied in this work, a sequential separation method of U, Np and Pu from environmental samples was established at last, the process is as follows.

1) Digesting samples. The environmental samples were digested with HNO3-HCl-HF mixture solution by temperature programme in a sealed microwave digestion device, the solution cooled into PTFE beaker, add some HClO4, evaporated in the electric hot plate to remove the fluoride ion. The residue was dissolved with 5 mol/L HNO3.

2) Concentrate samples. Adjusted the pH to 11 with NaOH solution to make Fe(OH)3 precipitation, concentrated U, Np, Pu and removed some matrix elements, centrifuged and discarded the supernatant.

3) Extracted U, Np and Pu. The precipitation was dissolved with 5 mol/L HNO3-0.05 mol/L KMnO4, heated to oxidate Np and Pu both to hexavalent. The solution was injected on a TBP extraction column, washed matrix elements with 10Vc (1Vc=3 mL) 5 mol/L HNO3, and desorpted U, Np and Pu with 7Vc 0.35 mol/L HNO3.

4) Sequential separate of U, Np and Pu. The U, Np, Pu fraction was converted to 0.01 mol/L α-HIBA media, and separated by high performance liquid chromatography on a C18 reversed-phase column. The flow rate of mobile phase was 1.5 mL/min. After injection, the column was washed by 0.025 mol/L α-HIBA pH=3.80 within 0-5 min to collect Np, then washed by 0.1 mol/L α-HIBA pH=3.80 within 5-12 min to collect Pu, finally washed by 0.1 mol/L α-HIBA-25% methanol pH=4.00 within 12-20 min to collet U, hence to achieve the separation of U, Np and Pu from each other.

To verify the reliability of the process, a small amount of 237Np and 239Pu tracer was added to the earth samples, and dealed with the process, the chemical yield of Np and Pu were both better than 90%. The Uranium content of the samples was measured by MC-ICP-MS, the results are accordance with the ones determined by neutron activation method.

Separation of Uranium From Spent Fuel Solution in Burnup Measurements Process

YANG Lei, MAO Guo-shu, ZHAO Ya-ping


In order to establish an automatic radiochemistry separation procedure of U from spent fuel solution,

a method of separating U quickly and effectively from the feed solution is needed. TBP exctraction chromograph method had been adopted to separate U from spent fuel solution. In

order to acquire good condition, we researched the sorption behaviour of uranium and fission products on anion exchangers from 4 mol/L HNO3 solutions. In our experiment, depletive uranium, fission products were used as the tracers. 1AW was used to simulate the feed solution, and 235U was added to be mass spectrum diluent. Ferrous sulphamate and hydrazine nitrate were selected for eliminating plutonium effectively.

TBP levextrel resin (75-120 μm) filled to the columns (φ4 mm×130 mm) with the volume of column


(Vc) 1.5 mL. The elutions were operated at flow rates of 0.33 mL/min. Pu, fission products, uranium were measured with liquid scintillation spectrometer，HPGe γ-spectrometers, mass spectrograph，respectively.

The experiment results are shown as following: Fission products are adsorbed poorly on on TBP column. U is adsorbed strongly on TBP column in 4 mol/L HNO3 solutions. U is desorbed with distilled water from TBP column and the recovery of U is more than 90%.

In above work, a separating method of U from the feed solution was built as follow. 1) The quantitative 1AW solution was put into a polypropylene tube, then the solution was adjusted

to 4 mol/L HNO3-0.05 mol/L Fe(NH2SO3)2-0.05 mol/L hydrazine nitrate and was stayed for 15 min. 2) The solution was added to TBP column, collecting effluent in plastic bottle. 3) The column was eluted with 20Vc 4 mol/L HNO3 and the elution was discarded. 4) U was desorbed from the TBP column with 6Vc water and was collected into a tube. U was

measured with liquid scintillation spectrometer, HPGe γ-spectrometers, mass spectrograph, respectively. The results indicate the concentration of 238U is 66.34 μg/g with uncertainty of 0.73%, and the

concentration of 235U is 0.68 μg/g with uncertainty of 1.04%. The chemical yield of U is more than 90%. Decontamination factor for 137Cs is 3.03×105. And the decontamination factor for Pu is more than 102.

Separation of Molybdenum From Spent Fuel Solution in Burnup Measurements Process

ZHAO Ya-ping, YANG Lei, MAO Guo-shu


In order to establish a kind of automatic radiochemistry separation procedure of nuclide 100Mo from

spent fuel solution in burnup measurements process, a method of separating Mo quickly and effectively from the feed solution is needed. In the studies, the solution of irradiated target prepared high enrichment 235U was used instead of spent fuel solution, two extraction solvents of 1% α-benzoin oxime-ethyl acetate and 0.1% α-benzoin oxime-chloroform are compared. A lot of experiments showed both of extractants had very high extracting efficiency, but the later was more suitable for automatic radiochemistry separation procedure. According above works, a separating method of Mo from the feed solution was build as follow.

1) A certain volume of feed solution was converted to 1 mol/L HNO3 medium. 2) The feed solution was adjusted to 1 mol/L HNO3-0.01 mol/L HF system, adding the same volume

equilibrated 0.1% α-benzoin oxime-chloroform (1 g/L), to the feed solution, and extracting for 1 min by shaking, and centrifuging 1 min. After phase separation, the organic phase was taken out.

3) The organic phase was washed with the same volume 1mol/L HNO3 for 1 min and centrifuged for 1 min. After phase separation, the organic phase was picked up.

4) Mo was back-extraction with 2 mol/L NH4OH for 1 min from the organic phase, and centrifuged for 1 min. After phase separation, the aqueous phase was withdrawn from the centrifuge tube.

5) A small quantity of organic phase, remaining in aqueous phase, was removed with concentrated HNO3 and HClO4. Finally, the aqueous phase was converted to 0.35 mol/L HNO3 medium.

6) The product of Mo was measured with HPGe γ spectrum.


To prove reliability of above procedure, a quartz target was prepared with 10 mg U3O8 (enriched isotope of 235U is 90%). The target was irradiated for 1h in microreactor (thermal neutron flux rate is 7×1011 cm－2·s－1), and then it was cooled for 5 days. After the fission gas was exhausted from the target placing the gas separating system, the target was dissolved with the concentrated nitric acid and converted to 2 mL 1 mol/L HNO3 medium.

The product of 99Mo was obtained from a certain quantity of feed solution by the chemical procedure and measured through HPGe γ spectrum. The results showed the chemical yield of 99Mo is more than 90% and the method had high decontamination factor for the interferential nuclides, such as 141Ce, 132Te, 140La, 103Ru, 147Nd, 140Ba, 95Zr, 132I, 137Cs, the decontamination factor was >3.1×104, >5.0×104, >6.8×104, >2.0×104, >5.6×103, >2.7×104, >9.1×103, >2.7×104 and >5.4×105, respectively. As a result, the procedure has high yield and is able to achieve chemical separation quickly, which means the method is easy to establish a kind of automatic radiochemistry separation procedure.

Content of Transuranium Nuclide in Process of Irradiating Thorium

MA Peng, MAO Guo-shu (Department of Radiochemistry)

Currently, sufficient nuclear fuel supply is most important problem with the nuclear power grow rapidly,

so the use of thorium fuel is being put on the agenda. The applicability of thorium as a power reactor is based on a (n, γ) reaction on 232Th. The consequent nucleus, 233Th, is unstable and decays by twice beta release into 233U. It can be converted to transuranium nuclide by capturing several neutrons. The transuranium nuclide must be considered for the reactor design and irradiated fuel reprocessing. So the content of transuranium nuclide produced in irradiation process of thorium placed in thermal and fast reactor was calculated.

The key issues are the calculation of the equivalent cross-section of some nuclear reactions in reactor. The equivalent cross-section can be obtained by Formula (1), σ(E) is excitation function of nuclear reaction which comes from ENDF/B- .0 database, Ⅶ Ф(E) is neutron energy spectrum of reactor.

( ) ( )d

( )

E EE

E

σ Φσ

Φ=

∫

∫ (1)

Because of the complex neutron energy spectrum and excitation curve, curve fitting is very difficult by one function.So piecewise functions was be use to solve this problem. The neutron energy spectrum function Ф(E) and excitation function have been obtained by piecewise functions, and the equivalent cross-section has been calculated by Formula (1). The content of transuranium nuclide were calculated by ORIGEN2 code with 1 000 g 232Th and a flux rate of 1.0×1014 cm－2·s－1 in thermal and fast reactor. The part of data indicate that the content of neptunium, plutonium and americium rise with the increase of irradiation period. The content of element is different in same reactor with same irradiation period, and the content of neptunium is maximum. The content of transuranium nuclide produced in fast reactor is more than that of thermal reactor, and this difference will become evident with the increase of irradiation period.


Morphology Characterization of Uranium Particles From Laser Ablated Uranium Materials

ZHANG Yan, ZHAO Yong-gang, WANG Cheng


In the study, metallic uranium and uranium dioxide material were ablated by laser beam in order to simulate the process of forming the uranium particles in pyrochemical process. The morphology characteristic of uranium particles and the surface of uranium material were represented by Scanning Electron microscopy and Transmission Electron microscopy. The results indicated that these two kinds of materials were melted and the surface of metal uranium presented a series wavelike segments and the surface of dioxide uranium presented pellets aggregation under the bombardment of laser beam (Fig. 1). The irregular micron-sized particles and about 1 micrometer spheric particles occurred in ambient environment (Fig. 2).

Fig. 1 The surface microscopic structures of the dioxide uranium(a) and metal uranium materials (b)

before (1) and after (2) laser ablation (×250, ×1 000)

Fig. 2 The SEM images of particles from laser ablating the dioxide uranium (a) and metal uranium materials (b) (×10 000)

The results concluded that regular uranium oxides spheres with high density characterize

pyrochemical process, which are quite different with particles from low temperature denudation. They were characteristic of pyrochemical process based on particle morphology.

Studies on Measurement of Impurities in Uranium Sample

ZHU Liu-chao, ZHAO Xing-hong, WANG Tong-xing, ZHAO Yong-gang, ZHANG Ji-long, JIANG Xiao-yan


The impurities of nuclear material produced by different factory usually has its characteristic information which can be used to trace to the source of nuclear material.Because of the complexity of


emission spectrum,uranium will have a serious interferes on the measurement of impurities.therefore, impurities have to separate from uranium before measurement. This work aims to separate impurities from uranium using TBP extraction chromatography, and the recovery of impurities was obtained by the measurement using MC-ICPMS.

The TBP resin was marinated in Mili-Q water for 24 h after washing several times.then the resin was packed in a quartz column. Conditioning of the column was carried out passing Mili-Q water, 20 mL 0.5 mol/L HNO3 and Mili-Q water to convert the resin to be neutral. Finally 20 mL 5 mol/L HNO3 was passed through the column to balance the resin. A blank test was carried out by passing 20 mL 0.5 mol/L HNO3 through the resin. The elution was collected and converted to water-solution that can be measurement directly by MC-ICPMS.The impurities solution was treated using the same procedure as the blank.

The measurement result showed that the content of Mg and Cr is much higher than we had imagined.Through altering the condition of nitric acid used, beaker and fume hood, it was showed that the contribution of Mg and Cr in the blank was mainly consisted of the contribution of the environment in the fume hood and the contribution of nitric acid used.The recovery of 89.2%, 91.3%, 93.8%, 94.1% was achieved for Mg, Cr, Ni and Cu after separation of TBP extraction chromatography.

Monitoring Fallout From Fukushima, Japan After Nuclear Accident

LI Jian-hua1, XU Xu-tao2, LI Hang2, DIAO Li-jun3, WEN Fu-ping2, LIU Guo-rong1,

ZHAO Yong-gang1, WANG Chen1, LI Jing-huai1, LI Sao-wei1, WANG Fan1, CHEN Yan1, SHEN Yan1, LIANG Qing-lei1

(1. Department of Radiochemistry; 2. Department of Radiation Safety Research;

3. Department of Radiation Metrology)

In this work, on March 23rd, 2011, following the radioactivity releases after the nuclear accident in

Fukushima, Japan, the first arrival of the airborne fission products 131I in Heilongjiang province the northeast of China, were detected, and several man-made radionuclides (such as 131I, 132I, 132Te, 134Cs and 137Cs) have also been detected from March 25th to May 29th 2011 by monitoring local air samples in Miyun county, Beijing. Within an ad hoc monitoring program in the radioactivity measurements laboratory at CIAE, a high-performance Compton suppression gamma-ray spectrometry system has been used by this work, for identifying trace radioactivity signals of short-lived isotopes indicating Fukushima fallout. Two high volume samplers with flow rates about 0.17 m3/h and 2 m3/min were used simultaneously. The sampling was carried out continuously.

The first signs of diluted airborne activities appeared over Beijing after one week of first arrival in Heilongjiang province. The highest detected activity is (8.72±2.62) mBq/m3 of 131I, and (0.91±0.27) mBq/m3 of 137Cs, respectively, which is much lower than alarming limits of National Standard, and also below the highest value (131I, 290 mBq/m3; 137Cs, 15 mBq/m3) obtained in the same area in Beijing and CIAE, Beijing, during the period of Chernobyl nuclear accident. The 134Cs/137Cs ratio is about 1﹕1, which indicated the 137Cs is “recent”, not “old”.

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radioactive Waste Treatment and Disposal 161

Radioactive Waste Treatment and Disposal

Preparation of Inorganic Sorbent KNiFC and Its Application

YOU Xin-feng, ZHANG Zhen-tao, MA Hui (Department of Radiochemistry)

137Cs which has high fission yield about 6.14%, long half-life, and 661.7 keV γ-ray exists in 1AW,

nuclear plant liquid waste, nuclear facilities decommissioning waste, radioactive lab liquid waste and other radioactive liquid waste. 137Cs can migrate into environment because of its single chemical state. 137Cs needs treatment and disposal for ensuring the public health and safety, and also the nuclear industry sustainable development. In this program, an inorganic sorbent KNiFC which absorbs only 137Cs almost in the radioactive liquid was prepared. Its preparation is followed below: added 0.3 mol/L K4Fe(CN)6- 1.8×10－3 mol/L CH3COOH solution to 0.5 mol/L Ni(NO3)2 slowly which dropping speed was about 0.5mL /min, and their volume ratio was 1﹕2.4, the mixture solution was bathed in the freezing water with 800±50 r/min stirring continuously. After dropping solution, the reaction was carried on 10-15 min, then stilled the mixture sample at 110 for several hours to precipitate the sample. Then cleaned the precipitation using deionized water and at last dried the precipitation at 110 , and gained the sorbent KNiFC. In this program, the absorption properties of KNiFC sorbent were tested through the batch test method. It was shown that the selectivity for 137Cs was very high with Kd-value above 104 mL/g, and its saturated absorption capacity for cesium was about 0.87mmol/g at pH＝5.5-10 range. Its absorption for cesium obeys Langmuir curve. The dynamic cloumn experiment was also carried out and operation condition was followed below: Column size was φ5 mm×100 mm, and added 0.5 mL KNiFC by wet method, the flow rate was 8.6 mL/h, the feed solution was simulated nuclear plant waste pH＝5.0, 137Cs 3.0×104 Bq/L, and about 4 L feed solution was treated through this column and the outflow liquid was measured by an α/β detector, and a DF more than 103 gained. During the experiment, the sorbent shows good hydraulic and mechanical performance. As a result, the preparation of the sorbent was simple and its selective for cesium was high with good hydraulic and mechanical performance, so it can be applied for treating or extracting 137Cs from varieties of radioactive liquid waste.

Preparation of Inorganic Sorbent for Strontium and Its Application

YOU Xin-feng, ZHANG Zhen-tao, MA Hui (Department of Radiochemistry)

90Sr, which has high fission yield, long half-life, and β radiation exists in 1AW, nuclear plant liquid

waste, nuclear facilities decommissioning waste, radioactive lab liquid waste and other radioactive liquid


waste. 90Sr is of highly radioactive toxicity, and it usually precipitates at the bones and lymph system of the body. Therefore, 90Sr needs treatment and disposal for ensuring the public health and safety, and also the nuclear industry sustainable development. In this program, an inorganic strontium sorbent which absorbs only 90Sr almost in the radioactive liquid was prepared. Its preparation was followed below: added 0.1 mol/L MnCl2 and certain concentrated NaOH solution to 0.1 mol/L KMnO4 slowly, which molar ratio was 1﹕1.5﹕2, and the reaction was described as below:

2KMnO4+3MnCl2+4NaOH+8H2O＝5Mn(OH)4(s)+2KCl+4NaCl The reaction was carried through at 40 for 2 hours with continuous mixing, and the pH of mixture

solution was kept in the range of 10-12 by adding NaOH solution. When the reaction was finished, stilling the mixture sample for several hours to precipitate. At last dried the precipitation at 110 , and the sorbent was gained. In this program, the absorption properties of the strontium sorbent were tested through the batch test method. It was shown that the selectivity for 90Sr was very high with Kd about 5.0×104 mL/g, and its saturated absorption capacity for strontium was about 0.73 mmol/g at pH＝5.5-10 range. Its absorption for strontium obeys Langmuir curve. The dynamic cloumn experiment was also carried out and operation condition was followed below：column size was φ5 mm×100 mm, and added 0.5 mL sorbent by wet method, the flow rate was 8.6 mL/h, the feed solution was simulated nuclear plant waste pH＝5.0, 90Sr 3.0×104 Bq/L, and about 4 L feed solution was treated through this column and the outflow liquid was measured by an α/β detector, and a DF more than 103 gained. During the experiment, the sorbent shows good hydraulic and mechanical performance. As a result, the preparation of the sorbent was simple and its selectivity for strontium was high with good hydraulic and mechanical performance, so it can be applied for treating or extracting 90Sr from varieties of radioactive liquid waste.

Destruction of Tributyl Phosphate and Exchange Resin by Electrochemical Oxidation

MA Hui, XING Hai-qing, ZHANG Zhen-tao, GAN Xue-ying, WANG Lei, BAI Yang (Department of Radiochemistry)

Spent tributyl phosphate and spent exchange resin are difficult to treat. It’s important to develop an

advanced treat method. Compared with traditional methods, electrochemical oxidation has obvious advantages, such as the operation can be done under mild conditions at 1ow temperature and atmospheric pressure. The equipment is compact and can be installed in the glove box; therefore, the level of radioactive operation can be raised. This method suits for handling higher level radioactive wastes.

A laboratory scale electrolytic cell was established. Lots of experiments were taken out to investigate how the parameters such as the concentration of nitric acid, silver nitrate concentration, the temperature, the current density, stirring rate, affect the degradation of TBP and resin. The best conditions for the destruction of TBP and cation resin were found. The destruction ratio of TBP and cation resin can achieve more than 99%. The parameters such as the concentration of nitric acid, the temperature, the current density, and stirring rate have a remarkable effect on the destruction of the organic. Higher concentration

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radioactive Waste Treatment and Disposal 163

of nitric acid, higher temperature, higher current density and higher stirring rate contribute to the destruction of the phosphate and exchange resin. The oxidation effect of Ag(Ⅱ) is better than Ce(Ⅳ).

Site Cleanup of Radioactive Isotope Container Rinsing Pool and Surrounding Environment

GAN Xue-ying1, ZHOU Chang-xin1, ZHANG Zhen-tao1, TU Xing-ming2,

QIAO Hai-tao2, CHENG You-jian2, LI Hang2 (1. Department of Radiochemistry; 2. Department of Radiation Safety)

Radioactive isotope container rinsing pool and surrounding environmental site was a place of

fabrication of container, and package, transportation and storage of radioactive isotopes. A heavy contamination existed in this area for burying of some radioactive wastes.

In order to remove the hidden peril of safety, the cleanup of the isotope container rinsing pool and surrounding environment was began on Aug. 23rd. 2010. the entire site remediation was divided into three phases: Site characteration investigation, digging pit survey, and site decontamination and cleanup. Through the effort on discussion, design and compile of each phase scheme, application for licenses, management of radiation supervision, organization of construction site, selection and storage of radioactive waste, and final checking and acceptance, the remediation task was finished on Apr. 22nd. 2011.


Isotopes

Biodistribution of 99Tcm Labelled Dextran Conjugates for Sentinel Lymph Node Detection

YANG Chun-hui, LI Hong-yu, LIANG Ji-xin, LU Jia, LUO Hong-yi, ZHENG De-qiang, SUN Gui-quan

(Department of Isotope)

Mannosylated dextran conjugates showed high receptor affinity to the receptors on the surface of macrophages in the lymph node. 99Tcm labelled mannosylated dextran conjugates could be used for sentinel lymph node (SLN) detection. In this paper, [99Tcm(CO)3(H2O)3]+ precursor was prepared using Isolink kit, then four kinds of dextran conjugates were labelled via [99Tcm(CO)3]+. The biodistribution studies of these labelled conjugates were carried out in Balb/C mice to study the effects of the differences in structures of these dextran conjugates (with and without mannose). The results were listed in Table 1.

Table 1 Biodistribution of [99Tcm(CO)3]+ labelled dextran conjugates in Balb/C mice

( x ±s)/%ID (n＝5)

Tissues 99Tcm-(CO)3-DC-15

(without mannose)

99Tcm-(CO)3-DCM-20

(with mannose)

99Tcm-(CO)3-DC-25

(without mannose)

99Tcm-(CO)3-DCM-30

(with mannose)

SLN 1h p.i. 0.24±0.02 3.18±0.18 0.73±0.25 5.44±1.04

SLN 4h p.i. 0.13±0.01 3.47±1.02 0.26±0.08 5.72±0.46

2LN 1h p.i. 0.07±0.01 2.16±0.41 0.14±0.05 3.48±1.54

2LN 4h p.i. 0.08±0.01 2.07±0.47 0.06±0.02 3.51±0.89

3.13±0.92 30.68±8.33 28.14±3.87 51.05±6.96 I.S. 1h p.i.

I.S. 4h p.i. 1.77±0.21 36.09±3.09 10.86±1.75 43.69±2.79

Liver 1h p.i. 13.41±0.63 23.34±3.50 2.26±0.19 11.88±2.73

Liver 4h p.i. 2.94±0.36 21.60±3.29 1.48±0.27 10.71±1.76

Spleen 1h p.i. 0.90±0.05 13.82±3.62 0.66±0.14 8.59±4.23

Spleen 4h p.i. 0.91±0.21 15.41±3.48 0.34±0.06 5.78±1.37

Blood 1h p.i 1.29±0.12 2.93±0.44 4.31±0.38 0.53±0.07

Blood 4h p.i. 0.68±0.11 1.27±0.07 1.94±0.06 0.31±0.03

Notes: p.i.: postinjection; SLN: sentinel node, popliteal node in mouse; 2LN: secondary node, lumbar node in mouse; I.S.: Injection site,

the injected foot pad

The results of biodistribution demonstrates that the labelled dextran conjugates (without mannose in

the molecules) show rather low SLN uptakes and in vivo excretion of these conjugates are comparatively faster, and the uptakes of injection site are also relatively low; on the other hand, the labelled dextran conjugates (with mannose in their molecules) show much higher uptakes in SLN than their corresponding dextran conjugates without mannose, but the retention in the injection site of these conjugates increase too. The result indicates the affinity of mannosyl-dextran conjugates the lymph node. The 99Tcm labelled

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Isotopes 165

mannosylated dextran conjugates show promising properties as SLN imaging agent and worth further investigation.

* Supported by CRP of International Atomic Energy Agency (CRP-14513/R0)

Preparation, Radiolabelling and Biodistribution Study of 177Lu-DTPA-G3

DENG Xin-rong, LIU Zi-hua, FAN Cai-yun, LI Feng-lin (Department of Isotope)

Polyamidoamine (PAMAM) dendrimers are new artificial macromolecules with tree-like structure

and have characteristics of greater water-solubility, bioavailability and compatibility. It can be carried by the drug molecules. PAMAM have been proved as promising nanocarriers for drug delivery.

This report described that three generation PAMAM (G3) was conjugated with diethylene triamine pentacetate acid (DTPA) to produce G3-DTPA and the concentration of DTPA was determined. The molar ratio of G3 to DTPA in G3-DTPA molecule prepared was 1﹕35. The dendrimer based agent was purified by PD-10 column. G3-DTPA was radiolabelled with 177Lu using direct labelling method. And then biodistribution of 177Lu-DTPA-G3 in normal mice was performed as well.

The purity of G3-DTPA was over 95.0% after purification. Each PAMAM molecule could be conjugated with 26 DTPA molecules. The radiochemical yield of 177Lu-DTPA-G3 after purification was higher than 98.0%. The biodistribution of Kunming mice showed that 177Lu-DTPA-G3 without tissue specificity could quickly eliminate from the circulation fast through urinary system.

177Lu-DTPA-G3 could be prepared with high radiochemical purity and radiochemical yield. 177Lu-DTPA-G3 is worthy being further studied.

Preparation and Biodistribution Evaluation in Mice of 177Lu-DOTA-TOC

DENG Xin-rong, LUO Zhi-fu, FAN Cai-yun, LIU Zi-hua, LI Feng-lin, XIANG Xue-qin (Department of Isotope)

The study of 177Lu labeled radiopharmaceuticals for cancer therapy is fast emerging as an important

part of nuclear medicine. 177Lu-labelling of DOTA derivatized peptide DOTA-TOC (Tyr3-Octreotide) was carried out and biodistribution of 177Lu-DOTA-TOC in normal mice and nude mice bearing PANC-1tumor were evaluated as well.

Optimal condition of labeling was chosen from different pH and reaction time. In the biodistribution study, the mice were injected in the tail vein with 177Lu-DOTA-TOC and sacrified in different time intervals. Labelling experiment was done under the condition (DOTA-TOC 25 μg, pH＝4.5 react at 90

for 30 min), the radiochemical activity of 177Lu-DOTA-TOC was over 98.0% after C18 Sep-Pak purification. The biodistribution of 177Lu-DOTA-TOC in normal mice showed rapid blood clearance. The uptake of 177Lu-DOTA-TOC was mainly accumulated in liver, spleen and kidney, and excreted by kidney.


177Lu-DOTA-TOC showed higher uptake in pancreatic tumor than normal tissues. 177Lu-DOTA-TOC could locate in the tumor and show good target.

The results provide the basis for further study on 177Lu-DOTA-TOC used in radioimage and radiotherapy of somatostatin receptor positive tumors.

Determining Contents of Five Impurities in Cyclotron- Produced 64Cu Solution by Emission Spectroscopy

JIANG Hua, YE Zhao-yun, ZHAO Xiu-yan, CHEN Yu-qing


64Cu (β+＝17%, β－＝39%, IEC＝43%) is an important emerging biomedical radionuclide, which is

useful for PET as well as a promising radiotherapy agent for the treatment of cancer. It can be produced on a small biomedical cyclotron utilizing 64Ni(p, n)64Cu nuclear reaction. An emission spectroscopic analysis method has been proposed for impurity elements analysis in cyclotron-produced 64Cu solution. This paper has selected the effective carrier and the suitable internal reference element.

Optimum working condition is determined and the matrix effect is checked. The limit of the detect sensitivity for various impurities are about 0.1-1 μg/mL, and the standard deviation of the method is within 16.6%.

Determination of Medronic Acid and Its Related Substances by Reversed-Phase High-Performance Liquid Chromatography

ZHAO Xiu-yan, FU Bo, YE Zhao-yun, LIU Yin-li, JIANG Hua


An isocratic liquid chromatographic method with evaporative light scattering detection (ELSD) was developed for the determination of medronic acid and its related substance. Volatile pentylamine was used as ion-pairing agent. Separations were performend on an symmetry C8 column with an mobile phase of 98﹕2 (V﹕V) 30 mmol/L pentylamine (pH＝5.0, adjusted by acetic acid)-methanol. The mobile phase delivered at a floe-rate 1.0 mL/min. The method is applied for the quality control of Medtronic acid.

Quantification of Kryptofix2.2.2 in18FDG by HPLC

ZHAO Yan, YE Zhao-yun, ZHAO Xiu-yan, JIANG Hua (Department of Isotope)

2-deoxy-2-[18F] fluoro-D-glucose (18FDG) is the most commonly used radiopharmaceutical for positron emission tomography (PET). Kryptofix2.2.2 (K-222) is used as a phase-transfer catalyst in the


synthesis of 18FDG. Because of its toxicity, the quality control analysis of K-222 is essential in the final preparation. A number of analytical methods such as thin-layer chromatograph, high-performance liquid chromatograph, liquid chromatograph/MS, gas chromatograph and ultraviolet spectrophotometry have been developed to determine K-222. In China, the standard of 18FDG injection production was according to the tentative standard promulgated by Chinese food and Drug Administration. The UV-spectrophotometry method of K-222 was developed by ZHAO Guizhi, K-222 forms stable complex with lead(Ⅱ) in the citric acid-NaOH media of pH＝6.4, having the peck absorbance at 253 nm. There were defection of using more sample and interference.

A high-performance liquid chromatograph method was used to quantify K-222 in the radiopharmaceutical of 18FDG. A Waters C18 column (XTerra RP18 150 mm×3.9 mm, 5 μm) was used as stationary phase, a mixture of V(50 mmol/L ammonium acetate)﹕V(acetonitrile)＝1﹕1 was used as mobile phase and the flow is 0.5 mL/min, UV detection wavelength was performed at 210 nm. The calibration curve was established over the range of 0.01-0.05 g/L, the linear correlation coefficient was 0.999, and the recovery was in the range of 95%-100%. The method was accurate and using less sample, and can be used for the quality control of K-222 in 18FDG injection production.

Development of Up-Converting Phosphor Immunochromatography Test for Quantitative Detection of Enrofloxacin

LI Li-bo, YAO Yan, LIU Zhong-rui, HOU Hui-ren, GUO Yong-gang


An up-converting phosphor (UCP) immunochromatography test was developed for the detection of enrofloxacin (ENR). The anti-ENR monoclonal was conjugated to the up-converting phosphor particles while the ENR-BSA immobilized on the nitrocellulose membrane. We evaluated the sensitivity, precision and recovery of this method. The analysis time was 15 minutes and the sensitivity was 0.5 ng/mL. The intra-assay CV (coefficient of variation) of the method was less than 15% and the inter-assay CV less than 20%. The recovery rate was from 53.6% to 140.6% in pork, chicken and shrimp. When the standard quantitative curve was determined, a good linearity was displayed in the range from 0.5 to 50 ng/mL. The method was simple, cheap and quantitative, especially for the quick test on spot.

Development of Up-Converting Phosphor Immunochromatography Test for Quantitative Detection of Sulfadiazin

LI Li-bo, YAO Yan, LIU Zhong-rui, HOU Hui-ren, GUO Yong-gang


An up-converting phosphor (UCP) immunochromatography test was developed for the detection of sulfadiazine (SD). The anti-SD monoclonal was conjugated to the up-converting phosphor particles while


the SD-BSA immobilized on the nitrocellulose membrane. We evaluated the sensitivity, precision and recovery of this method. The analysis time was 15 minutes and the sensitivity was 0.1 ng/mL. The intra-assay CV (coefficient of variation) of the method was less than 15% and the inter-assay CV less than 20%. The recovery rate was from 62.4% to 133.4% in pork, chicken, milk and shrimp. When the standard quantitative curve was determined, a good linearity was displayed in the range from 0.1 to 30 ng/mL. The method was simple, cheap and quantitative, especially for the quick test on spot.

Specific Activity and Impurities in Irradiated Natural Nickel Target

MA Jun-ping, ZHANG Li-feng, CHEN Hai-yang (Department of Isotope)

In this paper, the specific activity of the 63Ni which is produced by irradiating natural nickel in a

nuclear reactor is calculated. And in the 1 g irradiated natural nickel target, the species of the key impurity nuclides were analyzed, and the activity of some nuclides is calculated. This job is a foundation about 63Ni production by irradiating high-rich 62Ni. The results are shown in Fig. 1 and Table 1.

As the Fig. 1, the specific activity of 63Ni increase linearly during the targets being irradiated in a lower flux rate thermal neutron reactor, and just ~50 mCi/g is achieved for three years. However, the same targets are irradiated in a high flux thermal neutron reactor, the specific activity of 63Ni increase rapidly and achieve the maximum (~600 mCi/g) in short time. But these 63Ni being produced by natural nickel or low flux rate thermal neutron reactor, is useless in many fields, because the specific activity of these 63Ni is too low. So, the high-rich 62Ni targets are irradiated in a high flux thermal neutron reactor to achieve the 10 Ci/g.

A few of other nuclides present in a natural nickel target, and are activated during irradiation. The results of analyzing and calculating about the key impurities nuclides after the 1g natural nickel being irradiated in a 2×1013n·cm－2·s－1 reactor are shown in Table 1. As the Table 1, the 60Co has a longer half-life and high activity. So the 59Co must be very low or not present in the nickel target.

Fig. 1 The relation between specific activity of 63Ni and irradiation time


Table 1 The content and activity of key impurities

The content of key impurities/g Impurity Half-life Decay & radiation

10 d 20 d 30 d 40 d 50 d

60Co 5.27 a β－, with γ 6.507 31×10－7 1.299 06×10－6 1.944 61×10－6 2.587 41×10－6 3.227 47×10－6 65Zn 244.06 d β+, ε，with X, γ 1.847 21×10－10 3.634 92×10－10 5.365 07×10－10 7.039 49×10－10 8.659 9×10－10 55Fe 2.73 a ε, with X, γ 6.919 64×10－10 1.379 10×10－9 2.061 46×10－9 2.739 05×10－9 3.411 93×10－9 59Fe 44.495 d β－, with X, γ 1.790 47×10－11 3.323 27×10－11 4.635 54×10－11 5.759 1×10－11 6.721 16×10－11

32Si 172 a β－, with N 5.991 97×10－12 1.207 93×10－11 1.816 58×10－11 2.425 18×10－11 3.033 71×10－11

The activity of key impurities/mCi Impurity Half-life Decay & radiation

10 d 20 d 30 d 40 d 50 d

60Co 5.27 a β－, with γ 0.735 663 1.468 610 2.198 41 2.925 11 3.648 71 65Zn 244.06 d β+, ε，with X, γ 1.519 57×10－3 2.990 20×10－3 4.413 46×10－3 5.790 90×10－3 7.123 96×10－3 55Fe 2.73 a ε, with X, γ 1.647 71×10－3 3.283 92×10－3 4.908 75×10－3 6.522 24×10－3 8.124 49×10－3 59Fe 44.495 d β－, with X, γ 8.900 59×10－4 1.652 02×10－3 2.304 36×10－3 2.862 89×10－3 3.341 14×10－3 32Si 172 a β－, with N 3.892 36×10－7 7.846 63×10－7 1.180 05×10－6 1.575 39×10－6 1.970 68×10－6

Determination of Two Columns’ Performance

LIU Zi-hua, DENG Xin-rong, FAN Cai-yun, LI Feng-lin (Department of Isotope)

When protein is analyzed by high performance liquid chromatography (HPLC), the selection of

column is one of the most important factors. There are four quality control parameters for the column, which are theoretical plates n, capacity facto k′, relative retention (selectivity factor) α and resolution Rs.

Gel-filtration chromatograph and reversed-phrase chromatograph are two kind of HPLC which different theories. Theoretical plates, the most important column performance is tested to evaluated the ability of protein separation and analysis. 1 Experimental materials and instruments

Agilent 1200 HPLC (with DAD) instruction, Agilent Zorbax GF450 column (6 μm, 9.4 mm×250 mm), Agilent Zorbax GF250 column (4 μm, 4.6 mm×250 mm), Agilent Zorbax 300SB-C18 column (5 μm, 4.6 mm×150 mm), sodium azide, uracil, acetophnone, naphthalene, toluene, acetonitrile and phosphate buffer (PB, 0.15 mol/L, pH＝7.0). 2 Experiment method

2.1 The theoretical plates of GF450 column and GF250 column were determined by Gel-filtration HPLC with sodium azide dissolved in phosphate buffer as the standard, the theoretical plates was calculated according the formula:

n＝5.54(tr/W1/2)2 n＝ theoretical plates, tr＝retained time, W1/2＝the half width of the Chromatography peak in the fomula.

The theoretical plates determined can tell us if the column performance qualified or not when being compared to the theoretical plates in the manual provided by the manufacture.


2.2 Determination the theoretical plate of 300SB-C18 column by reverse phrase -HPLC, with sodium azide dissolved in phosphate buffer as the standard. The theoretical plates acquitted was compared to the theoretical plates in the manual provided by the manufacture, then we could be evaluated the column performance qualified or not, and then to make sure the laboratory conditions is adequate for protein analysis. 3 Results and discussion 3.1 Performance of Agilent Zorbax GF450 and GF250 test

Chromatographic conditions were as follows. Mobile phase was phosphate buffer (0.2 mol/L, pH＝

7.0); detection wavelength was 254 nm; the sample was NaN3 (2 500 μg/mL in mobile phase); temperature was room temperature.

1) Performance of Agilent Zorbax GF450 test The injection volume was 10 μL, column flow was 2 mL/min, the test chromatography was show in

Fig. 1.

Fig. 1 The test chromatography of performance of Agilent Zorbax GF450

The theoretical plates 15303 was obtained from the test. But the theoretical plates of veraficated

manual was 29 414, obviously there was a big difference between them. So the column was sent to a Specified department to re-determined, and the result was n＝15 207, so the experimental data was accuracy and reliability, because the data was still above of 15 000 which was the Bottom line, then this Agilent Zorbax GF450 column was qualified to protein analysis.

(2) Performance of Agilent Zorbax GF250 test The injection volume was 5 μL, column flow was 0.5 mL/min, the test chromatography was show in

Fig. 2.

Fig. 2 The test chromatography of performance of Agilent Zorbax GF250


The theoretical plates 3956 was obtained from the test. But the theoretical plates in its’ own manual was 29 414, obviously the data cannot reach the required value, it even less than 15 000 which was the Bottom line. So this Agilent Zorbax GF250 column can not to be used of protein analysis.

Size-exclusion chromatography separates protein compounds on the basis of effective size of the sample molecule. The GF450 and GF250 are complimentary, the total separation ranges for the columns is 900 000-10 000 Daltons, but now only GF450 is qualified, so protein having molecular weight from 900 000 to 25 000 Daltons can be analyzed. 3.2 Performance of Agilent Zorbax 300SB-C18 test

Chromatographic conditions were as follows. Mobile phase was 60%acetonitile/40%water; detection wavelength was 254 nm; the sample was uracil (5 μg/mL), acetophnone (0.6 μg/mL), toluene (3.8 μg/mL) and naphthalene (40 μg/mL) in mobile phase; temperature was room temperature; the injection volume was 5 μL; column flow was 1.0 mL/min. The test chromatography was showed in Fig. 3.

Fig. 3 The test chromatography of performance of Agilent Zorbax 300SB-C18

The theoretical plates 2843 was obtained from the test, according chromatography peak of

naphthalene. But the theoretical plates in the manual provided by the manufacture was 13 186, the bottom line was 9 000. Then this Agilent Zorbax 300SB-C18G column was invaluable.

Using compounds have different adsorption to the stable phrase to separate and analyze compounds is one of the most common method. Agilent Zorbax 300SB-C18 particles have a controlled pore size of 300 Å，is well suited for proteins, because this column has so poor theoretical plates, that it cannot be used for proteins analysis until regenerates or be replaced by a new one.

Anyway, proteins having molecular weight from 900 000 to 25 000 Daltons can be analyzed by gel-filtration high performance liquid chromatography in our laboratory now.


Applied Mathematics and Computer Technology

Synchronizability Analysis of Harmonious Unification Hybrid Preferential Model*

LIU Qiang, FANG Jin-qing, LI Yong

(Department of Nuclear Technology Application) The harmonious unification hybrid preferential model uses the dr ratio to adjust the proportion of

deterministic preferential attachment and random preferential attachment, enriched the only deterministic preferential network model, and the appropriate dr ratio can be obtained the small world property and scale-free property. We calculated the relationship between the dr ratio of HUHPM network and synchronizability, as shown in Fig. 1, network scale N=1 000, m=4.

Fig. 1 HUHPM synchronizability versus dr

Fig. 1 shows the relation between the HUHPM sychronizability and the dr ratio, we can see that λN/λ2

increase, and |λ2| decrease with the increase of the dr ratio, the trend of two synchronization criteria with dr shows that HUHPM network synchronizability abate with dr ratio increases. When dr≥10, λN/λ2 and |λ2| tend to be stable, it shows that when dr>10, network synchronizability is approximately the same. The dr ratio increases means time intervals of deterministic preferential attachment increase, or time intervals of random preferential attachment reduce, these results indicate that deterministic preferential attachment can enhance network synchronizability, and random preferential attachment weaken network synchronizability, but when dr>10, the synchronizability of HUHPM model remain stable.

* Supported by National Natural Science Foundation of China (60874087，61174151)

Algebraic Condition of Nonlinear Dynamical Network Synchronization*

LIU Qiang, FANG Jin-qing, LI Yong (Department of Nuclear Technology Application)

Consider N linearly and symmetrically coupled identical dynamical systems, every node expresses a

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Applied Mathematics and Computer Technology 173

dimensional dynamics system.

( )1

( )N

i i ij jj

x f x c a H x=

= + ∑ i=1, 2,…, N （1）

Where xi＝（xi1，xi1，…，xin）∈Rn is the state vector of the i-th node; c is the coupling strength; M=(Mij)N×N is the N×N coupled matrix. If there is a connection between mode i and mode j, then Mij＝Mji

＝1(i≠j), otherwise Mij＝Mji＝1(i≠j), and ij jijM M= −∑ . H(xj) makes the output function. The method

of the master stability function is presented to be used as a measure for the stability of the synchronous state. Through calculating matrix Mij characteristic root may be obtained,

0＝λ1＞λ2≥≥…≥λN （2） And it has been found that there exists an interval (α1, α2) on which the output function, which is the

largest Lyapunov exponent, is less than zero and the synchronized state is stable, and the algebraic condition for the existence of a linearly stable synchronous state is given.

R＝λN/λ2＜α1/α2＝β （3） The other algebraic condition for the existence of a linearly stable synchronous state is

c≥| d /λ2| （4）

where c is the coupling strength; d is a constant. It is seen that the synchronizability of the coupled network is enhanced as the ratio R is reduced, and the coupling strength c is reduced as well as the synchronizability of the coupled network is enhanced as |λ2| is increased.


Unified Hybrid Network Theoretical Model Trilogy*

LIU Qiang, FANG Jin-qing, LI Yong (Department of Nuclear Technology Application)

The first of the unified hybrid network theoretical model trilogy (UHNTF) is the harmonious

unification hybrid preferential model (HUHPM), seen in the inner loop of Fig. 1, the unified hybrid ratio is defined.

dr＝time intervals of deterministic preferential attachment (DPA)/time intervals of random preferential attachment (RPA) (1)

The second model in the UHNTF is the large unifying hybrid network model (LUHNM) as shown in the middle loop of Fig. 1. One ratio fd is socalled the deterministic hybrid ratio, which is defined by:

fd＝HPA/DA (2) Where HPA is helpful for the poor (lower degree) attachment; DA is deterministic attachment, and the another ratio gr is so-called random hybrid ratio, defined by:

gr＝GRA/RA (3) Where GRA is general random attachment; and RA is total random attachment. We have total deterministic attachment DA＝HPA+DPA and total random attachment RA＝GRA+RPA. The LUHNM


can simulate realistic networks, both random and deterministic. The third model in the UHNTF is the large unifying hybrid variable growing model (LUHVGM) as

shown in the outermost loop of Fig. 1, which depends on four hybrid ratios (dr, fd, gr, vg), where vg is a new hybrid variable growth ratio defined by:

vg＝DVG/RVG （4） Where DVG is time intervals of deterministic variable speed growth; and RVG denotes time intervals of random variable speed growth. LUHVGM can better describe a real network types.

Fig. 1 Diagrams unified hybrid network theory framework (UHNTF)


Influence of Deterministic Attachments for Large Unifying Hybrid Network Model*



Large unifying hybrid network model (LUHPM) introduced the deterministic mixing ratio fd on the basis of the harmonious unification hybrid preferential model, to describe the influence of deterministic attachment to the network topology characteristics, it can many more comprehensive simulation to the actual network. We calculated the relationship between the deterministic mixing ratio fd of LUHPM network and network synchronizability, as shown in Fig. 1 (N=1 000, m=4).

In the figure, the solid line is the curve of λN/λ2 with the gr, the dashed curve is the curve of |λ2| with the gr. These results show that deterministic referential attachment increase can make the synchronization ability maintain stability.

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Applied Mathematics and Computer Technology 175

Fig. 1 LUHNM synchronizability versus fd

a——gr=0; b——gr=0.5; c——gr=1


Influence of Random Attachments for Large Unifying Hybrid Network Model*



The large unifying hybrid network model (LUHNM) is the second model in the UHNTF, we

calculated the relationship between the synchronizability of LUHNM and the gr ratio, the results are shown in Fig. 1 (N=1 000, m=4).

In the figure, the solid line is the curve ofλN/λ2 with the gr, the dashed curve is the curve of |λ2| with the gr. If gr increase, network synchronizability weakens, so random referential attachment increase can make the synchronization ability maintain stability.

Fig. 1 LUHNM synchronizability versus dr

a——fd =0; b——fd =0.5; c——fd=1



Nuclear Safeguards Techniques

Uranium Enrichment Analysis With Electromechanical Cooled HPGe Detector

LIU Hong-bin, LU Wen-guang, WANG Mian, XU Zhen


The Micro_trans_SPEC-100 portable high-resolution gamma-ray radioisotope identifier was used for

the uranium enrichment analysis demonstration. Micro_trans_SPEC utilize stirling-cycle cooler and integrated detector, signal electronics and analysis process as a compact unit. The instrument is liquid nitrogen-free and suitable for field operation. Through the optimizing of the condition and parameter of measurement, two method using relative efficiency intrinsic self-calibration and standard calibration for the uranium enrichment analysis were tested.

The PC/Fram analysis software was adopted for the relative efficiency intrinsic self-calibration analysis. The coaxial HPGe detector parameters set was used for the gamma spectrum acquiring, the energy resolution was set up as 0.125 keV/ch. Through the parameters optimization, the relative error for the NBL-SRM 969 standards is less than 3%, for the container wall shields simulation with steel from 5 mm to 19 mm less than 6.2%, for the 30B and 48X type UF6 cylinders less than 20%.

Standards calibration uranium enrichment analysis method adopts the infinite-sample gamma measurement technique. When the measurement condition meets the infinite-thickness criterion, the uranium enrichment is proportional to the net 185.7 keV count rate of the 235U.The system was developed by the windows mobile system and built in the instrument. The system consists of the calibration standard parameters setup, calibration coefficient calculation and sample analysis. The method also considers the container wall attenuation correction and can be used when there is a container wall difference between the standard and samples. As to the 30B and 48X type UF6 cylinders, the relative error is less than 10%.

Development of Uranium Works Reference Sample for NDA Measurement

HE Li-xia, LIU Hong-bin, BAI Lei, XU Zheng (Department of Radiochemistry)

The works reference sample usually used in NDA instruments calibration, methods research and

samples quantitative analysis. It is also can be applied in quality control as instruments performance checking and maintenance. In this work, we develop a set of low enrichment uranium work reference sample for 235U enrichment verify and uranium quantitative reference material for 235U quality measurement. In result there are 23 samples containing U3O8 powder or U3O8 with diatomite admixture, and 3 containers without material.

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Safeguards Techniques 177

Eigenvalue in Uranium works reference sample has reasonable scale and grads. Both U3O8 mass and 235U enrichment relatively deviation are less than 0.1%. There is 200 g U3O8 filled in each uranium enrichment reference sample. For uranium mass work reference samples, they contain different mass U3O8 which is mixed with diatomite and sample density is approximate to 1 g/cm3.

After samples assembled they were verified by γ ray spectral analysis in preparation site. In result, the 235U enrichment and material homogeneity in uranium enrichment work reference samples achieved designed data. In uranium mass work reference samples, material is approximately homogeneity mixed with diatomite and the mass values are in accord with intending. In conclusion, the uranium works reference sample researched is adequate for NDA techniques application.

γ Ray Radioactivity Measurement of 88Y and 22Na Point Source

HE Li-xia, GAN Lin (Department of Radiochemistry)

Both 22Na and 88Y have adequate half life, they are broadly used in radioactive measuring field. They

are also very important in different techniques application and usually used in γ ray detectors like as high purity germanium efficiency calibration. Activity is a vital parameter for radioactive sources. So it is foremost choosing accurate method to determine the radioactivity.

In this work source-peak efficiency calibration method and relatively ratio activity measuring method are used for 88Y and 22Na point source radioactivity measurement. The deviation between two methods less than 1% and activity uncertainty is 0.7%. Considering standards uncertainty the two kind of methods are efficiency for nuclide radioactivity measuring and they can be validated by each other.

As a result, the respective deviation between measured and coefficient comparison radioactivity is －0.3% and －0.2%. In conclusion, specific radioactivity obtained in laboratory is according to true value. As radioactivity evaluation method they are correct and can provide traceable data. Exactly they can be used as γ ray point sources radioactivity determining.

Study on Application of Mobile Radiological Monitor

LI Xin-jun, XU Xiao-ming, BU Li-xin, LU Wen-guang (Department of Radiochemistry)

The mobile radiological monitor has been applied for the radiation level of a nuclear facility in 2011.

Based on the requirement, the monitor had been improved, it can measure and save the data of gamma-ray and neutron radiation level, the dose rate and the synchronous geography position information can also be saved at the same time. The monitor can communicate with the remote central alarm station through Internet. the remote central alarm station can monitor the data and the position information. 3D technology was to show the measured data and the radiation level of the measured position.


Emission Data-Analysis of TGS Under Continual Scanning Mode

ZHOU Zhi-bo, SUI Hong-zhi (Department of Radiochemistry)

In the emission data-analysis of TGS under the continual scanning mode, we divide the efficiency

matrix into two parts, one part has nothing to do with the measured sample, that is the intrinsic efficiency of the detector and the geometry efficiency of the system; and the other part is the self-absorption correction which is relative to the matrix. For the first part, it can be calculated by the Monte-Carlo simulation in advance; after that, calculations of the self-absorption correction factors are carried out. In order to calculate this factor, we divided the voxel into 125 small cubes, and the HPGe detector was equivalent to 49 point-detectors array. Then we multiply all of these factors together, and treat the average result as the detective efficiency of the detector to each voxel during each period of data obtaining. At last, experiments were carried out to verify the data-analysis method, the relative deviations between the calculating value and the declared value were less than 6% for 137Cs.

Transmission Data-Analysis of TGS Under Continual Scanning Mode

ZHOU Zhi-bo, SUI Hong-zhi (Department of Radiochemistry)

We choose the SART arithmetic to solve the problem of reconstruction of transmission image.

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kMk k i i

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j i ji

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i j ji

p p

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=+ +

+=

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∑

∑∑

There are three important factors to confirm in the equations: 1) Relaxing factor λ, which determines the constringency speed of the algorithm and the precision of the image reconstructed. In order to define the optimum λ, the numerical simulation experiments have been carried out on the measured samples; 2) weighing factor ωi，k, which determines the distribute proportion of the corrective values for each voxels in every repeat procedures. In this paper, the equivalent method has been adopted. Based on the intense distribution of the transmission bundle that traveled through the collimator, the efficiency distribution of


each point on the detector surface, and the path of each ray passed through the voxels, we equivalent the collimated transmission bundle to 5 rays on the panel, and then give these 5 rays different weight. By dividing the time for each spectrum obtaining into 10 moments with constant interval, calculating the string lengths of these 5 rays cut by each voxel at each moment, and multiplying these string lengths by

the weighing factors of each ray, the weighing factor ωi, k of SART can be obtained; 3) factor ~

ip . By the similar calculation used for weighing factor ωi, k, after equivalent the collimated transmission bundle to 5

rays on the panel, and use the μk before each repeat to calculate the transmission rate ~

ip of this transmission measurement.

After each factors of SART have been defined, verifications for the stability and accuracy of this arithmetic have been conducted. For the verification of stability, a kind of numerical simulation has been adopted. After the transmission rate of the transmission bundle of each measurement has been calculated, we added the random errors (less than 10%) into the calculated transmission rate, and then put these transmission rates with errors into the iterative formulas of SART, the maximum deviations of the rebuilt μ are all less than 15%. For the verification of accuracy, Monte-Carlo simulation and experimental validation have been performed. The maximum deviations of the rebuilt results are all less than 11%.

Nuclear Material Accountancy Assessment Technical Measures in Nuclear Centrifuge Enrichment Facility

GAO Xue-mei


Nuclear material accountancy assessment is the main technical measures for nuclear materials regulatory. It is an important basis to detect theft, loss and the illegal diversion of nuclear material. In order to implement the control of nuclear materials for nuclear facilities, national authority has required every nuclear facilities to build a nuclear material accountancy system of nuclear materials, and to account for all the nuclear materials held by operators. The facilities must evaluate the difference between the book inventory and physical inventory that is material unaccounting for (MUF) in facilities. The MUF assessment is basis of adjustment of accounts, if the MUF assessment results show that the true MUF value is not zero, then there may be the possibility of diversion of nuclear material through the MUF. The facilities can not simply adjust the accounts, they should find the real reason. The material facilities should adjust ending inventory on the basis of the statistical evaluation of MUF, that is to make the physical inventory as the beginning inventory of a new material balanced period. Nuclear material accountancy assessment is an important basis to meet the requirements of the national nuclear material control.

This working group completes the evaluation for the uranium centrifuge enrichment facilities. Nuclear material accountancy is based on three measurement operations: 1) Determination of the net

weight or volume of an item (bulk measurement); 2) sampling of the material; 3) analysis of the sampled material for element and/or isotope concentration. According to the process characteristics of both of Shaanxi uranium centrifuge enrichment plant and Lanzhou uranium centrifuge enrichment plant, we do the evaluation step by step: Dividing operations involving nuclear material into material balance areas


(MBAs); Maintaining records on the quantities of nuclear material held within each MBA; measuring and recording all transfers of nuclear material from one MBA to another or changes in the amount of nuclear material within MBAs due to; determining periodically the quantities of nuclear material present within each MBA through the taking of the physical inventory; Closing the material balance over the period between two successive physical inventory takings and computing the material unaccounted for (MUF) for that period; providing for a measurement control programme to determine the accuracy of calibrations and measurements and the correctness of recorded source data and batch data; testing the computed MUF against its limits of error for indications of any unrecorded nuclear loss or accidental gain; analysing the accounting information.

We help the facilities to do the measurements on site, collect data to calculate the total errors of UF6 material, using the assessment model. The measurement data show that the overall measurement, system error and random error related to analysis of the measurement can basically meet the requirements of the international target.

Study on Calibration of Device of Heterogeneous Matrix With Uranium inside

BAI Lei, WANG Zhong-qi, SHAO Jie-wen, CHENG Yi-mei, HE Li-xia (Department of Radiochemistry)

The device of measuring heterogeneous matrix with uranium inside is built base on ray segment scan technology and neutron analysis technology, to use to measure the heterogeneous matrix with Uranium inside which produced by chemical transformation facility in fuel element plant.

Device is composed of five parts by a transmission source platform, detector platform, center of rotation platform, front guide rail platform and neutron measuring ring. It can realize the pipeline into the sample, sample rotation measurement, sample matrix density distribution analysis, sample of uranium isotopes and quantity analysis and the use of neutron measurement of high density uranium containing material and other functions.

The Device using MC (Monte Carlo) passive method for calibration, it determined detector crystal internal cold hole radius, cold hole depth, the thickness of the casing, the outer dead - layer thickness and other parameters by experiment, determined collimator size, the value of experimental platform size, sample barrel size, the relative position relationship between components and material parameters, thus completing the device calibration. When measuring it built Matrix distribution according to transmission measurement results, then generates the sample description parameter of MC code, using the MC code to calculate the current layer and the adjacent layer efficiency distribution. Then get the total amount of uranium. After calibration, through the experimental platform placed high enriched uranium to make verified experiment, using the segment scanning to measurement and analysis, then results compare with the reference values, measurement error meet the project requirements. The results are list in Table 1.


Table 1 Verified Experiment Result

Sample name Reference vale/g Measurement value/g Measurement error/％

Sample 1 8.93 8.53 4.64

Sample 2 4.51 4.39 2.75

Sample 3 1.80 2.16 1.03

Software Development of Measurement System Heterogeneous Uranous Drums

SHAO Jie-wen, BAI Lei, CHENG Yi-mei, HE Li-xia


Segmented Gamma Scanner (SGS) is a kind of important assay methodology of non-destructive assay (NDA). With the characteristic gamma ray, the mass or activity and nuclear species of measured material can be determined by the method. The software has the function of parameter setup, auto control, data transfer and date analysis. In order to make sure the function of the software can meet actual request, different experiments have been taken to prove the analytical result are correct, and all function of the software test indicate that the system runs well, the function is complete, the software is easy to operate, and has friendly interface, meet the measurement request for measurement system heterogeneous uranous drums.

Fig. 1 The software interface of measurement system heterogeneous uranous drums

Study on Automatic Control of Measurement System Heterogeneous Uranous Drums

SHAO Jie-wen, BAI Lei, CHENG Yi-mei, HE Li-xia


Segmented gamma scanner (SGS) is a kind of important assay methodology of non-destructive assay (NDA). With the characteristic gamma ray, the mass or activity and nuclear species of measured material


can be determined by the method. Nowadays, SGS has been widely applied in measurement of nuclear material because of need of nuclear materials accounting.

In order to improve the precision of measurement, there are several required factors—exact position of detected sample, automatic control of transmission source gate, position of platform of detector and one of transmission source, rotation of sample platform and automatic control from data acquisition to analysis. A computer control system is designed with complete function and high grade of automatic control, to assure atomization for SGS.

In this essay, the need of SGS is analyzed with full consideration and the research of practicability is conducted. The whole system plan is identified and relevant software for operational system is compiled. The main function of software system is realized, such as control of waste drum delivery, automatic rotation of sample platform, rise-and-fall of detector and transmission source platforms, automatic data acquisition and analysis, etc.

Physical Protection System Effectiveness Evaluation Project

ZONG Bo (Department of Radiochemistry)

Whether the performance meets regulation requirements is a key point to physical protection system

(PPS) of nuclear material and nuclear facility. To develop PPS effectiveness evaluation methodology and to use risk analysis based on Design Basis Threat, those are practical significance for improving and enhancing protection measures of PPS, and for increasing PPS effectiveness while reducing cost,.

Therefore, according to the requirements of National Nuclear Safety Administration, Nuclear Safeguards Laboratory of China Institute of Atomic Energy cooperated with Qinshan Nuclear Power Plant Third Phase, in doing trial assessment for PPS effectiveness of nuclear power plant, for early research on effectiveness evaluation methodology. The project started at March, 2011. Analyzer team collected data through visiting on site three times, then discussed with personnel in the plant for building assessment model and confirming preferences. Finally, after model assessing, analyzer team found advantage and disadvantage in PPS, and got effectiveness of physical protection system, therewith analyzer team gave appropriate upgrade advice based on actual condition. The project has finished at December, 2011.

Application Research of Developed Drummed Nuclear Waste Neutron Counting System

ZHU Li-qun, XU Xiao-ming, GU Shao-gang, LI Xin-jun

(Department of Radiochemistry) The application researches such as variety of factors affecting the measurement, calibrating etc. are

need before the drummed nuclear waste neutron counting system (WNC) can be really put into use after installed at the site.

Basis on the application researches before, the effects of γ-ray is reduced by adjusting the gamma-ray


discrimination threshold of the detectors in 2011. The detection efficiency of the system is not change after the adjusting.

15 drummed wastes which may be α-contaminated radioactive waste have been measured by WNC in hot test. The analysis results are consistent with the reference value, which proved the good effects of the applied research work. The application research work of WNC has been accomplished completely; it indicates WNC to classify α radioactive waste is in the practical application stage.

Development on New Style of Drummed Nuclear Waste Neutron Counting System

ZHU Li-qun, XU Xiao-ming, GU Shao-gang, WANG Mian, BAI Lei, LI Xin-jun


Designing a new style of drummed nuclear waste neutron counting system (WNC) was carried out in 2011. 3He proportional tubes are used as detector in this system. According to the limited quantity of 3He tubes, Monte Carlo method is used for simulative calculating to determine some parameters of system to get high efficiency as possible. The transport and auto control compounds of the system have been designed, and the mechanism and electrics also have been designed. At present, the primary part of the system has been developed。

After adjusted, the system will be assembled and located in site, then debugged and capability tested.


Radiation Protection and Environmental Protection

Supervisory Monitoring of Workplace at CIAE in 2011

WANG Shao-lin, SHAO Ming-gang

(Department of Radiation Safety)

1 Introduction

Based on The Routine Monitoring Programme for Workplace at CIAE in 2011 which approved by Division of Safe and Environmental Protection, a management sector of China Institute of Atomic Energy (CIAE), supervisory monitoring of radiation workplace in supervised area at CIAE was carried out by Site Group of Radiation Monitoring and Assessment Research Section, Department of Radiation Safety. Reactors and critical facilities, accelerators, radioisotope production facilities, radiochemical laboratories, an irradiation facility and a hospital were involved in the programme. The monitoring frequency ranged from 1 to 4 times per year. External dose rates (including gamma dose rate and neutron equivalent dose rate), surface contamination and airborne contamination (including the concentration of radioactive aerosol and of radon) were monitored in this supervisory action. The purposes of the monitoring were: 1) to confirm the safety level of workplace and to identify the potential hazard on radiation safety, 2) to demonstrate that the efficiency of operating procedure and radiation protection rules comply with relevant regulations, 3) to estimate the possible upper limit of individual dose and to provide basis for the establishment of individual monitoring programme, and 4) to support decision-making for the management sector of CIAE.

2 Results 2.1 External dose rates

External dose rate monitoring was implemented at 305 workplaces in supervised area where

belonging to 17 departments or divisions, and the dose rates of 1 071 monitoring point-times were

monitored in 2011 (see Table 1). Results showed that the average value of dose rates was 2.55 μSv/h and

the maximum value was 551.5 μSv/h.The statistical results showed that the dose rates of 42.2 percent of

monitoring point-times were below the authorized limit for non-radiological area, of 51.0 percent of

monitoring point-times were below the authorized limit for supervised area, and of 6.8 percent of

monitoring point-times were above or at the authorized limit for supervised area. The workplaces with

dose rates above or at the authorized limit for supervised area were all submitted to the authority and

informed to relevant departments for remediation.

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radiation Protection and Environmental Protection 185

Table 1 Results of external dose rate monitoring of workplace at CIAE in 2011

Number of monitoring point-times

Departments

or divisions

Number of

workplaces

Number of

monitoring

point-times

＜Authorized limit for

non-radiological area

＜Authorized limit for

supervised area

≥Authorized limit for

supervised area

Average

values/

(μSv·h－1)

Maximum

values/

(μSv·h－1)

Department of Radiochemistry

92 360 112 248 0 0.33 2.98

Department of Reactor

Engineering Research and

Design

50 167 103 61 3 0.25 6.85

Department of Nuclear Physics

8 15 9 6 0 0.16 0.85

Department of Nuclear

Technology Application

10 32 27 5 0 0.22 1.28

Department of CEFR Project

11 11 10 1 0 0.14 0.30

Department of CARR Project

11 16 16 0 0 0.11 0.15

Department of Isotope

5 16 5 11 0 0.35 0.91

Department of Radiation Safety

4 27 14 13 0 0.25 0.98

Division of Radiation Metrology

13 31 17 14 0 0.32 2.90

Division of Tandem

Accelerator Upgrading Project

3 13 9 4 0 0.13 0.28

Hi-tech Atomic Technology Inc.

64 245 33 142 70 10.23 551.50

Beijing Atom High-Tech Jinhui

Co., Ltd.

7 40 32 8 0 0.13 0.28

Beijing Capture Co., Ltd.

5 36 26 10 0 0.32 2.06

Beijing Isotope Nuclear Electronic machine Co., Ltd.

1 6 6 0 0 0.10 0.11

Hospital for stuff and workers

17 40 24 16 0 0.26 1.28

Logistic Group 2 6 5 1 0 0.13 0.17

Machining shop 2 10 4 6 0 0.30 0.76

Total 305 1071 452 546 73 2.55 551.5

Note: 1) The authorized limit for non-radiological area is 0.15 μSv/h

2) The authorized limit for supervised area is 3 μSv/h


2.2 Surface contamination Surface contamination monitoring was implemented at 191 workplaces in supervised area where

belonging to 8 departments or divisions, and the surface contamination levels of 506 monitoring point-times were monitored in 2011 (Table 2). Results showed that all the alpha surface contamination levels of monitoring point-times was less than or equal to the Lower Limit of Detection (LLD) of the instruments, the average value of beta surface contamination levels was 1.29 Bq/cm2 and the maximum value was 79.76 Bq/cm2. The statistical results showed that the beta surface contamination levels of 67.2 percent of monitoring point-times were less than or equal to the LLD of the instruments, of 31.8 percent of monitoring point-times were below the control level of surface contamination for supervised area, and of 1.0 percent of monitoring point-times were above or at the control level of surface contamination for supervised area. The workplaces with contamination levels above or at the control level for supervised area were all submitted to the authority and notified to relevant departments for remediation.

Table 2 Results of surface contamination monitoring of workplace at CIAE in 2011

Number of monitoring point-times

(Workbenches, equipment, wall surfaces and floors) Departments or

divisions

Number of

workplaces

Number of

monitoring

point-times

Types ≤LLD ＜Control

level

≥Control

level

Average values/

(Bq·cm－2)

Maximum values/

(Bq·cm－2)

alpha 209 0 0 ≤LLD ≤LLD Department of

Radiochemistry

59 209

beta 115 94 0 0.27 2.00

alpha 139 0 0 ≤LLD ≤LLD Beijing Hi-tech

Atomic Technology

Inc.

59 139

beta 85 53 1 1.13 33.80


Isotope

11 11

beta 8 1 2 29.63 79.76


Reactor

Engineering

Research and

Design

36 96

beta 87 7 2 4.24 25.66


Radiation Safety

8 16

beta 14 2 0 0.16 0.16

alpha 15 0 0 ≤LLD ≤LLD Hospital for stuff

and workers

9 15

beta 15 0 0 ≤LLD ≤LLD

alpha 8 0 0 ≤LLD ≤LLD Division of

Radiation

Metrology

5 8

beta 5 3 0 0.16 0.16

alpha 12 0 0 ≤LLD ≤LLD Logistic Group 4 12

beta 11 1 0 0.16 0.16

alpha 506 0 0 ≤LLD ≤LLD Total 191 506

beta 340 161 5 1.29 79.76

Notes: 1) The LLD of the instruments for alpha is 0.01 Bq/cm2 and for beta is 0.1 Bq/cm2

2) The control level of alpha contamination for supervised area is 0.4 Bq/cm2 and of beta contamination for supervised area is 4 Bq/cm2

3) “≤LLD” mentioned above is not considered in statistics


2.3 Airborne contamination Airborne contamination included the concentration of radioactive aerosol and of radon. Air sampling

and measurement were implemented at 27 workplaces in supervised area where belonging to 5 departments or divisions, and 138 air samples were taken (see Table 3). The statistical results showed that the gross alpha levels of 136 monitoring point-times were at or below background levels, of 2 monitoring point-times were below the authorized limit of the concentration of radioactive aerosol for supervised area, and no workplace was found to exceed the authorized limit of the concentration of radioactive aerosol for supervised area. The gross beta levels of 42 monitoring point-times were at or below background levels, of 96 monitoring point-times were below the authorized limit of the concentration of radioactive aerosol for supervised area, and no workplace was found to exceed the authorized limit of the concentration of radioactive aerosol for supervised area.

Table 3 Results of airborne contamination monitoring of workplace at CIAE in 2011

Distributions of concentration of radioactive aerosol

Departments or

divisions

Number of

workplaces

Number

of

samples

Radiation

nuclides Types

background

level

＜

authorized

limit

≥

authorized

limit

Average

values/

(Bq·m－3)

Maximum

values/

(Bq·m－3)

alpha 75 2 0 3.00×10－3 4.00×10－3 Department of

Radiochemistry

18 77 239Pu 241Am

238U 232Th

125I 99mTc

beta,

gamma

32 45 0 1.78 2.52

alpha 8 0 0 background backgroundDepartment of

Reactor

Engineering

Research and

Design

2 8 60Co 137Cs

beta,

gamma

0 8 0 13.9 15.9

alpha 31 0 0 background backgroundHi-tech Atomic

Technology

Inc.

5 31 131I 125I beta 0 31 0 9.39 26.52

alpha 10 0 0 background backgroundHospital for

stuff and

workers

1 10 131I

beta 10 0 0 background background

alpha 12 0 0 background backgroundDivision of

Radiation

Metrology

1 12 222Rn

beta,

gamma

0 12 0 4.78 6.66

alpha 136 2 0 －－ Total 27 138 －

beta,

gamma

42 32 0 －－

Notes: 1) The background for alpha is 0.3 min－1 and for beta is 130 min－1

2) As for supervised area, the authorized limit of 239Pu is 7.8×10－2 Bq/m3, of 241Am is 9.3×10－2 Bq/m3, of 238U is 4.39×10－1 Bq/m3, of 232Th is 8.62×10－2 Bq/m3, of 125I is 342.5 Bq/m3, of 99Tcm is 8.62×10－4 Bq/m3, of 60Co is 147.1 Bq/m3, of 137Cs is 373.1 Bq/m3 and of 131I is 227.3 Bq/m3

3) The action level for remedial action relating to chronic exposure situations involving radon in workplaces, fall within a yearly average

concentration of 500 to 1 000 Bq of 222Rn per cubic metre of air (equilibrium factor 0.4). Remedial actions should be taken into account

when radon above 500 Bq of 222Rn per cubic metre, and should be carried out when radon above 1 000 Bq of 222Rn per cubic metre


The Biokinetic Model of Americium

WANG Chuan-gao, LUO Zhi-ping (Department of Radiation Safety)

To improve in vivo measurements for detecting internal exposure from transuranium radio nuclides,

such as neptunium, plutonium, americium, the bioknetic model was studied. According to ICRP report (1993, 1995, 1997) and other research, the biokentic model of americium is age-specific and the model could be summarized in Fig. 1.

As shown in Fig. 1, the model mainly includes skeleton, massive soft tissues, blood, liver, kidneys, urine and gonads. After absorbed into blood, activity would take part into human circulation. However there is little information about americium. Only a little data could be acquired from animal experiments. Experiment showed that the blood loses americium at a rate of 33.3 day－1 (corresponding to a removal half time of 30min) and postulate ST0 receiving 30% of americium leaving blood. When describing removal from the circulation, the parameter values are independent of age. After leaving the circulation, americium is mainly deposited at skeleton and liver. Bone surface is the initial place for activity entering and then bone marrow by bone resorption or bone volume by bone formation. Over a few months, activity would be removed from bone marrow to blood and be redistributed in the same pattern as the original input to blood. For americium, liver is also treated as a uniformly mixed pool that loses activity to blood and the GI tract with a biological half-time of 1 year. At last, part of americium would be excreted through urine or faeces.

Fig. 1 Biokinetic model of americium


According to the biokinetic model, the retention or daily excretion fuction of activity have been figured out. For example, Fig. 2 shows the retention or daily excretion of inhalation Type M of americium-241 following acute intake.

To detect the internal dose of americium, two methods of measurement can be chosen, one is radiochemical separation and α-spectrometry on biological samples on urine or faceal samples, another is in vivo measurement with γ-ray spectrometry. The first one has a better detection limit, which is 10－3 Bq, while it isn’t as quickly and convience as in vivo measurement. However, in vivo measurement of americium-241 don’t have adequate sensitivity. Hence, we are exploiting a new spectrometry (Gas Scintillation Proportional Counter, GSPC) which has a higher sensitivity. With GSPC, we can detect americium directly. After acquiring the measure value, we can estimate the internal dose from americium or other supra-uranium elements by equations below:

A=M/m(t) (1) E=Ae(50) (2)

Where, A is the intake; M is measured value; m(t) is predicted value of the measured quantity at time, t, for unit intake (excretion or retention function at time, ti, for unit intake); E is committed effective dose, e(50) is dose coefficient, committed effective dose per unit intake.

Fig. 2 241Am inhalation type M: predicted values (Bq per Bq intake) following acute intake

Research on Health Risk-Based Radioactive Acceptance Criteria of Municipal Solid Waste Landfill

ZHANG Hong-jian, LIU Sen-lin

(Department of Radiation Safety) The article focuses on the topics of Health Risk-Based Radioactive Acceptance Criteria of Municipal

Solid Waste Landfill (MSWL, including municipal refuse landfills or industrial solid waste landfills, MSWL). At first, health risk assessment methodologies of MSWL are built in this research, and health risks of MSWL are assessed. Secondly, the status quo of development and application of acceptable risk levels is investigated, and background risk levels of lying in the natural environment are also assessed. The third, acceptable risk level (lifetime excess carcinogenic risk, 5×10－5) is chosen. At last, Health Risk-Based Radioactive Acceptance Criteria of MSWL are built.

Some innovative disposal options of managing Very Low Level Waste (VLLW) safely and


cost-effectively, such as clearance as non-radioactivity waste, disposal of VLLW into hazardous waste facilities or MSWL, in-situ landfill, restricted recycle and reuse, and so on, have been explored and applied in the last ten years. The Middle Point Landfill in Tennessee of USA, belongs to RCRA Subtitle D Landfill that can accept non-hazardous solid waste. The Middle Point Landfill, having been landfilling VLLW since 1993, is a representative case. Design standards of MSWL in China are stricter than those of MSWL in USA. Safety requirements of MSWL in China are higher than ones of in-situ landfill in Japan. Radioactive acceptance criteria have not been developed and radioactive regulation requirements have not been set up in the present MSWL in China.

Health risk assessment(HRA) methodologies of MSWL are built, and health risks of three stages of MSWL, such as operation period, maintenance and management period after closure, and usage period without any restricted limits, are assessed. The results show that at the operation period, individual lifetime carcinogenic risk for all the carcinogenic chemical contaminants, and hazard index(HI) for all the non-carcinogenic chemical contaminants of landfill worker is 1.6×10－5, 0.62 respectively. Individual lifetime excessive carcinogenic risk for all the carcinogenic chemical contaminants, and HI for all the non-carcinogenic chemical contaminants of the public outside the landfill, is 8.2×10－6, 0.32 respectively. The results of HRA in the site usage period without any restricted limits indicate, that individual lifetime excessive carcinogenic risk for all the carcinogenic chemical contaminants of the adult and the child of the public, is 3.7×10－4, 2.3×10－4, respectively.

Background risks in our daily life are assessed. The results of health risk assessment show that individual lifetime excessive carcinogenic risk for all the naturally-occurring carcinogenic chemical contaminants in the soil for adult and 1-6 a child, due to ingestion and inhalation of soil dust, is 1.3×10－4, 1.7×10－2 respectively, and individual lifetime carcinogenic risk due to drinking water routes for adult and 1-6 a child is 3.9×10－3, 2.5×10－3 respectively. Nowadays 10－4-10－6 range values of individual lifetime carcinogenic risk had been used by many countries as acceptable risk level universally. 5×10－5 of individual lifetime carcinogenic risk has been chose and used as acceptable risk level to derive radioactive acceptance criteria of MSWL.

The derivation courses and results showed that, on the one hand acivtiy concentration values for most of radionuclides in the wastes accepted by MSWL, are different from the clearance levels set up by IAEA Safety Reports Series No.44, and acivtiy concentration values of a fraction of radionuclides are 1-2 orders of magnitude more than the clearance levels set up by IAEA Safety Reports Series No.44; On the other hand health risks of VLLW, which radioactivity concentration is below the certain limit, if accepted by MSWL, is always between 10－4 and 10－6 of individual lifetime carcinogenic risk level.

Simulation of High-Sensitive Measurement for 239Pu

WANG Wei (Department of Radiation Safety)

According to the characteristic of low-energy transuranic element 239Pu in reprocessing plant site, an

in vivo measurement experimental system with room temperature semiconductor detector array (CZT or Silicon detector) for 239Pu internal contamination is studied. This device can provide measurement tools and technical support for monitoring of 239Pu in internal contamination of in vivo measurement. Our study


use China male human body voxel phantom CNMAN and MCNPX to simulate the counts for different detectors (CZT or Silicon detector) when radioactive nuclide 239Pu is well-distributed with lung, according to the simulated results including detector efficiency and photon flux distributing message, we can choose the right detector for high-sensitive measurement for 239Pu and its right position. Our work can provide theoretical principle for further development for these kinds of detector design.

It can be seen from the simulated results that when radionuclide 239Pu are well-distributed with lung and emitted photons are intering into different detectors (CZT or Silicon detector), the detection efficiency of above detectors are all small with 10－7 pulse/photon. Fig. 1a and Fig. 1b describe the comparison of simulated detection efficiency results between these two types of detectors. As can be seen from the figures, the detection efficiency of silicon detector is about 50% lower than that of CZT detector.

Fig. 1 Comparison chart of the detection efficiency between silicon detector and CZT detector

When radionuclide 239Pu are well-distributed with lung of human body phantom CNMAN, the

distribution of photon flux above phantom is non-uniform, there are several positions with higher flux. According to the calculated results of photon flux distribution, we can place the detector above the left and right lungs where have higher photon flux, as a result, the detection efficiency for 239Pu can be improved. Due to our simulated study on the detection efficiency for 239Pu with CZT and Silicon detectors, many factors should be considered according to actual needs to choose the right detector when actual high-sensitive measurement for 239Pu are asked for.

RESEARCH AND DEVELOPMENT FOR TECHNIQUE APPLICATION 195

Neutron Ghost Imaging Technology Research on CARR Reactor

ZHANG Guo-guang1, JIN Ge2, GU Jian-zhong1 （1. Department of Nuclear Technology Application, China Institute of Atomic Energy;

2. University of Science and Technology of China）

Ghost imaging is also known as quantum imaging. Different from the classical imaging, the neutron ghost imaging is based on the quantum mechanics properties of light field and its intrinsic parallel characteristic, and developed by new optical imaging and quantum information parallel processing technology in quantum level. The X-ray or gamma-ray ghost imaging research is now getting more and more worldwide development. Comparing with the traditional optical imaging technology, which is recording the radiation field light intensity distribution to get the information method of target image, the neutron ghost imaging is utilizing and controlling the quantum fluctuations of radiation field to get the object image. The radiation field of the quantum fluctuations in quantum imaging characteristics plays an important role.

Because of the lack of high brightness coherent neutron source, diffraction images can not be got in traditional way. The neutron ghost imaging technology may be the best choice to achieve. We can use the coherent epithermal or cold neutron source to achieve the high resolution imaging which can only got by coherent neutron beams before. The distance from neutron source to detector is about 10 m preliminarily. And the imaging can be better when the neutron monochromatic is higher. The epithermal or cold neutron flux can reach 106 to 107 cm－2. The experimental conditions on CARR reactor are demanded further communication. In China, there is still no expert to develop on neutron ghost imaging research. The CARR reactor is relatively appropriate scientific research platform. Investigation on the CARR reactor platform is very practical significance.

Monte Carlo Simulation for Moderator of Compact D-T Neutron Generator

DOU Yu-ling, WANG Guo-bao, ZHANG Guo-guang, FENG Shu-qiang （Department of Nuclear Technology Application）

In order to study the neutron moderation of D-T neutron generator, moderators with diffident

materials and structures are predicted by Monte Carlo simulations. Neutron generator is simplified as the diameter 20 cm, length 25 cm cylinder. The target is very

small, as a point source. Neutron generated in this reaction has energy 14 MeV and is emitted into 4π irrelative to the target. Other part of generator is assumed to be vacuous.

Metal and graphite is used as moderator material. The structure of moderator is multi-match. Fig. 1 shows the structure of the moderator. The basic component of the moderator contains multiplication materials and moderation materials. Cell 3 is neutron generator, Cell 8 is multiplication materials, Cell 4 and Cell 5 are moderation materials. The material in Cell 1 is the same in Cell 8 and Cell 2 has the same material with Cell 4 and Cell 5. Cell 6 is used for shield. The neutron moderation structure is using hollow


sphere as moderation and hollow cone as outlet. The thermal neutron counts are detected at outlet (Fig. 2).

Fig. 1 Geometric model of moderation Fig. 2 Moderating curve of graphite and polythene

The variance reduction skills, which are provided by the MCNP program, were used try to reduce the computing time and reduce the computational results of the statistical error.

Graphite and polythene are usually used as the neutron moderation materials. Fig. 3 shows the moderation effects of graphite and polythene to neutron.

Fig. 3 Neutron multiplication effect of several metals alone with thickness of graphite

For the neutron moderation structure, the hollow sphere is used as main body moderation, and the

hollow cone is used as outlet. This can get the high-density and well-proportioned thermal neutron beam.

Mapping Nuclear Decay to Complex Network

LI Yong, FANG Jin-qing, LIU Qiang （Department of Nuclear Technology Application）

Network model is always a key topic in the research of network science. Large Unifying Hybrid

Network (LUHNM) theory, which we proposed before, is a universal network model that can be used to depict the diversity and complexity of the natural network. Ideas from LUHNM can be applied to many networks. Nuclear decay is investigated by the view of network science and the relationship of nuclear decay among different radionuclide can be mapped to a network topology directly.

The network includes 1 410 nodes and 1 275 edges. The average degree of the network of nuclear


decay is about 1.8, the cumulative degree distribution still meets the typical power-law distribution, and the corresponding exponent is about 4.1. Not considering their dynamic behavior, the fitting parameters of the nuclear decay network are obtained according to the LUHNM theory proposed by our group before. Their cumulated degree distributions of the nuclear decay network match well. The idea and method may provide a new way to study some other problems of nuclear physics.

Study of Associated α Particle Imaging Technique for Explosives Detection

ZHENG Yu-lai, WANG Qiang, YANG Lu, LI Yong, GUO Feng-mei, WANG Guo-bao （Department of Nuclear Technology Application）

The explosive detecting technique about neutron mainly include the thermal neutron analysis (TNA),

the fast neutron analysis (FNA), the pulse fast and thermal neutron analysis (PFTNA) and the associated α particle imaging technique about fast neutron (API).

The API technique uses fast monochromatic neutrons with energy of 14.1 MeV produced in binary reaction D＋T→4He＋n. In this reaction the α-particle with the energy of 3.5 MeV flights back-to-back with the neutron (in c.m. system). By measuring the α-particle trajectory the direction of the corresponding neutron is determined. These tagged neutrons interact with the interrogated object and can produce γ rays with energy spectra which are unique for each chemical element in the object. The characteristic γ-spectra could serve as “fingerprints” to identify the hidden substance. Fast neutron induced reactions produce specific gamma-rays used to determine the chemical composition of the inspected material. The associated particle technique is employed to precisely locate the interaction points of the neutrons. The unique advantage of the API method is to provide the image of the hidden object in 3-dimensions. It also significantly suppresses the background.

In experiments with neutron intensity of 5×107 s－1，The γ-rays from (n, γ) reactions are registered by LYSO detector with the scintillator of φ63 mm and thickness 50 mm. The graphite is selected as sample to be detected. The detecting time interval is about thirty minute. This experiment has been done by use of FNA method and API method. The Fig. 1a and the Fig. 1b show the energy spectrum of γ-rays detected by use of the FNA method and the API method, respectively. One can see a clear twin peak feature from the carbon line of 4.44 MeV with its single escape (SE) in the Fig. 1b. A large signal-to-background ratio provided by the API method significantly facilitates the identification of the hidden substances.

Fig. 1 Energy spectra of γ rays detected for graphite sample using of FNA (a) and API (b) methods


Monte Carlo Simulation of Dosimetric Parameters for HYBRID PdI Source in Brachytherapy

ZHENG Yu-lai, ZHANG Wen-zai, WANG Qiang （Department of Nuclear Technology Application）

A novel brachytherapy source model, ADVANTAGE HYBRID PdI, has been designed by CIAE For treatment of cancer. In this project, the purpose of this study is to obtain the dosimetric parameters of HYBRID PdI source. The Monte Carlo simulation code system MCNP has been used to calculate air-kerma strength and the dose distribution surrounding the source in the updated TG-43U1 formalism of the AAPM. The dosimetric characteristics of a novel brachytherapy source, composed of a mixture of 125I and 103Pd radioisotopes, have been determined following AAPM TG-43U1 protocol.

A dose calculation model, which is shown in Fig. 1, was developed to determine the dosimetric characteristics of this source design. In this model, Monte Carlo simulated parameters from each isotope of the source were individually determined assuming 1 mCi and 2 mC radioactivity from 125I and 103Pd isotopes, respectively.

Fig. 1 Model of HYBRID PdI source

The following results represent the TG-43U1 parameters from HYBRID PdI source design. These

parameters have been determined according to the TG-43U1 protocol. The calculational result is in good agreement with TG-43U1 (Table 1)．

Table 1 Dosimetric parameters

g(r) Distance/cm

125I 103Pd Hybrid PdI

0.5 1.02 1.23 1.13

1 1.00 1.00 1.00

2 0.885 0.610 0.741

3 0.731 0.358 0.536

4 0.593 0.216 0.396

5 0.471 0.119 0.286

6 0.373 0.064 5 0.211

7 0.268 0.041 5 0.149


NQR Stimulation Technique for Explosives Detection System

HE Gao-kui, QIAN Yu-qing, TIAN Hua-yang, JIN Yu-heng, LIU Yang, JI Shi-liang (Department of Nuclear Technology Application)

A method of customization stimulation signal based on direct digital frequency synthesis (DDS) for

Nuclear Quadrapole Resonance Explosives Detection System is presented. DDS has many advantages, such as high frequency resolution, high convert speed, adjustable signal phase and high stability. With DDS technique, the NQR stimulation signal’s frequency, phase and amplitude can be accurately controlled by digital signal (MCU). Consequently, it is convenient to control the stimulation signal to compensate frequency shifting due to sample temperature changing and gain high signal to noise ratio.

The frequency of DDS signal is as following: f0＝K·Δf＝K·fs/2N 0≤K≤2N－1

Where fs is a reference clock, Δf is the signal frequency resolution，f0 is the DDS signal frequency，K is the digital bits of phase accumulator. For a certain system clock, it is possible to produce expected frequencies by setting the bits of phase accumulator and frequency control word.

The lowest frequency corresponding to K=1, is equal to frequency resolution of DDS: fmin＝Δf＝fs/2N

The system uses a AD9854 in-cooperate with a single Chip Microprocessor. AD9854 has a high speed and performance orthogonal digital to analog converter and a high speed comparator to achieve the orthogonal I and Q outputs. AD9854 has 48 bits frequency resolution and high signal stability. The stimulator hardware sketch diagram is as Fig. 1.

DDS is in parallel connected to MCU, the control computer sends the frequency control word to MCU via a standard USB interface. The MCU then calculates the incoming data and writes them to DDS circuit. Finally, the DDS synthesizes a customized frequency signal.

Application of Grey Relational Cluster Method in Muon Tomography for Materials Detection

WANG Yue

(Department of Nuclear Technology Application) When the number of particles is small, We try to use grey system theory better in dealing the work

which has little sample and incomplete information. Grey relational cluster method is applied for materials detection of the research of Muon tomography for the first time. Grey relational cluster method is the foundation of the system analysis in grey system theory, and it can be used to assort factors which are same to materials detection with Muon tomography.

Fig. 1 System sketch diagram


In the research, observation objects are comic rays including deflexion angle and deflexion displacement. We can get the sequences of objects:

X1＝(x1(1), x1(2)), X2＝(x2(1), x2(2)),…, Xm＝(xm(1), xm(2)) The algorithm using in the research is given as follow. 1) selecting the character reference sequence Yj, j=1, 2,…,l. We use the informations of Muon comic

rays though the iron, lead and uranium for character reference sequence. 2) According to the formulae as follow, we calculate the grey relating degree of Xi|i=1, 2,…,m and

Yj, j=1, 2,…,l respectively.

Finally we get the grey relational matrix:

3) We set a compare modulus, and according to the matix the rays are compared and sorted, so we can distinguish the rays going through the different matierals.

Simulation experiment built a geometry model by Geant4 tool as Fig. 1.

Ten groups of data are selected in the experiment (Table 1).

The compare modulus is set to 0.75 (0.65≤c≤1). We get a result that 1 and 10 are belong to the rays through iron, and 1, 4, 6 and 9 are belong to the rays through lead, and 5 and 8 are the rays through uranium. The result is to be up to the mustard basically.

Table 1 Ten groups

Item x(1)/mrad x(2)/mm Item x(1)/mrad x(2)/mm

X1 19.2 1.79 X6 22.9 2.13

X2 10.2 1.34 X7 12.9 1.22

X3 4.5 0.11 X8 27.9 2.69

X4 16.6 1.63 X9 18.5 1.59

X5 28.0 2.59 X10 11.4 1.15

Fig. 1 Geometry model

|)()(|maxmax|)()(|

|)()(|maxmax|)()(|minmin))(),((

00

00

0 kxkxkxkx

kxkxkxkxkxkx

ikii

ikiikii −+−

−+−=

ξ

ξγ

∑=

=n

kii kxkx

nXX

100 ))(),((1),( γγ

11 12 1

21 22 2

1 2

...

...( )

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

m

mij

s s sm

γ γ γγ γ γ

γ

γ γ γ

⎡ ⎤⎢ ⎥⎢ ⎥= =⎢ ⎥⎢ ⎥⎢ ⎥⎣ ⎦

Γ

IMPORTANT NUCLEAR INSTALLATION AND EQUIPMENT 203

Annual Report on SPR Operation in 2011

NIU Sheng-li

1 Information of operation Operation person: present chief operators are 11 persons, operators are 6 persons; new chief

operators are 3 persons, new operator is 1 person; training chief operators are 3 persons, training operators are 1 persons; transferred chief operator is 0 person; transferred operator is 0 person. Operation data: times of operation are 10; times of unplanned shutdown are 4; operation duration is 3 346.01 h; the released energy is 487.95 MW·d; the rated power is 3.5 MW. Primary loop water: pH=5.9, conductance is 7.15×105 Ω·cm; pool for maintaining: pH=6.0, the conductance is 4.14×105 Ω·cm. Radioactive waste: 41Ar, 4.408×107 m3, 5.235×1011 Bq; primary liquid, 37.09 m3, 2.085× 108 Bq; solid, 0 m3, 0 Bq. 2 State of operation and production

1) The reactor has operated a safely for 139 days, ten times this year. Operation duration: 3 346.01 hours. Released energy: 487.95 MW·d.

2) Total amount of isotopes in one year: One hundred and forty seven cans. Irradiative isotope categories: 131I, 125I, 153Sm, 177Lu, 63Ni, 46Sc. Irradiative silicon: 3 860 kg.

3) Physical measure: Twenty-seven relative flux measurement and three absolute flux measurement were implemented in 2011.

3 Science research and experiments

The metal material of the pressure vessel was irradiated in 49-2 reactor normally.

4 Abnormal states 1) During the operation, something wrong of equipments and instruments could be judged and

repaired in time. 2) The unplanned shutdown of the reactor was four times. Of the four times, the outside supply

power instant broke three times during the operation. Once is because there is something wrong with the cable of the pressure-meter of the second loop.

5 Maintenance items

Operation: Ten times. Unplanned shutdown: Four times. According to the 2011 equipment and instrument’s repair plan, the technology management team arranged the equipments and instruments repair work uniformly.

1) Instruments and equipments checked regularly: Temperature-meter of the primary loop and the second loop; flow-meter of the primary loop and the second loop; water-level instrument of swimming-pool, 308# supply water tank and the second loop well; water pressure-meter of the primary loop and the second loop.

2) The water level of the swimming pool and the spent fuel storage pool were checked. The purified water was supplied suitably.

3) All the production systems were checked normally per month. The crane and silicon manipulator were checked and repaired before each operation. The silicon baskets and tubes were checked and repaired before each operation.


4) The control and protection system and the thermal instrument system and the radioactive monitoring system were checked routine before each operation.

5) In March, a new storage battery was in use instead of the old one. 6) In April, two heat-exchangers of the primary loop were cleaned. 7) In September, the crane of the transportation corridor was changed into a new one. 8) In November, the main control room was fitted up. The room where the second loop pump was

put was reinforced.

6 Fuel management 1) Refueling was implemented six. Eleven boxes spent fuel were removed from reactor core (eleven

boxes, one hundred and seventy-one pieces). Eleven boxes new fuel were installed in reactor core (eleven boxes, one hundred and seventy-one pieces).

2) After refueling, technical staffs drew the core loading chart of the reactor. Recorded storage seat of spent fuel and calculated data of plutonium, remain isotope and elements in spent fuel.

3) Check the fuel regularly and made the records of condition of the storage of the fuel carefully.

7 Training of operation persons 1) 120 operators of five nuclear power station had been trained in 2011. 2) One chief operator and three operators got new licenses because the olds were going to be out of date.

Three operators passed the exam and got the chief operator license. One practicing operator got formal license. 3) All operators were trained about the nuclear safety regulations in 2011. 4) Before each operation all the leaders and operators take a meeting to discuss the issue of operation.

Include: Core loading of reactor and safety, etc.

8 Safety management 1) Management of isotope Check and number the preparing irradiative elements before each operation to keep the quality.

Workers of hall operate diligently in 308# hall and technical staffs supervise in 313# room. The chief operator is responsible for all the operation. So the wrong is lesser and lesser.

2) Operation meeting Before each operation the vice director who is in charge of the operation asks the chief operator,

professional core members to join the operation meeting. Content: Conclude the situation of operators and persons on duty, the problems during the operation and the time of shutdown, and so on. So the rate of wrong of the system and the equipment became lower and lower.

9 Spent fuel transportation

In March, the numbers of the spent fuel checked. In May, the spent fuel was imitated to load in the imitated basket.

10 Operation license

The old operation license became due in October. The new operation license has permitted by the experts to arrive in December.

11 Environment around N.492 factory house

The results of measure for γ are shown in Table 1.

IMPORTANT NUCLEAR INSTALLATION AND EQUIPMENT 205

Table 1 Results of measure for γ

γ dose/(nSv·h－1) Time

East West South North

Spring 163 185 183 170

Summer 166 188 184 171

Autumn 165 184 183 173

Winter 161 184 185 172

12 Person and collectivity dose equivalent

The person number monitored is 44 persons. The collective dose equivalent is 57.22 mSv·person. The average individual dose equivalent is 1.33 mSv. The maximum individual dose equivalent is 8.91 mSv.

HI-13 Tandem Accelerator in 2011

KAN Chao-xin, HU Yue-ming, BAO Yi-wen, FAN Hong-sheng

In 2011, HI-13 tandem accelerator provided 27 kinds of ions and 3800 hours beam time. The

distribution of beam time versus ion was shown in Fig. 1. The tank has been opened 6 times in 2011, most of problems caused by the laddertron charging

system and high voltage stability system, other maintenance work finished for the injector, vacuum system and electronics and control system. Most of vacuum system developing works for all the beam lines has been finished this year, the vacuum devices operating, supervising, and interlock control will be finished by computer.

The important work in 2012 is keeping the accelerator running well, doing some good works for the machine developing and increase operating efficiency.

Fig. 1 HI-13 the distribution of beam time versus ion


Operation and Service Based on 5SDH-2 Accelerator

WANG Zhi-qiang, LUO Hai-long, LIU Yi-na (Radiation Metrology Division)

The 5SDH-2 accelerator was imported from National Electrostatics Corporation of USA in 1996,

which is mainly used to establish mono-energitic neutron reference field. The pulsed upgrading belonging to Key Laboratory project was finished including computer control system in 2006.

As so far, several kinds of mono-energitic neutron with various energy can be provided in use of various nuclear reaction by this accelerator, yield of which is about from 106-109 per second. The proton and deuteron beam can be accelerated, the maximum energy of which is 3.4 MeV. The accelerator can be operated in two modes, namely direct current and pulsed mode. The frequency of pulse can be adjusted which is 4, 2, 1, …, 0.062 5 MHz respectively, the optimum pulse width is between 1 and 2 nanoseconds.

In the past years, the 5SDH-2 accelerator operated for 2 000 hours per year on the whole. The operation services for calibration and relative science study were provided for various institutes mainly including China Academy of Engineering Physics, Northwest Institute of Nuclear Technology, China Institute for Radiation Protection, Chinese Academy of Sciences and China Institute of Atomic Energy. Many key projects are covered which belong to national key project such as National Program on Key Basic Research Project of China (973 Program); and National High-tech R&D Program of China (863 Program), Defense Advance Research Program of Science and Technology and Technology Foundation of National Defence.

In 2011, various services were provided for several institutes by the accelerator. The calibration service was provides for neutron detectors of Northwest Institute of Nuclear Technology by different energy points. The customer is satisfied with the results.

The project “the establishment of keV neutron reference field” has been in progress in use of the accelerator. The cooling experiment of the target tube had finished in the past year, the key trouble was solved. The high voltage stability improved by using “Slit Mode” ensured mono-energitic neutron produced by the reaction 45Sc(n, p)45Ti with narrow resonance zone.

The beam current was provided for the project “the establishment of simulated neutron reference field”. The preliminary measurement of neutron spectrum and ambient dose-equivalent laid a base for success of the project.

In addition, the maintenance and measurement of the neutron standard instruments were done routinely based on the accelerator. Some calibration and test services were provided in use of the accelerator.

APPENDIX·International Scientific Technology Exchanges in 2011 209

International Scientific Technology Exchanges in 2011

In 2012, CIAE sent 432 scholars abroad for taking part in international meeting, technical visiting, further studying and training.

CIAE received more than 300 foreign scholars from about 30 countries, and some reports were given by foreign scholars as follows:

Jan. 5th -11th Mr. Kenneth Littrell, from America SNS visited CIAE and gave the report on the development of research by neutron scattering in SNS.

Apr. 12th -19th Mr. William Yelon from University of Missouri visited CIAE and gave the report on design of CARR diffractometer.

Apr. 22nd Mr. Alain Tournyol Du Clos Picrre Gallo, consular from France Embassy to China, visited CIAE for exchanges about improving power of CEFR.

May 10th Prof. Nguyen Van Giai, Institute of Nuclear Physics, University Paris-XI, France visited CIAE and gave the report on inter crust of neutron star.

May 16th-Jun 1st Prof. Adelmann Andreas from Paul Scherrer Institute visited CIAE and gave the report on precise beam dynamics simulations: from high power cyclotron to (X) FEL modeling.

May 12th Prof. Peter Ring from Technische universitat Munchen and his colleagues visited CIAE and gave the reports on covariant density functional theory and relativistic density functional in nuclear structure.

May 25th-26th Mr. Jeffreyd Chamberlin from U.S. Department of Energy visited CIAE and exchanged low enrichment of MNSR.

Jun. 6th-7th Mr. Laidler James J. and his colleagues from Argonne National Laboratory visited CIAE and exchanged reprocessing separation technology.

Jun. 6th-10th Mr. Vicenzo Palmieri from National Institute of Nuclear Physics visited CIAE and gave the report on Sputtering and deposition in vacuum and its application.

Jun. 6th-10th Mr. Toshiyuki Hattori from Tokyo Institute of Technology visited CIAE and delivered the report on the electron accelerator ridgetron for industrial irradiation.

Jun. 21st-27th Mr. Alexander Ioffe from Forschungzemtrun Juelich, Germany visited CIAE and gave the report on wide-angle polarization analysis for SANS studies of objects with a strong hydrogen contents.

Jun. 23rd Mr. Nobuski Teraoka, from JAEA visited CIAE and gave the report on Japanese Atomic Energy Agency.

Jun. 25th Mr. Leslie Keith Fifield from Australian National University visited CIAE and gave the report on application and development of accelerator mass spectrometry at Australian National University.

Jun. 28th Mr. Slshansky Yury and his colleagues from Scientific and Technical Center RATEC visited CIAE for maintenance and adjustment of neutron inspection explosives.

July 13th Mr. Werner Botzem from NUKEM Technologies GmbH visited CIAE and gave the report on treatment of radioactive waste.

July 18th Mr. Filip G. Kondev from Argonne National Laboratory gave the report on CARIBU facility at ATLAS: Advanced Fuel Cycle Application, Nuclear Structure and Astrophysics and Decay Data Evaluations and Measurements.

Aug. 18th Mr. Raymond from the Ohio State University gave the report on neutron detection and its


application in reactor safety. Sep. 1st-7th Mr. Giuseppe Gorini from Univesita degli Studi di Milano-Bicocca gave the report on

the development of research by neutron scattering. Sep. 5th-9th Mr. Naohiko Otsuka from IAEA gave the introduction to EXFOR. Sep. 12th-18th Mr. Jiang Ma from University of Nevada gave the report on oxygen sensor

development for lead bismuth eutectic and gas phase oxygen control for lead bismuth eutectic. Sep. 14th Mr. Lui Yiu-Wing from Texas A&M University gave the report on giant monopole

resonance: expected and unexpected. Sep. 23rd Mr. Mary Patricia Nell from DOE gave the report on experiences on radwaste

management and D&D of nuclear facilities in DOE. Sep. 25th Mr. Mike Seidel from PSI gave the report on an introduction to the PSI facility. Sep. 26th-30th Mr. Suga Kiyoshi from Suzuki Shiken, Japan gave the report on the application of

PCT instrument in hydrogen storage materials. Oct. 24th-28th Mr. Renata Mikolajczak from Institute of Atomic Energy visited CIAE and gave the

lecture on current status of radiopharmaceuticals in Europe/Poland, development of Lu-177/Y-90 radiopharmaceuticals and preparation and quality control of Lu-177/Y-90 labelled antibodies.

Oct. 10th Prof. Claudio Spitaleri from INFN, Italy gave the report on theory and application of the Trojan horse method.

Oct. 10th Mr. Robin Forrest from IAEA gave the report on nuclear data acidities of IAEA NDS and activation data for fusion and ways to identify the important nuclides and reations.

Oct. 15th Mr. Manuel Garcia-Leon from University of Seville gave the introduction accelerator mass spectrometry at the Spanish national center for accelerators.

Oct. 18th Mr. Lionel Merlat from French-German Research Institute of Saint Louis gave the report on research of illicit substance detection by nuclear quadrupole resonance.

Oct. 18th Mr. T. Golashvili T. from Russian ROSATOM Joint Stock Company gave the lecture on evaluation the discrepant experimental data and recommended decay decay in Russia.

Oct. 25th Mr. Petrov Anatoly from Y.G. Khlopin Radium Institute gave the introduction on boron isotopes separation technology in Y.G. Khlopin Radium Institute.

Nov. 2nd Mr. Yosuke Katsumura from nuclear professional school, the University of Tokyo gave the report on the research of radiolytic product and mechanism of TBP, a model for radiolysis of nitric acid and its application to the radiation chemistry of uranium ion in nitric acid medium and the introduction of picoseconds pulse radiolysis equipment and the development in picoseconds pulse radiolysis equipment in Tokyo University.

Nov. 3rd Mr. Bradley Sherrill from Michigan State University gave the report on overview of the facility for rare isotope beams.

Nov. 6th Mr. Alberto Facco from INFN Laboratori Nazinali di Legnaro gave the introduction on superconducting radio frequency and some progress of international project about intense proton accelerator and last developments on RF controls at LNL.

Nov. 14 Mr. Zoran Drac from IAEA gave the report on enhancing the capabilities of national institutions supporting nuclear power development.

Nov. 23rd Mr. Roger W. staehle from University of Minnesota gave the report on elements of reliability of Chinese nuclear plants and elements of aging in nuclear equipment.

APPENDIX·CIAE Seminars in 2011 211

CIAE Seminars in 2011

No. Topics Speaker Date 1 High pressure—a new dimension in physics study MAO He-guang 2011.08.19 2 The key science and engineering technology problem of

nuclear fusion resource system PAN Chuan-hong 2011.11.25

3 25th “May 4” Youth Symposium 2011.04 Experimental studies of exotic two-particle emission

from high-lying excited states of proton-rich nuclei 17,18Ne and 28P

XU Xin-xing

Experimental study of shear mechanism in A~110 mass region HE Chuang-ye

Technique of single event upset mapping SHI Shu-ting New determination of the 13C(p, γ)14N astrophysical S

factor and reaction rate from the 13C(7Li, 6He)14N reaction

LI Yun-ju

The design of control system for instrument neutron activation analysis of CARR

XIAO Cai-jin

FEM simulation of residual stress by hole cold expansion

LIU Xiao-long

The fusion reaction research of 32S+90,96Zr at near-barrier energy region

JIA Hui-ming

Study of calibration method of absorbed dose for low proton energy using ionization method

CHEN Yi-zhen

Ananlytical method of N, N-dimethylhydroxylamine and methylhydrazine in Purex process

LI Chuan-bo

Development and application of the 238Pu radioactive source for poison alarm

WU Zong-xian

Determination of uranium and nitric acid in feed solution of uranium purification process by near infrared spectroscopy

LI Ding-ming

The separation and preliminary evaluation of biodistribution of the L-BPA

LI Feng-lin

Application of anion exchange fiber on time-resolved fluorescent method in measuring U pretreatment

LIANG Liang

Development of chemiluminescence enzyme immunoassay for the detection of folic acid and preparation of monoclonal antibodies against FA

LIU Ting

A new radioanalytical technique of 90Sr in soils SHU Fu-jun Preparation technology of 103Pd-125I complex sources LIU Zhuo


Determination of 240Pu/239Pu at ultra trace level with MC-ICP-MS

ZHANG Ji-long

4π liquid scintillation coincidence absolute measurement automatic system

QI Jie

Study on the calculating the second dimension retention index in comprehensive two-dimensional gas chromatography spectrometry

ZHAO Ya-ping

Labelelling of TGLA with 131I and its biodistribution QIN Hong-bin The improvement research of plutonium purification

cycle in Purex process ZUO Chen

Solution for research and manufacture of DN300 sodium valve

LV Ming-yu

Conceptual design of general structure in lunar-surface reactor power system

YAO Cheng-zhi

Utilization of perturbation method in in-core fuel management optimization

YANG Xiao-yan

Study on deuterium and tritium technics for the neutron tube

SONG Ying-min

A new fitting and iteration method to correct the measured core reactivity

HU Yun

The status of multiscale modelling of radiation damage in structural materials in CIAE

HE Xin-fu

Test and improvements of CEFR alarm system SHAN Hao Development and application of a thermal hydraulic

analysis code for annular fuel assemblies DIAO Jun-hui

Seismic analysis of fast reactor core assemblies with fluid-structure interaction using a homogenization method

WANG Lu-bo

The improvement of 49-2 reactor primary heat exchanger cleaning method

YANG Chen

Sodium spray fire―Design and experimental method LIU Chen Development of a thermal economics analysis code for

thermal-power system of nuclear plant ZHANG Song-mei

The measurement and analysis of CEFR’s SVRE ZHOU Ke-yuan The measurement and analysis of fission cross section

ratio and capture-fission cross section ratio of 237Np/235UWANG Shi-xi

Experimental calibration and precision calculation of sweep rate for optic streak camera

TIAN Bao-xian

Design and development of medical cyclotron CUI Tao Single-shot measurement device of high power UV

ultrashort pulse laser XU Yong-sheng

Design and verification of the RF system for medical cyclotron

LI Peng-zhan

APPENDIX·CIAE Seminars in 2011 213

Monte Carlo simulation for the exposives inspection technique based the Associated α-Particle method

ZHENG Yu-lai

The biological effect of 12C heavy ions to chromosome of human peripheral blood lymphocytes

WANG Chuan-gao

The design of high power S-band microwave test bench ZHU Zhi-bin The development of multi-channel pulse analyzer

system of BIXS JI Xiao-mei

Research on optical transmission of large area portable beta surface contamination monitor

HOU Jie

The study on the data-analysis of TGS under the continual scanning mode

ZHOU Zhi-bo

The development of the water-meter statistical system CHENG Xi The construction of the treatment in CIAE LI Na Status and Improvement of Citations of Atomic Energy

Science and Technology in 2000-2010 TANG Xiao-hao

Performance appraisal system design of research post based on KRIF

MA Dan

Briefly talking about the creative application of volunteers in our community—Taking the example of the theme report meeting for 60 years of innovation and development

ZHANG Jing-song

The strategy to apply for the nuclear energy exploiture scientific research project in CIAE

SONG Li-jun

How do we initiate projects on anti-terrorism in our institute

LIU Ying-yu

Beijing patent pilot project and some advice WANG Gui-liang The present state of education and training at CNNC

graduate school FU Ran

Drugs selection and opportunity in the endocrine therapy on breast cancer

GAO Hong-bo

Effects of hyperbaric oxygen therapy on heart rate and its clinical significance

FU Yang

Helicobacter pylori infection and inflammation of the correlation factor

CHEN Juan

Short term treatment effect of using iodine[131] matuximab injection to treat 79 patients with advanced primary liver cancer

JIN Cong-jun


Subject of Prize of Science, Technology and Industry for National Defense

No. Subjects Contributories Grade prize

1 Design and Construction of the Passive Heat Removal System of China Experimental Fast Reactor

YAN Fu-chang, YE Yuan-wu, XU Yi-jan, LIU Lian-ping, LIU Gui-juan, YIU Zhi-ming, TANG Long, ZHANG Yan, YU Hua-jin, CHEN Yi-shao

2

2 Design and Manufacture of Facilities for Replaceable Machines in CEFR

WANG Ming-zheng, YANG Kong-li, SUN Gang, GU Ji-pin, YU Tuan-jie, JIN Fang-lei, LIN Jian-ru, XU Bao yu, LI Hai, LIU Zhao-yang

2

3 The Production and Filling of the Na-Kalloy as Heat Transfer Medium Used in the Cold Trap of CEFR

DU Hai-ou, HON Shun-zhang, WU Jie, WANG Rou-dong, XIE Chun, XU Yong-xing

2

4 The Stand for H－ Ion Source and Pulsed Beam Injection Line With High Intensity

ZHANG Tian-jue, AN Shi-zhong, JIA Xian-lu, LV Yin-long, YIN Zhi-guo, SONG Guo-fang, LI Peng-zhan, XIE Huai-dong, LIU Geng-shou, ZOU Jian

2

5 Development and Application of the Irradiation Facility Dedicated for Single Event Effect Induced by Heavy ion Strikes on Microelectronic Devices

GUO Gang, CHEN Quan, SHEN Dong-jun, HU Yue-ming, SHI Shu-ting, XU Jin-cheng, HUI Nin, LU Xiu-qin, KAN Zhao-xin, LIU Jian-cheng,

2

6 The Application Research and in-sute Test of Chemical Decontamination for the Large Carbon Steel Tank and Stainless Steel Equipment

ZHENG Zuo-xi, ZHU Xin-yan, XIE Wei-hong, MA Mei-hua, XIA Ming-xu, BAO Fang, WANG Xiao-qiang, ZHAO Hua-song, TAN Yu-ping, LI Hong-zhan

2

7 Study of Dose Calibration for (5~40 MeV) Proton Irradiation

LIU Ming, CHEN Yi-zhen, YE Hong-sheng, CHEN Ke-sheng, XU Li-jun, WANG Feng, SU Dan, WANG Hong-yu, XIA Wen, CUI Ying

2

8 Studies on the Artery Potassium Heat Pipe

CHAI Bao-hua, DU Kai-wen, XU Guo-hua, WEI Guo-feng, WEI Guang-ren

3

9 Development of an Online Enrichment Monitor for UF6 Gas of Uranium Enrichment Plant

LV Xue-sheng, LIU Guo-rong, JIN Hui-min, ZHAO Yong-gang, HAO Xue-yuan

3

10 Design of the Control System of the Power of the CEFR

LIU Gui-juan, QIAO Feng, YAO Yuan, DUAN Tian-ying, LIU ZHi-guo

3

APPENDIX·Subject of Prize of Science & Technology for China National Nuclear Corporation 215

Subject of Prize of Science & Technology for China National Nuclear Corporation


1 The Study on Purification of XX With the Process of Electrochemical Dissolution and Solvent Extraction

YE Guo-an, OU YANG Ying-gen, HU Xiao-dan, LUO Fang-xiang, LI Hui-bo, TANG Hong-bin, LIU Li-sheng, GUO Jian-hua, LIU Xie-chun, WANG Xiao-yong, LI Gao-liang, HE Hui, CHANG Li, LAN Tian, SU Ming-ye

1

2 Design and Construction of the Passive Heat Removal System of China Experimental Fast Reactor

YAN Fu-chang, YE Yuan-wu, XU Yi-jan, LIU Lian-ping, LIU Gui-juan, YIU Zhi-ming, TANG Long, ZHANG Yan, YU Hua-jin, CHEN Yi-shao, JIN Ye, LIU Yi-zhe, LUO Xue-jun, CHEN Dao-long, LIU Yu

1

3 Development and Application of the Irradiation Facility Dedicated for Single Event Effect Induced by Heavy ion Strikes on Microelectronic Devices

GUO Gang, CHEN Quan, SHEN Dong-jun, HU Yue-ming, SHI Shu-ting, XU Jin-cheng, HUI Nin, LU Xiu-qin, KAN Zhao-xin, LIU Jian-cheng,

2

4 Study of Dose Calibration for (5~40 MeV) Proton Irradiation

LIU Ming, CHEN Yi-zhen, YE Hong-sheng, Chen Ke-sheng, XU Li-jun, WANG Feng, SU Dan, WANG Hong-yu, XIA Wen, CUI Ying

2

5 Design of Reactor Vessels in Pool for CARR

SHI Chen-lei, ZHANG Zhan-li, FAN Yue-rong, LANG Rui-feng, SUN Lin-zhi, LIU Xing-min, HAN Hai-fen, DAI Chang-nian, YANG Chang-jiang, JIANG Bai-hua

2

6 Studies on the Artery Potassium Heat Pipe

CHAI Bao-hua, DU Kai-wen, XU Guo-hua, WEI Guo-feng, WEI Guang-ren, YANG Qi-fa, WANG Wei, GAO Shan, FENG Bo, BI Ke-ming

2

7 The Improvement and Adjustment of the Control Rod System

ZHANG Ying-chao, GAO Yong-guang, ZHANG Ming-kui, KANG Ya-lun, JI Song-tao, HUANG Dao-li, MA Ming-wu, WANG Hui, SONG Guo-liang, CHEN Li-xia

2

8 The Design for Digital Control and Protection System of CARR

XU Qi-guo, ZHANG Ming-kui, CENG Hai, LI Song, LI Zhen-yi, CHEN Hui-qiang, SONG Yun-peng, SONG Guo-liang, TANG Guo-jing, XIAO Chen

2

9 Engineering Application Research and In-Situ Test of Chemical Decontamination for the Large Storage Tanks made of Carbon Steel

ZHENG Zuo-xi, ZHU Xin-yan, LIAO Yuan-zong, HOU Hui-juan, MA Wen-ge, SHA Feng, CHEN Shu-ming, CHEN Ji-zhao, ZHAO Hua-song, LIU Zhi-chao

2

10 The Robotic System for Nuclear Inspection and Emergency Treatment

XIAO Xue-fu, CHOU Wu-sheng, HAN Yong-chao, WANG Tiao-miao, CHEN Ling, ZHANG Tao-yi, XIAO Weng-hui, LIU Yuan, LIU Rui-yui, LUO Zhi-ping

2

11 Design and Manufacture of Fuel Operating Control System for CEFR

DONG Sheng-guo, ZHU Hao, MA Hong-sheng, TANG Ji-ben, ZHA Li-xia, DUAN Tian-ying, ZHANG Xi-mei, LIANG Hong-zai, MA Da-yuan, LIN Jian-ru

2


12 Design of CEFR Protection System

LIU Guo-fa, XUE Chang-lin, DUAN Tian-ying, LIU Gui-juan, FENG Wei-wei, ZUO Xin, CAO Jie, YU Zheng, YAO Yuan, XIE Yi

2

13 The China Experiment Fast Reactor Accidents and Troubles steam Generation Systems Design and Building

LI Wen-hong, MA Yong-gang, LIU Gui-juan, YU Hua-jin, DUAN Tian-ying, ZHOU Li-jun, LV Gang, LI Tong-sheng, QI Min, LUO Xue-yun

2

14 The Stand for H－ Ion Source and Pulsed Beam Injection Line With High Intensity

ZHANG Tian-jue, AN Shi-zhong, JIA Xian-lu, LV Yin-long, YIN ZHi-guo, SONG Guo-fang, LI Peng-zhan, XIE Huai-dong, LIU Geng-shou, ZOU Jian

2

15 Development of an Online Enrichment Monitor for UF6 Gas of Uranium Enrichment Plant

LV Xue-sheng, LIU Guo-rong, JIN Hui-min, ZHAO Yong-gang, HAO Xue-yuan

3

16 Simulation Study and Detector Development for RHIC/PHENIX Relativistic

LI Xiao-mei, HU Shou-yang, ZHOU Jing, BAI Xin-zhan

3

17 Design and Manufacture of Facilities for Replaceable Machines in CEFR

WANG Ming-zheng, YANG Kong-li, SUN Gang, GU Ji-pin, YU Tuan-jie

3

18 The China Experiment Fast Reactor Accidents and Troubles Steam Generation Systems Design and Building

PEI Zhi-yong, ZHOU Yu-ying, LIN Jian-yu, LV Ming-yu, YU Chun-li

3

19 Design of Spent Fuel Cleaning System for CEFR

LU Xiao-chun, YUAN Wai-mei, YANG Jian-wei, WAN Ji-hua, TANG Zhao-hui

3

20 Design of the Control System of the Power of the CEFR

LIU Gui-juan, QIAO Feng, YAO Yuan,DUAN Tian-ying, LIU ZHi-guo

3

21 Study of Analysis and Monitoring System of Impurities in Sodium at CEFR

HOU Shun-zhang, YU Xiao-chen, ZHANG Xi-mei, XIE Chun, XU Chi

3

22 Process Detecting System Design and Facilities Develop for the Nuclear Island of CEFR

CHEN Dao-long, YANG Jian-wei, DONG Kang-li, LI Tong-sheng, LI Xin-ying

3

23 Development of PSA Technology and Its Application in China Experimental Fast Reactor

REN Li-xia, HU Wen-jun, YU Hong, YANG Hong-yi, QIAN Hong-tao

3

24 Fundamental Algorithm Study on Beam Dynamics of High Intensity Cyclotron and Development of the Large Scale Parallel Computation Cobe

YANG Jian-jun, ZHANG Tian-jue, AN Shi-zhong, YIN Zhi-guo, BI Yuan-jie

3

25 Design of Plate-type Dispersion Fuel Assembly for CARR

KAN YA-lun, ZhANG Ai-min, SHEN Feng, LU Xing-min, CHEN Hui-qiang

3

26 Design of Parameter Measuring System for China Advanced Research Reactor

LI Song, JIU Huai-qi, ZHANG Ming-kui, LI Hua, LI Chuan-xia

3

APPENDIX·Subject of Prize of Science & Technology for China Nuclear Energy Association 217

Subject of Prize of Science & Technology for China Nuclear Energy Association


1 Design and Manufacture of Fuel Operating Control System for CEFR

DONG Sheng-guo, ZHU Hao, MA Hong-sheng, TANG Ji-ben, ZHA Li-xia, DUAN Tian-ying, ZHANG Xi-mei, LIANG Hong-zai,MA Da-yuan, LIN Jian-ru, LIU Jian, MA Jian-ming, YAN Hua, JIN Yu, BAI Xin-ran

2

2 Process Detecting System Design and Facilities Develop for the Nuclear Island of CEFR

CHEN Dao-long, YANG Jian-wei, DONG Kang-le, LI Tong-sheng, LI Xin-ying, PENG Sheng-zhi, WANG Xuan, ZHANG Yan, XIAO He, LV Peng, YANG Yang, CUI Guo-sheng, SHANG Yun-zhi, DUAN Tian-ying, LIU Guo-fa

3

3 The Design of Heavy-Water System and Other Related Systems for China Advanced Research Reactor (CARR)

HAN Hai-fen, ZHANG Jin-shen, LI Jun-de, HUANG Xing-rong, SHI Jia-juan, JIANG Bai-hua, WANG Qiang, LIU Tian-cai, DAI Shou-tong, ZHANG Ying-Qi

3


National Prize for Progress in Science and Technology on Energy in 2010


1 Master Design of Loops of China Advanced Research Reactor (CARR)

HUANG Ru-xian, ZHANG Xiao-rong, XIE Guang-shan, QIAN Shun-fa, DUAN Hai-yan, HUANG Chen, SUN Gang, YU Tuan-jie, LI Jun-de, DUAN Jia-qing

2

APPENDIX·Science and Technology Award of Beijing Municipality in 2010 219

Science and Technology Award of Beijing Municipality in 2010


1 Study of the Key Reactions in Evolution of Stars

LI Zhi-hong, LIU Wei-ping, GUO Bing, WANG You-bao, BAI Xi-xiang, SU jun

3

2 Research of Several Important Issues on Theory and Application of Network Science

FANG Jin-qing, WANG Xiao-fan, ZHENG Zhi-gang, LI Xiang, DI Zeng-ru, FAN Ying

3


CIAE Application of Patent in 2011

Serial number

Apply item Assignee Application No. Style

1 MHz ns pulsed beam production device

AN Shi-zhong, YIN Zhi-guo, SONG Guo-fang, LI Peng-zhan, LIU Geng-shou

201120061174.0 Utility model

2 Measurement device for MHz ns pulsed beam

AN Shi-zhong, XIE Huai-dong, GUAN Feng-ping, YING Zhi-guo


3 Digital protection system for reactors based on general utilization

ZHANG Ming-kui, YANG Zi-jue, XU Qi-guo, LI Song, LIU Jiang-yan, SONG Guo-liang

201110045960.6 Invention

4 A switching device for step motor driving

XU Qi-guo, ZHANG Ming-kui, CENG Hai, SONG Guo-liang, LI Song, LIU Jiang-yan

201110045959.3 Invention

5 A switching device for step motor driving used in the power adjustment system of reactors



6 Reactor control rod structure of frame style

ZHANG Ai-min, KE Guo-tu, SUN Zhi-yong

201110060043.5 Invention

7 Reactor control rod structure of frame style



8 Neutron source initiated by reactors

SHI Yong-qian, ZHU Qing-fu 201110129866.9 Invention

9 Tubular grid spacer for two-sided cooling fuel rod of pressurized water reactor

ZHANG Ru-xian, ZHANG Ai-min, JI Song-tao, ZHANG Pei-sheng, HE Xiao-jun, DIAO Jun-hui, ZHANG Yi

201110200081.6 Invention







APPENDIX·CIAE Application of Patent in 2011 221

12 An observation device featured with radiation photography resisting

YIN Zhen-guo, WANG Xin, WANG Ke-jiang, LIU Xin-ao

201110380355.4 Invention

13 A measurement method for absolute activity of γ source

YAO Li-nong, WANG Xin, WANG Ke-jiang, BI Ke-ming, LIU Xin-ao, YIN Zhen-guo, YAN Tian-yu

201110380413.3 Invention

14 An leak detection device for conducting liquid

WANG Qiang, ZAN Huai-qi, LI Song


15 An integration throttling set

LI Song, LI Hua, ZAN Huai-qi 201120556766.X Utility model

16 Hybrid physical-chemical cleansening technique for reactor heat exchanger

YANG Chen, QU Pu, JI Xue-yi, WANG Zuo-qing, LIU Jian-zhong

201110451372.2 Invention

17 A gripping apparatus for fuel element

YAO Cheng-zhi, ZHANG Jin-shan, FAN Yue-rong, FENG Jia-min, SHI Chen-lei, YI Da-yong

201110451386.4 Invention

18 A gripping apparatus for fuel element

YAO Cheng-zhi, ZHANG Jin-shan, FAN Yue-rong, FENG Jia-min, SHI Chen-lei, YI Da-yong


19 A cleaning tool for heat exchanger of poor reactor

YANG Chen, QU Pu, JI Xue-yi, WANG Zuo-qing, LIU Jian-zhong


20 Abundance analysis method for uranium isotope

QIAN Ya-hua, WU Ju-zhong, YANG Yi, ZHENG Wei-ming, LIU Shi-long

201110040236.4 Invention

21 A measurement container of on-line inspection device for the uranium abundance of UF6

LV Xue-sheng, JIN Hun-min, ZHAO Rong-gang, LIU Guo- rong, LI Jin-huai

201110051745.7 Invention


LV Xue-sheng, JIN Hun-min, ZHAO Rong-gang, LIU Guo-rong, LI Jin-huai


23 A measurement method for uranium enrichment

LI Jian-hua, JIN Hun-min, ZHAO Rong-gang, CHANG Zhi-yuan, LV Xue-sheng, WANG

201110060041.6 Invention


Xin, LI Li-li 24 A method to improve

the cycles of Pu concentration in the Purex process

LUO Fang-xiang, LIU Xie-chun, XIAO Song-tao, LAN Tian, YANG He, YE Guo-an, ZHANG Hu, LI Gao-liang

201110081587.X Invention

25 An integration glove box system for precise measurement of Pu content

LIU Quan-wei, LUO Zhong-yan, ZHU Hai-qiao, LIANG Jing, WU Ji-zhong


26 A method to directly measure the concentration of mixed components of U, HNO3 and HNO2

LI Li, ZHANG Hu, YE Guo-an 201110097465.X Invention

27 An extraction spectrophotometric method for precise measurement of uranium

ZHU HAI-qiao, WU Ji-zhong, CHANG Zhi-yuan, LIU Quan-wei

201110097471.5 Invention

28 A method of using Ag+ to catalyze electrolytic oxidation to destroy acetic acid in system containing nitric acid

LI Gao-liang, HE Hun, TANG Hong-bin, YE Guo-an

201110097473.4 Invention

29 A preparation method for uranous solution

LI Bin, HE Hun, TANG Hong-bin, YE Guo-an, ZHANG Qiu-yue, CHEN Yan-xin, LIU Jin-ping

201110097474.9 Invention

30 A method of analysing methylhydrazine

LI Chuan-bo, ZHENG Wei-fang, YAN Tai-hong, LIU Jin-ping, ZHANG Yu, BIAN Xiao-yan, ZUO Chen, XIAN Liang, YUAN Zhong-wei, ZHANG Bo-qing, ZHANG Qi-zhen, LOU Hai-lin

201110153007.3 Invention

31 A method of analysing N, N-dimethyl tibial amine

LI Chuan-bo, LIU Jin-ping, ZHENG Wei-fang, YAN Tai-hong, ZHANG Yu, ZUO Chen, BIAN Xiao-yan, XIAN Liang, YUAN Zhong-wei, ZHANG Bo-qing, ZHANG Qi-zhen, LOU Hai-lin

201110153010.5 Invention

32 A preparation method for selective adsorbent of inorganic Sr

ZHANG Zhen-tao, YOU Xin-feng, MA Hun, BAI Yang, WANG Lei, LIANG Xian-yuan

201110179497.4 Invention


33 A preparation method for selective adsorbent of inorganic Cs

ZHANG Zhen-tao, YOU Xin-feng, MA Hun, BAI Yang, WANG Lei, LIANG Xian-yuan

201110179500.2 Invention

34 A method for uranium purification cycle in the Purex process

BIAN Xiao-yan, ZHANG Bo-qing, ZHENG Wei-fang, LOU Hai-lin, ZUO Chen, YAN Tai-hong, ZHANG Yu, YUAN Zhong-wei, LI Chuan-bo, XIAN Liang, JIAO Hai-yang, DI Ying

201110179516.3 Invention

35 A method of measuring single uranium particle isotope ratio using SEM-ICP_MS

WANG Xiao-ming, LI Li-li, ZHANG Yan, ZHU Lin-qiao, ZHAO Yong-gang

201110179528.6 Invention

36 Separation material for separation extraction of technetium in acid solution system

LI Hun-bo, KONG Yan-rong, JIA Yong-feng, WANG Xiao-rong, LIN Can-sheng, SU Zhe, LIU Zhan-yuan, SONG Feng-li, WANG Hun, LIU Geng, YUAN Jie-qiong, CONG Hai-feng

201110179590.5 Invention

37 A synthetic method for triisobutylphosphine sulfide

LI Hun-bo, SU Zhe, LIN Can-sheng, SONG Feng-li, WANG Xiao-rong, YUAN Jie-qiong, CONG Hai-feng, LIU Zhan-yuan

201110179603.9 Invention

38 A method of U-Pu separation in the Purex process

XIAO Song-tao, LI Li, YE Guo-an, LOU Fang-xiang, LIU Xie-chun, YANG He, LAN Tian

201110205447.9 Invention

39 A hand held calculating instrument for passive neutron

ZHU Li-qun 201110258462.X Invention

40 A device for oxidization adjustment of valence state of Pu using N2O4

LI Gao-liang, HE Hun, ZHENG Wei-fang, LI Hui-rong, TANG Hong-bin, YE Guo-an, LAN Tian, ZHANG Hu, LOU Fang-xiang

201110261272.3 Invention

41 An electrodeless conductivity analyser of small sample intake

ZHANG Li-hua, FAN De-jun, WU Ji-zhong, SHAO Xiao-xiong, QIAN Hong-juan, ZHANG Qian-ci, ZHENG Wei-ming, LIU Huan-liang


42 A uranous analyzing method

ZHANG Li-hua, QIAN Hong-juan, LIU Huan-liang, WANG Tie-jian, WANG Ling,



FU Jian-li, WU Ji-zhong, LI Ding-ming

43 A calibration method for non equivalent standard sample

WANG Zhong-qi, SHAO Jie-wen, CHENG Yi-mei, BAI Lei, ZONG Bo, GAO Qiang, WANG Yi-bo, GAN Lin

201110301218.7 Invention

44 A catalytic oxidation method for Pu in the nitric acid system

CHANG Li, TIAN Bao-sheng, ZHANG Qian, GUO Jian-hua, LIU Li-sheng, CHANG Shang-wen, WANG Chang-shui, LI Rui-xue, OUYANG Ying-gen

201110358154.4 Invention

45 A pre-treatment method for trace Pu sample

LIANG Jing, WU Ji-zhong, SU Tao, TAN Shu-ping, LIU Huan-liang, ZHAO Sheng-yang

201110358170.3 Invention

46 A preparation method for the composite of Cs-137 extraction

YOU Xin-feng, ZHANG Zhen-tao, MA Hun

201110380381.7 Invention

47 A modularization neutron detection device with variable structure

MENG Yan-tai, ZHU Li-qun, YIN Hong-he, WANG Xiao-zhong, LU Wen-guang, BAI Lei, JIA Xiang-jun, HU Shao-gang, SHAO Jie-wen, WANG Mian

201110380383.6 Invention

48 A large area portable monitor for B surface contamination

HOU Jie, QU Yan-tao, MA Ji-zeng


49 A portable monitoring system for internal radiation somatometry

QU Yan-tao, WANG Ying, WANG Kai, XU Yong-jun, WANG Zhong-wen

201110380384.0 Invention

50 A heating and condensing device with a hollow structure

PAN Jing-shun, WEN Fu-ping, CHEN Ling


51 An imaging type laser velocity interferometer used for diagnosis

ZHANG Ji 201110226881.5 Invention

52 A vehicle scanning inspection device

ZHANG Guo-guang, SUN Han-cheng, SONG Xiao-jian, WU Qing-sheng, ZHU Jia-zheng, SONG Xin-zeng, FENG Shu-qiang, ZHAO Xiao

201110332642.8 Invention

53 A vehicle scanning inspection device

ZHANG Guo-guang, SUN Han-cheng, SONG Xiao-jian, WU Qing-sheng, ZHU Jia-zheng, SONG Xin-zeng, FENG



Shu-Qiang, ZHAO Xiao 54 A preparation

technique for capacitance Frisch-grid CZT detector

MENG Xin, HAO Xiao-yong, ZHANG Kai, LIU Yang, HE Gao-kui, CHENG Guo-zhu

201110344109.3 Invention

55 An electron irradiation accelerator featured with titanium film protection function

LI Jin-hai, HAN Guang-wen, HUANG Jun

201110380385.5 Invention

56 An on-line dismounting device of electron gun for electron accelerator

LI Jin-hai, HUANG Jun, YIN Meng

201110380412.9 Invention

57 An imaging type laser velocity interferometer system used for diagnosis

WANG Zhao, LIANG Jing, HE Yi-gueng, TIAO Bao-xian, TANG Xiu-zhang


58 A proton calibration dose system using Faraday cup method

LIN Ming, YE Hong-sheng, CHEN Ke-sheng, XU Li-jun, Chen Yi-zhen, XIA Wen

201110051741.9 Invention

59 A vacuum rotating target

LIN Ming, YE Hong-sheng, CHEN Ke-sheng, XU Li-jun, Chen Yi-zhen, XIA Wen

201110051747.6 Invention

60 A neutron personnel dose monitor capable of energy compensation

WEI Ke-xin, SONG Ming-zhe, WU Chang-ping, CHEN Jun, WANG Zhi-qiang, HOU Jin-bing, LIU Hai-long

201110051774.3 Invention


WEI Ke-xin, SONG Ming-zhe, WU Chang-ping, CHEN Jun, WANG Zhi-qiang, HOU Jin-bing, LIU Hai-long


62 A transmission ionization chamber used for on-line monitoring for proton beams above 15 MeV

CHEN Yi-zhen, LIN Ming, YE Hong-sheng, CHEN Ke-sheng, XU Li-jun, XIA Wen


63 A cryotrap device for irradiation Kr-Xe separation

XU Li-jun, YE Hong-sheng, CHEN Ke-sheng, LIN Ming, CHENG Yun-dong, XIA Wen


64 A digital and smart cable laying system

ZHANG Xi-mei, ZHENG Yu-lai, LIU Jian, DUAN Tian-ying, LV Jian-you, YANG Hong-yi, LIN Jian-ru

201110051762.0 Invention


65 A cleaning device for spent fuel assembly of fast reactor

LU Xiao-chun, YANG Zhong- min

201110057048.2 Invention


LU Xiao-chun, YANG Zhong- min


67 A control technology for using large torque angle step motor for power adjustment of reactors

LIU Gui-juan, QIAO Feng, GUO Wen-qi, LIU Guo-fa, DUAN Tian-ying

201110057032.1 Invention

68 A full-automatic refueling control method for sodium-cooled fast reactor and its control system

DONG Sheng-guo, ZHU Hao, MA Hong-sheng, ZHAO Li-xia, TANG Ji-ben, DUAN Tian-ying

201110060029.5 Invention

69 A full-automatic refueling control system for sodium-cooled fast reactor



70 A signal conversion device and method for inspection assembly type sensor used in the refueling of sodium-cooled fast reactor

DONG Sheng-guo, ZHU Hao, TANG Ji-ben, MA Hong-sheng, ZHAO Li-xia

201110060030.8 Invention

71 A signal conversion device for inspection assembly type sensor used in the refueling of sodium-cooled fast reactor



72 A location sensor device and its signal conversion method for the refueling of sodium-cooled fast reactor


201110060033.1 Invention

73 A location sensor device and its signal conversion method for




the refueling of sodium-cooled fast reactor

74 A calculating method for power adjustment of fast reactors

LIU Gui-juan, QIAO Feng, GUO Wen-qi, LIU Guo-fa, DUAN Tian-ying

201110060034.6 Invention

75 A sealed magnetic resistance electric motor

JIN Yue-qin, WANG Ming- zheng, ZHANG Dong-hui, YANG Kong-li, SUN Gang, JIN Feng-lei, WANG Xue-e

201110129854.6 Invention


JIN Yue-qin, WANG Ming- zheng, ZHANG Dong-hui, YANG Kong-li, SUN Gang, JIN Feng-lei, WANG Xue-e


77 A magnetic clutch JIN Yue-qin, WANG Ming- zheng, ZHANG Dong-hui, YANG Kong-li, SUN Gang, JIN Feng-lei, WANG Xue-e

201110129867.3 Invention

78 A magnetic clutch JIN Yue-qin, WANG Ming- zheng, ZHANG Dong-hui, YANG Kong-li, SUN Gang, JIN Feng-lei, WANG Xue-e


79 A digital physical experiment system for reactors

AFAN Zhen-dong, CHEN Xiao-liang, ZHAO Yu-sen, YANG Yong, HU Bin, ZHAO Jin-kun


80 An irradiation experiment method using activation in sodium-cooled fast reactor

YU Hong, CHEN Xiao-liang, HU Ding-sheng, FAN Zhen-dong, ZHAO Yu-sen, YANG Yong, WANG Shi-xi

201110376907.4 Invention

81 A measurement method for the value of void reactivity in sodium-cooled fast reactor

YU Hong, ZHOU Ke-yuan, HU Bin, YANG Xiao-yan, GANG Zhi, CHEN Yi-yu

201110380025.5 Invention

82 A dead time correction method for the measured reactivity value in reactors

HU Bin, XU Li, ZHAO Yu-sen, YANG Xiao-yan, ZHANG Jian, CHEN Yi-yu


83 An outer source correction method the measured reactivity value in reactors

HU Bin, ZHANG Jian, ZHAO Yu-sen, ZHOU Ke-yuan, YANG Xiao-yan, XU Li

201110381344.8 Invention


84 A preparation method for 18F-FET

ZHANG Jin-ming, HUANG Wei, TIAN Jia-he, ZHANG Xiao-jun

201110195309.7 Invention

85 A primary neutron source component used for the start of nuclear reactors

CUI Hai-ping, WANG You-mei, YANG Rui-jin, CHEN Hong-tao, HE Shun-rao, WANG Xiao-jing, DUAN Li-min, ZHANG Chun- bao, XUE Quan-yi, GONG Lin-ling, YANG Xin, LI Xin

201110179415.6 Invention

86 A primary neutron source component used for the start of nuclear reactors

CUI Hai-ping, WANG You-mei, YANG Rui-jin, CHEN Hong-tao, HE Shun-rao, WANG Xiao-jing, DUAN Li-min, ZHANG Chun- bao, XUE Quan-yi, GONG Lin-ling, YANG Xin, LI Xin


87 A freeze-drying technique applied in L-BPA

LUO ZHi-fu, HUANG Wei, LI Fen-lin, TANG Zhi-gang, HAN Shi-quan, ZHANG Xian-zhong, ZHAO Zha-quan

201110358171.8 Invention

88 A diagnosis device for heavy ion beams for single event experiment and its relevant measurement method

SHEN Dong-jun, GUO Gang, CHEN Quan, LIU Jian-cheng, SHEN Shu-ting, HUI Ning, WANG Hui

201110051763.5 Invention

89 A diagnosis device for heavy ion beams for single event experiment

SHEN Dong-jun, GUO Gang, CHEN Quan, LIU Jian-cheng, SHEN Shu-ting, HUI Ning, WANG Hui

201120054734.X Utility model

90 A beam shutter for single event effects ground accelerator simulation experiment

SHEN Shu-ting, GUO Gang, LIU Jian-cheng, HUI Ning, SHEN Dong-jun

201110057061.8 Invention

91 A beam shutter for single event effects ground accelerator simulation experiment

SHEN Shu-ting, GUO Gang, LIU Jian-cheng, HUI Ning, SHEN Dong-jun


92 A laser positioning device with CCD calibration and its method

GUO Gang, SHEN Shu-ting, CHEN Quan, SHEN Dong-jun, HUI Ning, LIU Jian-cheng

201110057063.7 Invention

93 A laser positioning device with CCD calibration


201120061190.x Utility model

94 A method using HUI Ning, GUO Gang, SHEN 201110057034.0 Invention


nuclear pore membrane to determine the beam distribution in radiation channel for single event effects

Dong-jun, GAO Li-juan, SHEN Shu-ting, WANG Hui

95 A preparation method for nanometre zinc oxide line

NI Bang-fa, LIU Cun-xiong, LIU Chao

201110129855.0 Invention

96 A portable neutron detection device

WANG Yu, WANG Hong-li, HAN Song-bai, HAO Li-jie, WU Mei-mei, HE Lin-fen, WEI Guo-hai, YU Zhou-xiang, CHEN Dong-feng, LIU Yun-tao

201110179451.2 Invention

97 A portable neutron detection device

WANG Yu, WANG Hong-li, HAN Song-bai, HAO Li-jie, WU Mei-mei, HE Lin-feng, WEI Guo-hai, YU Zhou-xiang, CHEN Dong-feng, LIU Yun-tao


98 A measuring and controlling method for neutron diffraction texture and its system

LIU Xiao-long, LI Mei-juan, TIAN Geng-fang, WU Zhan-hua, HAN Song-bai, YU Zhou-xiang, HU Rui, SUN Kai, WANG Hong-li, LIU Yun-tao, CHEN Dong-feng

201110179453.1 Invention

99 A position detector for neutron beams

HE Lin-feng, HAN Song-bai, WANG Hong-li, HAO Li-jie, WU Mei-mei, WANG Yu, WEI Guo-hai, CHEN Dong-feng, LIU Yun-tao, WU Li-qi

201110179455.0 Invention

100 A position detector for neutron beams



101 A high-speed neutron imaging device


201110179473.9 Invention

102 A high-speed neutron imaging device

HE Lin-feng, HAN Song-bai, WANG Hong-li, HAO Li-jie, WU Mei-mei, WANG Yu, WEI Guo-hai, CHEN Dong-feng, LIU



Yun-tao, WU Li-qi 103 A mirror high

temperature furnace device for in situ experiment of neutron diffraction sample

GAO Jian-bo, LI Jun-hong, CHEN Dong-feng, LIU Yun-tao, WANG Hong-li, SUN Kai, XIAO Hong-wen, HAN Song-bai, LI Mei-juan, ZHANG Li, WU Zhan-hua, LI Tian-fu, JIAO Xue-sheng, LIANG Feng, YANG Hao-zhi, WANG Zi-jun, HU Rui

201110179475.8 Invention

104 A mirror high temperature furnace device for in situ experiment of neutron diffraction sample



105 An attitude adjustment device for multiaxis neutron monochromator



106 An attitude adjustment device for multiaxis neutron monochromator



107 A method using tablet machine to prepare thermal neutron scintillator convertor

WANG Yu, WANG Hong-li, HAN Song-bai, HAO Li-jie, WU Mei-mei, HE Lin-fen, WEI Guo-hai, HAN Wen-ze, CHEN Dong-feng, LIU Yun-tao

201110179535.6 Invention

108 A method using atomizer to prepare thermal neutron scintillator convertor

WANG Yu, WANG Hong-li, HAN Song-bai, HAO Li-jie, WU Mei-mei, HE Lin-fen, WEI Guo-hai, CHEN Dong-feng, LIU Yun-tao, WU Li-qi

201110179546.4 Invention

109 A method using paint WANG Yu, WANG Hong-li, 201110179553.4 Invention


film maker to prepare thermal neutron scintillator convertor

HAN Song-bai, HAO Li-jie, WU Mei-mei, HE Lin-fen, WEI Guo-hai, CHEN Dong-feng, LIU Yun-tao, WU Li-qi

110 A neutron imaging inspection device for feul rod of pressurized water reactor and inspection method

WEI Guo-hai, HAN Song-bai, HAO Li-jie, WU Mei-mei, HE Lin-fen, WANG Yu, LIU Yun-tao, WANG Hong-li, SUN Kai, WU Li-qi

201110179586.9 Invention

111 A neutron imaging inspection device for feul rod of pressurized water reactor



112 A transfer container for nuclear fuel element in non destructive testing of neutron imaging


201110179587.3 Invention

113 A transfer container for nuclear fuel element in non destructive testing of neutron imaging



114 A neutron texture test device

CHEN Dong-feng, LI Mei-juan, LIU Xiao-long, WU Zhan-hua, TIAN Geng-fang, YANG Hao-zhi, LI Jun-hong, GAO Jian-bo, JIAO Xue-sheng, LI Tian-fu, HAN Wen-zhe, XIAO Hong-wen, YU Zhou-xiang, HU Rui, SUN Kai, WANG Hong-li, LIU Yun-tao


115 A neutron texture test device

CHEN Dong-feng, LI Mei-juan, LIU Xiao-long, WU Zhan-hua, TIAN Geng-fang, YANG Hao-zhi, LI Jun-hong, GAO Jian-bo, JIAO Xue-sheng, LI Tian-fu, HAN Wen-zhe, XIAO Hong-wen, YU Zhou-xiang, HU Rui, SUN Kai, WANG Hong-li, LIU Yun-tao


116 The first collimator adjustment device for

CHEN Dong-feng, LI Mei-juan, LIU Xiao-long, WU Li-qi, WU

201110200106.2 Invention


neutron diffraction texture

Zhan-hua, TIAN Geng-fang, YANG Hao-zhi, LI Jun-hong, GAO Jian-bo, JIAO Xue-sheng, LI Tian-fu, HAN Wen-zhe, XIAO Hong-wen, YU Zhou-xiang, HU Rui, SUN Kai, WANG Hong-li, LIU Yun-tao

117 The first collimator adjustment device for neutron diffraction texture

CHEN Dong-feng, LI Mei-juan, LIU Xiao-long, WU Li-qi,WU Zhan-hua, TIAN Geng-fang, YANG Hao-zhi, LI Jun-hong, GAO Jian-bo, JIAO Xue-sheng, LI Tian-fu, HAN Wen-zhe, XIAO Hong-wen, YU Zhou-xiang, HU Rui, SUN Kai, WANG Hong-li, LIU Yun-tao


118 A stretching device for neutron absorbing layer carrier

CHEN Dong-feng, YANG Hao-zhi, WANG Yu, WU Zhan-hua, TIAN Geng-fang, WU Li-qi, LI Mei-juan, LIU Xiao-long, HAN Song-bai, SUN Kai, WANG Hong-li, LIU Yun-tao

201110200108.1 Invention

119 A stretching device for neutron absorbing layer carrier

CHEN Dong-feng, YANG Hao- zhi, WANG Yu, WU Zhan-hua, TIAN Geng-fang, WU Li-qi, LI Mei-juan, LIU Xiao-long, HAN Song-bai, SUN Kai, WANG Hong-li, LIU Yun-tao


120 Neutron collimator and neutron scattering spectrometer


201110200109.6 Invention

121 Neutron collimator and neutron scattering spectrometer



122 A method to improve the surface area of capacitor electrode

LIU Yong-hui, WU Zhen-dong, ZHOU Shu-hua, FU Yuan-yong



123 A device of measuring neutron residual stress and its method

CHEN Dong-feng, LIU Yun-tao, LI Jun-hong, LI Ji-zhou, GAO Jian-bo, HAN Song-bai, LI Tian-fu, JIAO Xue-sheng, LI Mei-juan, WANG Hong-li, SUN Kai, XIAO Hong-wen, ZU Yong, LIU Rong-deng, WU Mei-mei, YU Zhou-xiang, LIANG Feng, ZHANG Li, HU Rui, LIU Xiao-long, HAN Wen-zhe, WU Li-qi, CHENG Na, SUN Shuo

201110276888.8 Invention

124 A flight time device for measurement of cool neutron beam quality for multi-purposes

CHEN Dong-feng, LIU Yun-tao, LIANG Geng, WANG Hong-li, CHENG Jun, BAO Zong-yu, YU Zhou-xiang, SUN Kai, HAN Song-bai, Hao Li-ji, WU Mei-mei, JIAO Xue-sheng, ZHANG Li, GAO Jian-bo, LI Tian-fu, WU Li-qi

201110332619.9 Invention

125 A method of preparing black silver nanoparticles using nuclear track porous surface

LIU Cun-xiong, NI Bang-fa, HU Lian

201110332644.7 Invention

126 A neutron callibration system of Cockcroft-Walton accelerator

BAO Jie, XIN Biao, RUAN Xi-chao, ZHOU Zu-ying, TANG Hong-qing, NIE Yang-bo

201110358167.1 Invention

127 A nuclear track filter for liquid medicine production

ZHANG Bao-tiang, SU Sheng- yong, YANG Bao-jun


128 Locater LIU Hai-jun, YANG Li-jun, ZHANG Chao, ZHANG Zhu-guang, ZHANG Xiao-hua, ZHANG Xiao-yong


Note: National defence patent isn’t included


CIAE Patent in 2011

Serial number

Apply item Assignee Application No.Patent date

Style

1 Siphon breaker devices

YANG Fu-chang, DING Zhen-xin, ZHANG Dong- hui, SUN Gang

200710087008.6 2011.01.12 Invention

2 A method and device for directly dissolve sodium samples in distilled water

XIE Chun, JIA Yun-teng 200710151355.0 2011.03.16 Invention

3 Argon distribution system of sodium cooled fast reactor

TANG Chao-hui, DONG Bi-bo, MA Bing-zeng

200710195020.9 2011.09.14 Invention

4 Boron carbide shielding component

ZHANG Ru-xian 200710195022.8 2011.07.20 Invention

5 Sodium-sodium heat exchanger

JIANG Ting-san, LIU Lian-ping, YE Yuan-wu, TANG Long, LIU Jia-yi

200710195023.2 2011.03.09 Invention

6 Radioactive sodium in-line purified cold trap

ZHOU Yu-ying, DONG Bi-bo, LIU Bao-quan, LI Jing

200710198421.x 2011.07.20 Invention

7 An overpressure protection device for pool-type sodium- cooled fast reactor

CHEN Gui-zhen, CAO Kang, WANG Bing, ZHOU Li-jun, PEI Zhi-yong, LIU Bao-quan, LI Wen-hong

200710198422.4 2011.01.12 Invention

8 Method of disassem- bling pipes filled with liquid sodium- potassium alloy

DU Hai-ou 200710198424.3 2011.06.01 Invention

9 A method of NaK charging and device

DU Hai-ou, HONG Shun-zhang

200710306973.8 2011.07.20 Invention

10 The automated fast transfer assembly by gas driven

ZHU Qing-fu, CAO Jian, ZHAO Shou-zhi, LUO Huang-da, ZHANG Wei, SHI Yong-qian, WANG Zuo-qing,

200810135229.0 2011.11.02 Invention

APPENDIX·CIAE Patent in 2011 235

ZHANG Jin-shan, HUANG Xin-rong, LI Song

11 The seismic response analysis method for reactor main vessel

WEN Jing, LI Hai-long, YU Hua-jin, SONG Qing, RUAN Lin, BAO Yang-min

200810135231.8 2011.09.14 Invention

12 The Extinguishants for Sodium Fire

DU Hai-ou, SHEN Feng- yang, HONG Shun-zhang

200810135232.2 2011.08.24 Invention

13 The drive device of neutron check source

LIU Yu-pu, LIU Hao-jie 200810135234.1 2011.08.24 Invention

14 The neutron shielding device on reactor vault of sodium cooled pool type fast reactor

LU Zhao-fu, XU Bao-yu, ZHAO Ru-cai, BAO Yang-min, JIN Yue-qing, WANG Ming-zheng, FANG Bang-cheng, XU Yi-jun

200810135236.0 2011.08.24 Invention

15 Simulated fuel sub- assembly for sodium-cooled fast reactor

WANG Xiao-rong, XIE Guang-shan, ZHANG Ru-xian, YANG Fu-chang, QIAN Shun-fa, XU Mi

200810135238.x 2011.07.20 Invention

16 A throttle device in cooling system of supporting structure of primary pump

FENG Yu-heng, YANG Hong-yi, YOU Ji-kun, SUN Gang, BAO Yang-min

200810135242.6 2011.08.24 Invention

17 An opening device to the seal cask of the burst assembly of sodium cooled pool type fast reactor

WANG Chang-ling, GU Ji-pin, LU Yun-biao, JIN Yue-qing, XIAO Xun-ze, TIAN Chuan-jiu, BAO Yang-min

200810135245.x 2011.09.14 Invention

18 A welding process of thin hexagonal tube

WANG Xiao-rong, XIE Guang-shan, ZHANG Ru- xian, DUAN Hai-yan, QIAN Shun-fa

200810135249.8 2011.01.12 Invention

19 A installation device for fixing the sodium height meter in sodium cooled fast reactor

SUN Gang, YOU Ji-kun, BAO Yang-min, JIN Yue-qing, XIAO Xun-ze, TIAN Chuan-jiu

200810135250.0 2011.06.15 Invention

20 X-ray fluorescence analysis equipment

ZHEN Wei-ming, HUANG Qing-liang, SONG You, WU Ji-zong,

200910119502.5 2011.03.16 Invention


LIU Gui-jiao 21 A explosive detec-

tion equipment for mails

HE Gao-kui, WAN Yu-qing, TIAN Hua-yang, JIN Yu-heng

200910119504.4 2011.11.02 Invention

22 A surveillance device for irradiation of the core vessels of high flux research reactors

XU Yuan-chao, SHI Chen-lei, NING Guang- sheng

200910119506.3 2011.06.01 Invention

23 A new type of walk-through metal and radioactive materials detector

WANG Qiang, WANG Guo-bao, LI Xue-quan, GAO Qi, LIU Zhi-ying, GUO Feng-mei, YAN Jing-ru

200910119584.3 2011.08.24 Invention

24 Taking and releasing tools of sleeve of spent fuel trans- porting machine in a oblique position

GU Ji-ping, WANG Chang-ling, WANG Ming-zheng, LU Yun- biao, SUN Lin-zhi, WU Fang, YANG Kong-li, SUN Gang, JIN Feng-lei, LI Hai, YU Tuan-jie

200910130944.x 2011.03.09 Invention

25 Method to Set Up the design transient for the coolant system and component of sodium coolant fast reactor NPP

YANG Hong-yi 200910130945.4 2011.08.24 Invention

26 A portable sampling device of under-water sediment

YAO Cheng-zhi, FENG Jia-min, ZHANG Jin-shan, JIA Zi-yu, HUANG Xing-rong, ZHUANG Yi, YI Da-yong, DAI Shou-tong

200910130946.9 2011.07.20 Invention

27 Age determination of trace plutonium

CHEN Yan, CHANG Zhi-yuan, ZHAO Yong- gang, ZHANG Ji-long

200910142192.9 2011.03.16 Invention

28 A method of determining the two-phase interfacial area of the mixing oil-water

LI Chuan-bo, ZHENG Wei-fang, ZHANG Yu, YAN Tai-hong, BIAN Xiao-yan, ZUO Chen, ZHANG Bo-qing, ZHANG Jin-zhu, ZHOU Yi-ping

200910142193.3 2011.12.07 Invention

29 A method with the LI Chuan-bo, ZHENG 200910142194.8 2011.05.11 Invention


attachment of sampling the organic phase from the oil-water

Wei-fang, ZHANG Yu, YAN Tai-hong, ZUO Chen, ZHANG Bo-qing, BIAN Xiao-yan, ZHANG Jin-zhu, ZHOU Yi-ping

30 A sort of underwater cutter

FAN Yue-rong, ZHANG Jin-shan, HAN Hai-fen, YI Da-yong, ZHUANG Yi, FENG Jia-min, YAO Cheng-zhi

200910142196.7 2011.09.14 Invention

31 A sort of underwater electric clutch

ZHANG Jin-shan, HAN Hai-fen, FAN Yue-rong, YI Da-yong

200910142197.1 2011.09.14 Invention

32 A sort of steering gear for twisting the neutron source tube

HAN Hai-fen, LIN Sheng- huo, ZHANG Jin-shan, RONG Chun-fang, FAN Yue-rong, LIANG Shu-hong

200910142198.6 2011.09.14 Invention

33 A sealing thingamy between motor and other parts

ZHANG Jinshan, HAN Hai-fen, FAN Yue-rong, YI Da-yong

200910142199.0 2011.12.07 Invention

34 A device for sampling small volume solution in hot cell

WU Ji-zong, ZHANG Li-hua, LIU Huan-liang, MU Ling, QIAN Hong-juan, FAN De-jun, WANG Nan-jie

200910147720.x 2011.08.24 Invention

35 The vacuum suction-impaction collector for particles

WANG Tong-xing, LI Jing- huai, ZHANG Yan, ZHAO Yong-gang, CHANG Zhi- yuan, LI Shao-wei, WANG Fan, LI Li-li, SHEN Yan

200910170060.7 2011.01.26 Invention

36 Asymmetric shimming bar method for enhancing vertical focusing in isochronous cyclotron

ZHANG Tian-jue, WANG Chuan, ZHONG Jun-qing, YAO Hong-juan

200910211156.3 2011.12.07 Invention

37 Transportation systems for inspected target

XU Xiao-ming, ZHU Li-qun, JIA Xiang-jun, MENG Yan-tai, WANG Xiao-zhong, GAN Lin, BAI Lei, SHEN Ning, MENG Lei, ZHANG

201010000589.7 2011.11.02 Invention


Quan-bao 38 A hot cell

sampling device JIAO Hai-yang, WEI Yan, WANG Hui, ZHENG Wei-fang

201010120192.1 2011.11.02 Invention

39 Operating manipulators in remote tracks

YANG Kong-li, YU Tuan-jie, WANG Chang- ling, LIU Zhao-yang, SUN Gang, LI Hai, JIN Feng-lei

201010123837.7 2011.11.02 Invention

40 A preparation method for sealed source of 103Pd

GAO Hui-bo, LI Zhong- yong, WANG Wei, DENG Xue-song, ZHANG Wen- hui, HAN Lian-ge, JIN Xiao-hai

201010212968.2 2011.12.07 Invention

41 Neutron detecting device for nuclear wastes in barrels

ZHU Li-qun, GAN Lin, XU Xiao-ming, JIA Xiang-jun, MENG Yan-tai, WANG Xiao-zhong, GU Shao-gang, BAI Lei, SHEN Ning

201020001146.5 2011.03.16 Utility model

42 Fixing component for photomultiplier of plastic scintillation detectors

ZHAO Rong-sheng, ZHAO Shi- wu, ZHANG Wen-liang, LI Xin-jun, ZONG Bo, FANG Xin, ZHANG Li-ping, GAN Lin

201020106702.5 2011.03.02 Utility model

43 Full sealing high-temperature sodium testing vessel

XU Yong-li, LONG Bin, ZHANG Dao-de, ZHANG Jin-quan

201020126013.0 2011.03.02 Utility model

44 Connecting device for main container and sodium filling and discharging pipeline systems of fast neutron reactors

SUN Gang, WANG Ming-zheng, JIN Yue-qing, LIU Zhao-yang, XIAO Xun-ze, LI Hai

201020126017.9 2011.03.02 Utility model

45 Refrigeration equipment for feeding pumps

DI Ying, LI Chun-yi, CHANG Shang-wen, JIAO Hai-yang

201020260135.9 2011.01.19 Utility model

46 Floor drain monitoring device

WANG Qiang, ZAN Huai-qi, LI Chuan-xia, LI Hua

201020260162.6 2011.01.19 Utility model

47 Burnup measure- LI Jian-hua, LIU 201020270740.4 2011.01.26 Utility


ment system for spent fuel assemblies

Hong-bin, ZHAO Yong-gang, JIN Hui-min, ZHU Liu-chao, CHEN Yan

model

48 A connecting and supporting structure for double-layer containers

BAO Yang-min, YOU Ji-kun, SUN Gang, JIN Yue-qing, XIAO Xun-ze, WANG Ming-zheng, YANG Kong-li

201020270737.2 2011.03.02 Utility model

49 Metal thermal insulation layers for reactor container of sodium-cooled fast neutron reactors

SUN Gang, BAO Yang-min, YOU Ji-kun, XING Feng-chun, YING Qing- fang, JIN Yue-qing, XIAO Xun-ze, WANG Ming-zheng, YANG Kong-li

201020270731.5 2011.03.02 Utility model

50 Reactor screw anti- loosing structure

SUN Gang, BAO Yang-min, JIN Yue-qing, YOU Ji-kun

201020270721.1 2011.01.26 Utility model

51 Gas-Lift pump sampling device for fuel dilapidation detecting in fast neutron reactors

LIU Yu-pu, WANG Lin, LIU Hao-jie

201020270716.0 2011.01.26 Utility model

52 An anemometer for measuring the wind velocity in the axial direction of pipelines

JING Li-gang, LIU Guo-min

201020270698.6 2011.01.26 Utility model

53 Miniature mixer- settler with high flow ratio

CHANG Shang-wen, LIU Li-sheng, GUO Jian-hua, CHANG Li, WANG Chang-shui, LI Rui-xue, WANG Xiao-rong, LI Wei-min, OUYANG Ying-gen

201020270744.2 2011.03.02 Utility model

54 Locking structure of bolt and nut

FAN Yue-rong, ZHANG Zhan-li, SHI Chen-lei, LANG Rui-feng, DAI Chang-nian, HUANG Dao-li, SUN Lin-zhi

201020529997.7 2011.03.16 Utility model

55 Decay tank ZHANG Zhan-li, FAN Yue-rong, SHI Chen-lei

201020529996.2 2011.11.02 Utility model


56 Radiation imaging system based on photoluminescence imaging plate with radiation memory function

MA Ji-zeng, LUO Zhi-ping, WANG Ying

201020529979.9 2011.04.27 Utility model

57 Radiation imaging system based on radiation-photoluminescence imaging plate with radiation memory function

MA Ji-zeng, LUO Zhi-ping, WANG Ying

201020529980.1 2011.08.03 Utility model

58 Detecting device for conductive liquid

LI Song, ZAN Huai-qi, LI Hua, WANG Qiang, LI Chuan-xia

201020591474.5 2011.05.18 Utility model

59 Device for liquid level measurement for reactor pool

LI Hua, LI Chuan-xia, ZAN Huai-qi, WANG Qiang

201020591452.9 2011.06.01 Utility model

60 Diversion box SHI Chen-lei, FAN Yue-rong, ZHANG Zhan-li, SUN Lin-zhi, LANG Rui-feng

201020591463.7 2011.08.24 Utility model

61 Heavy water tank SHI Chen-lei, FAN Yue-rong, ZHANG Zhan-li, SUN Lin-zhi, LANG Rui-feng

201020591428.5 2011.06.15 Utility model

62 A liquid metal flow meter based on correlation method

CHEN Dao-long, LIU Yun-yan, LI Xing, DUAN Tian-ying, LI Kang-ning, LV Peng, YANG Jian-wei, LI Xin-ying

201020592931.2 2011.08.24 Utility model

63 Flat nuclear fuel assemblies

KANG Ya-lun, ZHANG Ai-min

201020593161.3 2011.08.24 Utility model

64 Locating and connecting structure of follower units and absorber units

KANG Ya-lun, ZHANG Ai-min, CHEN Li-xia

201020593164.7 2011.06.15 Utility model

65 Fixing installations for reactor controlling rod guide

CHEN Li-xia, ZHANG Ying-chao, GAO Yong- guang

201020593166.6 2011.06.15 Utility model

66 Equipments for WANG Zhong-qi, GAN 201020696160.1 2011.09.14 Utility


liquid nitrogen filling

Lin model

67 A locating and measuring bracket used for high purity germanium detector

WANG Zhong-qi, GAN Lin, LU Wen-guang

201020696167.3 2011.07.20 Utility model

68 A type of fuel assembly under water turnover mechanism

YI Da-yong, ZHANG Jin-shan, HUANG Xing- rong, ZHUANG Yi, YAO Cheng-zhi

201020696177.7 2011.08.03 Utility model

69 A type of fuel assembly under water gripping apparatus

YI Da-yong, ZHANG Jin-shan, HUANG Xing- rong, ZHUANG Yi, YAO Cheng-zhi

201020696184.7 2011.08.31 Utility model

70 An associated α particle detector used for sealed neutron source

LI Jing-huai, WU Sui-jun, LIANG Qing-lei, LIU Guo-rong, LI An-li, ZHAO Yong-gang

201020696228.6 2011.09.14 Utility model

71 A new electrode structure of static-electricity spiral deflecting plate

YANG Jian-jun, ZHANG Tian-jue, JIA Xian-lu

201020696145.7 2011.08.03 Utility model

72 Metal-sealed high- vacuum gate valve

HAN Guang-wen, HUANG Jun, YIN Meng, CUI Zong-wei

201020700161.9 2011.08.03 Utility model

73 Fixing components for main magnet of ion source

JIA Xian-lu, ZHANG Tian-jue, LV Yin-long

201020700150.0 2011.09.07 Utility model

74 Magnet structure for producing virtual filtering magnetic field

JIA Xian-lu, ZHANG Tian-jue, LV Yin-long

201020700147.9 2011.12.07 Utility model

75 A switching device for step motor driving used in the power adjustment system of reactors


201120048040.5 2011.09.14 Utility model


LV Xue-sheng, JIN Hun-min, ZHAO Rong- gang, LIU Guo-rong, LI Jin-huai

201120054731.6 2011.12.07 Utility model



WEI Ke-xin, SONG Ming-zhe, WU Chang-ping, CHEN Jun, WANG ZHi-qiang, HOU Jin-bing, LIU Hai-long

201120054750.9 2011.12.07 Utility model

78 A transmission ionization chamber used for on-line monitoring for proton beams above 15 MeV

Chen Yi-zhen, LIN Ming, YE Hong-sheng, CHEN Ke-sheng, XU Li-jun, XIA Wen

201120054720.8 2011.09.14 Utility model


LU Xiao-chun, YANG Zhong-min

201120061209.0 2011.11.02 Utility model

80 A laser positioning device with CCD calibration


201120061190.x 2011.09.14 Utility model

81 MHz ns pulsed beam production device

AN Shi-zhong, YIN Zhi-guo, SONG Guo-fang, LI Peng-zhan, LIU Geng-shou

201120061174.0 2011.08.24 Utility model

82 Measurement device for MHz ns pulsed beam

AN Shi-zhong, XIE Huai-dong, GUAN Feng- ping, YING Zhi-guo

201120061187.8 2011.11.02 Utility model

83 A full-automatic refueling control system for sodium- cooled fast reactor


201120064687.7 2011.11.02 Utility model

84 A signal conversion device for inspection assembly type sensor used in the refueling of sodium- cooled fast reactor


201120064685.8 2011.09.14 Utility model

85 A location sensor device and its signal conversion method for the refueling of sodium-cooled fast


201120064682.4 2011.09.14 Utility model


reactor 86 Reactor control rod

structure of frame style


201120064675.4 2011.09.14 Utility model

87 Locater LIU Hai-jun, YANG Li-jun, ZHANG Chao, ZHANG Zhu-guang, ZHANG Xiao-hua, ZHANG Xiao-yong

201120093184.2 2011.11.09 Utility model

88 An integration glove box system for precise measurement of Pu content

LIU Quan-wei, LUO Zhong-yan, ZHU Hai-qiao, LIANG Jing, WU Ji-zhong

201120114759.4 2011.12.07 Utility model


JIN Yue-qin, WANG Ming-zheng, ZHANG Dong-hui, YANG Kong-li, SUN Gang, JIN Feng-lei, WANG Xue-e

201120160187.3 2011.11.02 Utility model

90 A magnetic clutch JIN Yue-qin, WANG Ming-zheng, ZHANG Dong-hui, YANG Kong-li, SUN Gang, JIN Feng-lei, WANG Xue-e

201120160186.9 2011.12.07 Utility model

Note: National defence patent isn’t included


List of Scientific Publication in Foreign Languages in 2011

1 Metrologia, Vol. 48, 2011 1) International key comparison of measurements of neutron source emission rate (1999–2005): CCRI(III)-K9. AmBe, technical supplement, 06018. Roberts N J (National Physical Laboratory), WANG Z, LIU Y, WANG Q, CHEN X, LUO H, RONG C, et al.

2 Advanced Materials Research, 2011 1) The optimization of material thickness for neutron shielding with Monte Carlo method, Vol. 124, p. 166. CHEN C, WANG M 2) Simulation of radiation damage for the typical tritium permeation barrier coating materials, Vol. 308-310, p. 1 226-1 229.

ZHU B(State Key Laboratory of Material Processing and Die and Mould Technology, Huazhong University of Science and Technology), ZHANG Y S, HU J G, YANG H G, ZHAN Q

3 Annuals of Nuclear Energy, Vol. 38, 2011

1) Model calculation of neutron kerma coefficient for n+56Fe below 20 MeV, No. 2-3, p. 455. SUN Xiao-jun(Guangxi Normal Univ, Coll Phys & Technol), et al., DUAN Jun-feng, ZHANG Jing-shang 2) Calculation and evaluations for n+63,65,nat.Cu reactions, No. 9, p. 1 852. HAN Yin-lu, XU Yong-li, LIANG Hai-ying, GUO Hai-rui, SHEN Qing-biao 3) Double differential cross sections of n+63,65,nat.Cu reactions, No. 9, p. 1 950. HAN Yin-lu, XU Yong-li, LIANG Hai-ying, GUO Hai-rui, SHEN Qing-biao

4 Applied Physics Letters, Vol. 99, 2011 1) Anisotropic nanocrystalline MnBi with high coercivity at high temperature, No. 8, 082505. YANG J B( Peking Univ, Sch Phys, State Key Lab Mesoscop Phys), et al., WU M M, CHEN D F

5 Applied Radiation and Isotopes, 2011 1) Study on bubble detectors used as personal neutron dosimeters, Vol. 69, No. 10, p. 1 453. ZHANG Gui-ying, NI Bang-fa, LI Li, LV Peng, TIAN Wei-zhi, WANG Zhi-qiang, ZHANG Chun-bao, LUO Hai-long, JIANG Shun-li, WANG Ping-sheng, HUANG Dong-hui, LIU Cun-xiong, XIAO Cai-jin

6 Computational Materials Science, Vol. 50, 2011 1) Effect of Cr precipitates and He bubbles on the strength of ⟨110⟩ tilt grain boundaries in BCC Fe: An atomistic study, No. 3, p. 925. TERENTYEV D(CEN SCK, Struct Mat Grp, Nucl Mat Sci Inst), HE X

7 Energy Conversion and Management, Vol. 52, 2011 1) Gallium Nitride Schottky betavoltaic nuclear batteries, No. 4, p. 1 955. LU Min(CAS, Su Zhou Inst Nanotechnol & Nanobion), ZHANG, Guo-guang, SU Dan, HU Ji-feng

APPENDIX·List of Scientific Publication in Foreign Languages in 2011 245

8 Progress in Chemistry, Vol. 23, 2011 1) Some thinking of nuclear fuel reprocessing/recycling in China, No. 7, p. 1 263. GU Zhong-mao, et al. 2) A review on the development of spent nuclear fuel reprocessing and its related radiochemistry, No. 7, p. 1 289. YE Guo-an, ZHANG Hu

9 Electrochemistry Communications, Vol. 13, 2011 1) Production of iron and oxygen in molten K2CO3-Na2CO3 by electrochemically splitting Fe2O3 using a cost affordable inert anode, No. 12, p. 1 521. YIN Hua-yi(Wuhan Univ, Sch Resources & Environm Sci), et al., ZHANG Yu

10 European Physical Journal A, Vol. 47, 2011 1) Sub-barrier capture with quantum diffusion approach: Actinide-based reactions, No. 3. SARGSYAN V V(Joint Inst Nucl Res), et al., ZHANG H Q 2) Sub-barrier capture with quantum diffusion approach: Actinide-based reactions, No. 3, p. 38. SARGSYAN V V( Joint Inst Nucl Res), et al., ZHANG H Q 3) Study of proton resonances in 18Ne via resonant elastic scattering of 17F+p and its astrophysical implication in the stellar reaction of 14O(alpha, p)17F, No. 5, p. 1. HE J J( Chinese Acad Sci CAS, Inst Modern Phys), et al., SU J, LI E T 4) Level structures in the 114In nucleus, No. 11, p. 141. LI C B, ZHENG Y, WU X G, HE C Y, LI G S, YAO S H, YU B B, CAO X P, HU S P, WANG J L

11 European Physical Journal C, Vol. 71, 2011 1) Strange particle production in proton-proton collisions at root s=0.9 TeV with ALICE at the LHC, No. 3, p. 1 594. AAMODT K( Univ Bergen, Dept Phys & Technol), et al., LI X 2) Production of pions, kaons and protons in pp collisions at root s=900 GeV with ALICE at the LHC, No. 6, p. 1 655. AAMODT K( Univ Oslo, Dept Phys), et al, Hu S, LI X, LI Y, LU S, WEN Q, ZHOU S

12 European Physical Journal Plus, Vol. 126, 2011 1) Transverse spin structure of the nucleon through target single-spin asymmetry in semi-inclusive deep-inelastic (e, e'pi+/-) reaction at Jefferson Lab, No. 1, p. 2. GAO H( Duke Univ), et al., LI X M

13 EPJ Web of Conferences, Vol. 17, 2011 1) Quasifission and fusion-fission competition in 32S+184W reaction, 04002. ZHANG H Q, ZHANG C L, LIN C J, LIU Z H, YANG F 2) Nuclear reactions studied by quasi-elastic measurements with high precision at backward angles, 05005. LIN C J, JIA H M, ZHANG H Q, YANG F, XU X X, LIU Z H, ZHANG S T

14 Fusion Science and Technology, Vol. 60, 2011 1) The pack-cementation process of iron-aluminide coating on china low activation martensitic and 316L


austenitic stainless steel, No. 3, p. 1 065. YUAN X M, YANG H G, ZHAO W W, ZHAN Q, HU Y, Team T. M. T. 2) Study on the hydrogen isotope permeation behaviors of the FeAl/Al2O3 composite coating, No. 4, p. 1 531. HU Y, YANG H G, ZHAO W W, ZHAN Q, YUAN X M

15 Health Physics, Vol. 100, 2011 1) Preliminary study on application of neutron bubble detectors as personal neutron dosimeters in nuclear well logging, No .2, p. S30. ZHANG Gui-ying, ZHANG Hai-qing, NI Bang-fa, TIAN Wei-zhi, WANG Ping-sheng, HUANG Dong-hui, LIU Cun-xiong, XIAO Cai-jin, ZHAO Chang-jun

16 International Journal of Modern Physics E, Vol. 20, 2011 1) Alpha decay half-lives of exotic nuclei around shell closures, No. 1, p. 127. WANG Y Z, DONG J M, PENG B B 2) Chirality in the mass 80 region: 79Kr, No. 2, p. 520. KOIKE T(Tohoku Univ, Dept Phys), et al, FU Y Y 3) Configuration assignment of the positive-parity structures in 108Ag, No. 11, p. 2 351. LIU C(Shandong Univ Weihai, Sch Space Sci & Phys, Shandong Provincial Key Lab Opt Astron), et al., ZHU L H, WU X G, LI G S, HE C Y, ZHENG Y, WANG L L, ZHANG B

17 Journal of Chromatography A, Vol. 1218, 2011 1) A method of calculating the second dimension retention index in comprehensive two-dimensional gas chromatography time-of-flight mass spectrometry, No. 18, p. 2 577. ZHAO Ya-ping

18 Journal of Chromatographic Science, Vol. 49, 2011 1) Preparation and characterization of an immunoaffinity column for the selective extraction of salbutamol from pork sample, No. 7, p. 276. WANG Guo-min(Chongqing Univ, Coll Bioengn, Minist Educ, Key Lab Biorheol Sci & Technol), et al., WU Ji-zong

19 Journal of Crystal Growth, Vol. 329, 2011 1) Deposition temperature effects on tungsten single-crystal layer by chemical vapor transport, No. 1, p. 62. LV Yan-wei(Beijing Inst Technol, Sch Mat Sci & Engn), et al., ZHENG Jian-ping

20 Journal of the Korean Physical Society, Vol. 59, 2011 1) Theoretical method to set up double-differential cross section files of light nuclei, No. 2, p. 843. ZHANG Jing-shang, HAN Yin-lu, DUAN Jun-feng 2) The theoretical calculation of cross section and spectrum for n+238U reaction up to 150 MeV, No. 2, p. 855. HAN Yin-lu, XU Yong-li, LIANG Hai-ying, GUO Hai-rui, SHEN Qing-biao 3) Microscopic optical model potential of isospin dependent nucleon, deuteron, and helium-3, No. 2, p. 859. HAN Yin-lu, GUO Hai-rui, SHEN Qing-biao 4) System of covariance data evaluation at china nuclear data centre-COVAC, No. 2, p. 883. XU R R, LIU T J, ZHANG J S, SUN Z J


5) Theoretical analysis of neutron double-differential cross sections of n+9Be reactions, No. 2, p. 999. DUAN J F, ZHANG J S, WU H C 6) The updated version of chinese evaluated nuclear data library (CENDL-3.1), No. 2, p. 1 052. GE Z G, ZHAO Z X, XIA H H, ZHUANG Y X, LIU T J, ZHANG J S, WU H C 7) Progress of China nuclear data evaluation, No. 2, p. 1 063. ZHAO Zhi-xiang, GE Zhi-gang 8) Present status of evaluated nuclear data library for accelerator-driven systems in China, No. 2, p. 1 069. HAN Yin-lu, SHEN Qing-biao 9) Nuclide guide and international chart of the nuclides-2009, No. 2, p. 1 104. GOLASHVILI T (Joint Stock Co Energy & Ind Analyt), et al., ZHAO Zhi-xiang, HUANG Xiao-long, GE Zhi-gang, WU Zhen-dong 10) Benchmark testing of CENDL-3.1, No. 2, p. 1 146. WU H C, ZHANG H, ZHANG H Y 11) Benchmarking CENDL-3.1 with critical benchmarks, No. 2, p. 1 150. ZHANG Hua, WU Hai-cheng 12) Integral test of CENDL-3.1 with shielding benchmarks, No. 2, p. 1 166. ZHANG H Y, WU H C 13) Semi-empirical study on the yield energy-dependence of the 235U+n fission, No. 2, p. 1 353. SHU N C, CHEN Y J, LIU T J, SUN Z J, WU X Z, QIAN J, XU R R 14) Present status of evaluated nuclear data library for accelerator-driven systems in China new IAEA actinide decay data library, No. 2, p. 1 455. KELLETT M A( IAEA, Nucl Data Sect, Vienna Int Ctr), et al., HUANG Xiao-long 15) Consistency of existing decay data bases, No. 2, p. 1 495. CHECHEV V(VG Khlopin Radium Inst, Radionuclide Data Ctr), et al., HUANG Xiao-long, GE Zhi-gang, WU Zhen-dong 16) Total cross-section measurements of 169Tm below 1 00 eV, No. 2, p. 1 681. WANG W M, et al. 17) Measurement of the secondary neutron emission differential and double-differential cross sections between 20 and 30 MeV, No. 2, p. 1 729. RUAN X C, CHEN G C, HUANG H X, LI X, NIE Y B, ZHOU B, MA Z Y, BAO J, ZHONG Q P, ZHOU Z Y, TANG, H Q, ZHANG J S 18) Elastic and inelastic neutron scattering cross sections for natPb, 209Bi and natTa in the energy range from 2 MeV to 4 MeV, No. 2, p. 1 876. POENITZ E (Phys Tech Bundesanstal), et al., CHEN Guo-chang

21 Journal of Materials Research, Vol. 26, 2011 1) Helium nanobubble release from Pd surface: An atomic simulation, No. 3, p. 416. WANG Liang(Hunan Univ, Dept Appl Phys), et al., HU Shi-lin

22 Journal of Materials Science, Vol. 46, 2011 1) Crystal structure and negative thermal expansion of solid solution Y2W3－xMoxO12, No. 15, p. 5 160. PENG J(Chinese Acad Sci, Grad Univ, Coll Chem & Chem Engn), et al., WU M M, HAN S B, LIU Y T, CHEN D F, et al.


23 Journal of Nuclear Materials, 2011 1) Long-term product consistency test of simulated 90-19/Nd HLW glass, Vol. 408, No. 1, p.102. GAN X Y, ZHANG Z T, WANG L, BAI Y, MA H 2) Segregation of Cr at tilt grain boundaries in Fe-Cr alloys: A metropolis Monte Carlo study, Vol. 408, No. 2, p. 161. TERENTYEV D( CEN SCK, Struct Mat Grp, Nucl Mat Sci Inst), HE X, et al. 3) Neutron/proton irradiation and He effects on the microstructure and mechanical properties of ferritic/martensitic steels T91 and EM10, Vol. 415, No. 3, p. 306. DAI Y( CEA, DEN, SRMA), et al., TONG Z, LONG B 4) Study of an iron-aluminide and alumina tritium barrier coating, Vol. 417, No. 1-3, p. 1 237. YANG H G, ZHAN Q, ZHAO W W, YUAN X M, HU Y, HAN Z B 5) Fusion neutron flux of center hole in LiD assembly under CARR reactor, Vol. 417, No. 1-3, p. 1 341. YU Jin-nan, HE Xin-fu, QIAN Jin, SHEN Feng, et al. 6) The fourth SINQ target irradiation program DAI Y(Paul Scherrer Institute), et al., GAO W, HOU H, HUANG Y, LONG B, et al.

24 Journal of Nuclear Science and Technology, Vol. 48, 2011 1) Multilateral assessment of the fast reactor system as a component of the future sustainable nuclear energy and paths for the system deployment, No. 4, p. 591. USANOV Vladimir(IAEA), et al., XU Mi, et al.

25 Journal of the Physical Society of Japan, Vol. 80, 2011 1) Study of the multiphonon gamma-vibrational bands in even-even 176-190Pt isotopes, No. 4, 044201. KANG Xuzhong(China Inst Technol, State Key Lab Breeding Base Nucl Resources & Envi), et al., GU Jian-zhong, WU Xiao-guang, et al.,

26 Journal of Physics: Conference Series, 2011 1) Fusion-fission and quasifission competition in the 32S+184W reaction, Vol. 282, No. 1, 012013. ZHANG H Q, ZHANG C L, LIN C J, et al. 2) Current progress of nuclear astrophysical reaction and decay study at CIAE, Vol. 312, Section 4, 042013. LIU W P, LI Z H, GUO B, WANG Y B, SU J, BAI X X, LIAN G, WANG B X, YAN S Q, ZENG S, LI Y J, LI E T, JIN S J, LIU X 3) Lifetime measurements in mirror nuclei 31S and 31P: A test for isospin mixing

Tonev D.(INRNE, Bulgarian Academy of Science), et al, ZHONG Q 4) Peculiarities of sub-barrier reactions with heavy ions, Vol. 282.

Sargsyan V V (Joint Institute for Nuclear Research), et al, ZHANG H Q

27 Journal of Physics G, Vol. 38, 2011 1) Evolution of the X(5) critical-point symmetry in rotating 176Os, No. 2, 025102. HAO X, ZHU L H, WU X G, HE C Y, PAN B, ZHENG Y, WANG L L, WANG L, LI X Q, LIU Y, LI G S 2) Isomeric mirror states as probes for effective charges in the lower pf shell, No. 3, 035104. HOISCHEN R( Lund Univ, Dept Phys), et al., MA H L, et al. 3) A new approach to select the quasifree mechanism in the Trojan horse method, No. 8, 085103.


WEN Qun-gang(Univ Sci & Technol China), et al., LI Cheng-bo, ZHOU Shu-hua, MENG Qiu-ying

28 Journal of Physical Chemistry B, Vol. 115, 2011 1) Large-scale structures in tetrahydrofuran-water mixture with a trace amount of antioxidant butylhydroxytoluene (BHT), No. 24, p. 7 887. LI Zhi-yong(CAS, State Key Lab Polymer Phys & Chem, Joint Lab Polymer Sci & Mat, Beijing Natl Lab Mol Sci, Inst Chem), et al., ZHANG Li, et al.

29 Journal of Radioanalytical and Nuclear Chemistry, 2011 1) Preparation and measurement of the half-life of 101Tc, Vol. 287, No. 1, p. 267. YOU Xin-feng, ZHANG Sheng-dong, YANG Zhi-hong, DING You-qian, CUI An-zhi 2) Correction factors for the gamma attenuation effects in large sample neutron activation analysis, Vol. 287, No. 2, p. 513. ZHANG Hai-qing, NI Bang-fa, TIAN Wei-zhi, ZHANG Gui-ying, HUANG Dong-hui, LIU Cun-xiong, XIAO Cai-jin, NIE Peng, SUN Hong-chao 3) Study on mechanism for oxidation of N, N-dimethylhydroxylamine by nitrous acid, Vol. 287, No. 3, p. 673. LI Gao-liang, HE Hui 4) Study on essential and toxic elements intake from drinking of Chinese tea, Vol. 287, No. 3, p. 887. ZHANG Hai-qing, NI Bang-fa, TIAN Wei-zhi, ZHANG Gui-ying, HUANG Dong-hui, LIU Cun-xiong, XIAO Cai-jin, SUN Hong-chao, ZHAO Chang-jun 5) Characterization of sampling behavior for multielements in NIST SRM 2703, Vol. 288, No. 1, p. 163. HUANG Dong-hui, SUN Hong-chao, NI Bang-fa, TIAN Wei-zhi, WANG Ping-sheng, LIU Cun-xiong, ZHANG Gui-ying, XIAO Cai-jin, ZHANG Hai-qing, ZHAO Chang-jun 6) Study on valence adjustment of Pu in 1 bp solution of CIAE-APOR process with N2O4, Vol. 288, No. 1, p. 279. LI Gao-liang, HE Hui, ZHENG Wei-fang, TANG Hong-bin, LI Hui-rong, LAN Tian, LIU Xie-chun, ZHANG Hu, YANG He, LUO Fang-xiang, XIAO Song-tao, YE Guo-an 7) The application of N, N-dimethylhydroxylamine as reductant for the separation of plutonium from uranium, Vol. 288, No. 2, p. 351. LIU Jin-ping, HE Hui, TANG Hong-bin, CHEN Yan-xin 8) Separation of 142La from fission products by SISAK technique, Vol. 289, No. 1, p.23. XU Li-jun, YE Hong-sheng, CHEN Ke-sheng, LIN Min, CHEN Yun-dong 9) The kinetics of the reduction reaction of plutonium (IV) with N, N-dimethylhydroxylamine, Vol. 289, No. 1, p. 41. CHEN Yan-xin, TANG Hon-bing, LIU Jin-ping, HE Hui

30 Laser and Particle Beams, Vol. 29, 2011 1) The comparison of the elements for the homogenizing charged particle irradiation, No. 1, p. 87. LI J H, REN X Y

31 Materials Science Forum, Vol. 687, 2011 1) 60Co gamma-ray irradiation effects on pentacene-based organic thin-film transistors, p. 576. LI Cai, et al.


32 Materials Research Bulletin, Vol. 46, 2011 1) Structural, magnetic and dielectric properties of Bi1－ySryFe(1－y)(1－x)Sc(1－y)xTiyO3 (x=0-0.2, y=0.1-0.3) ceramics, No. 3, p. 378. SHI Chen-yang(Chinese Acad Sci, Grad Univ, Coll Chem & Chem Engn), et al., LIU Xin-zhi, et al.

33 Nuclear Instruments & Methods in Physics Research Section A, 2011 1) Particle pulse shape discrimination on a silicon surface barrier detector irradiated with 14 MeV neutrons, Vol. 625, No. 1, p. 35. LI Yong-ming, RUAN Xi-chao, MA Zhong-yuan, ZHOU Bin 2) A neutron reflectometer with horizontal sample geometry at CARR, Vol. 656, No. 1, p. 65. YUAN Guang-cui(Chinese Acad Sci, Inst Chem, State Key Lab Polymer Phys & Chem, Joint Lab Polymer Sci & Mat), et al., LI Tian-fu, HE Lin-feng, LIU Yun-tao, CHEN Dong-feng 3) Determination of U-235 isotope abundance by measuring selected pairs of fission products, Vol. 665, p. 70. QIAO Ya-hua, WU Ji-zong, YANG Yi, ZHANG Ming, LIU Shi-long

34 Nuclear Instruments & Methods in Physics Research Section B, Vol. 269, 2011 1) Study on measurement of fission product nuclide 126Sn by AMS, No. 3, p. 392. SHEN Hong-tao, JIANG Shan, HE Ming, DONG Ke-jun, LI Chao-li, HE Guo-zhu, WU Shao-lei, GONG Jie, LU Li-yan, LI Shi-zhuo, ZHANG Da-wei, SHI Guo-zhu, HUANG Chun-tang, WU Shao-yong 2) Calculation and analysis of cross-sections for p+90,91,92,94,96natZr reactions up to 200 MeV, No. 4, p. 472. REN Wen-tao, HAN Yin-lu 3) Calculation and analysis of p+40,42,43,44,46,48,natCa reaction cross sections at incident energies from threshold to 250 MeV, No. 6, p. 597. LIANG Hai-ying, HAN Yin-lu, SHEN Qing-biao 4) Calculation of cross-sections for p+92,94,95,96,97,98,100Mo reactions up to 160 MeV, No. 7, p. 671. WU Zhen-dong, HAN Yin-lu 5) Theoretical calculation and analysis of the p+59Co reaction, No. 17, p. 1 899. LIANG Hai-ying, HAN Yin-lu, SHEN Qing-biao 6) 32Si AMS measurement with delta Δe-Q3D method, No. 23, p. 2 745. GONG Jie, LI Chao-li, WANG Wei, ZHENG Guo-wen, HU Hao, HE Ming, JIANG Shan 7) The cyclotron development activities at CIAE, No. 24, p. 2 863. ZHANG Tian-jue, LI Zhen-guo, AN Shi-zhong, YIN Zhi-guo, YANG Jian-jun, YANG Fang 8) Design and construction of a compact portable pulsed power generator, No. 24, p. 2 941. WANG Chuan, ZHENG Xia, ZOU Jian, ZHANG Tian-jue, JIANG Xing-dong 9) Development and application of a new method to shim first harmonic in compact cyclotron, No. 24, p. 2 946.

ZHANG Tian-jue, ZHONG Jun-qing, LI Ming, WANG Chuan, LU Yin-long, JIANG Xing-dong, YANG Jian-jun, LIN Jun, YANG Fang 10) Overall design of CYCIAE-14, a 14 MeV PET cyclotron, No. 24, p. 2 950.

ZHANG Tian-jue, LU Yin-long, YIN Zhi-guo, ZHONG Jun-qin, CUI Tao, LI Min, WEI Su-min, SONG Guo-fang, WU Long-cheng, JI Bin, XING Jian-sheng, QIN Jiu-chang, JIA Xian-lu, HU Wei-ping, YANG Jian-jun, AN Shi-zhong, GUAN Feng-ping, ZHEN Xia, WEN Li-peng, LIN Jun, LI Zhen-guo, ZHANG Xing-zhi, CAI Yue-xin, YANG Fang 11) Beam dynamics study for a small, high current 14 MeV PET cyclotron, No. 24, p. 2 955. ZHANG Tian-jue, LI Ming, ZHONG Jun-qing, AN Shi-zhong, WEI Su-min


12) Physics design of a 70 MeV high intensity cyclotron, CYCIAE-70, No. 24, p. 2 959. ZHANG Tian-jue, AN Shi-zhong, WANG Chuan, YIN Zhi-guo, WEI Su-min, LI Ming, YANG Jian-jun, JI Bin, JIA Xian-lu, ZHONG Jun-qing, YANG Fang 13) Conceptual design of an 800 MeV high power proton driver, No. 24, p. 2 964. ZHANG Tian-jue, YANG Jian-jun, LI Ming, XIA Le, AN Shi-zhong, YIN Zhi-guo, ZHONG Jun-qing, YANG Fang 14) Investigation for the vertical focusing enhancement of compact cyclotron by asymmetrical shimming bar, No. 24, p. 2 968. ZHANG Tian-jue, WANG Chuan, ZHONG Jun-qing, YAO Hong-juan

35 Nuclear Physics A, 2011 1) Charged particle elliptic flow in p+p collisions at LHC energies in a parton and hadron cascade model PACIAE, Vol. 860, No. 1, p. 68.

ZHOU Dai-mei(Institute of Particle Physics and Key Laboratory of Quark & Lepton Physics, Huazhong Normal University), YAN Yu-liang, DONG Bao-guo, LI Xiao-mei, SA Ben-hao

2) New approach for alpha decay half-lives of superheavy nuclei and applicability of WKB approximation, Vol. 861, No. 1, p. 1. DONG Jian-min, et al.

36 Nuclear Science and Engineering, 2011 1) Calculation and analysis of neutron-induced reactions on Co-59 up to 200 MeV, Vol. 168, No. 2, p. 151. ZHANG Yue, HAN Yin-lu, GUO Hai-rui, SHEN Qing-biao 2) Calculation of the complete sets of nuclear data for n+S-32,S-34 below 20 MeV, Vol. 169, No. 2, p. 198. YIN Sheng-gui, HUANG Xiao-long

37 Nuclear Science and Techniques, Vol. 22, 2011 1) Radiolytic organics in gamma-ray irradiated aqueous solution of N, N-diethylhydroxylamine, No. 2, p. 95. WANG Jin-hua (Shanghai Univ, Sch Environm & Chem Engn, Shanghai Appl Radiat Inst), et al., ZHENG Wei-fang, HE Hui, ZHANG Sheng-dong 2) Design of a prompt-gamma neutron activation analysis system on China Advanced Research Reactor, No. 5, p. 287. SUN Hong-chao, NI Bang-fa, XIAO Cai-jin, ZHANG Gui-ying, LIU Cun-xiong

38 Optics Letters, Vol. 36, 2011 1) Demonstration of soft X-ray laser of Ne-like Ar at 69.8 nm pumped by capillary discharge, No. 17, p. 3 458. ZHAO Yong-peng(Harbin Inst Technol, Natl Key Lab Sci & Technol Tunable Laser), et al., YANG Da-wei, et al.

39 Physica Scripta, 2011 1) Study of L-shell X-ray production cross section of Ta and Au by 20-55 MeV O5+ and F5+ bombardment, Vol. T144, 014020.

XU Qiu-mei(Chinese Acad Sci, Inst Modern Phys), et al., DU Shu-bin, CHANG Hong-wei, ZHANG Yan-ping


40 Physica Status Solidi, Vol. 5, 2011 1) X-ray detectors based on Fe doped GaN photoconductors, No. 5-6, p. 187. FU Kai(Chinese Acad Sci, Suzhou Inst Nanotech & Nanobion), et al., ZHANG Guo-guang

41 Physical Chemistry Chemical Physics, Vol. 13, 2011 1) Structure-property relations in crystalline L-leucine obtained from calorimetry, X-rays, neutron and Raman scattering, No. 14, p. 6 576. JIAO Xue-she, et al.

42 Physical Review C, 2011 1) New insight into the shape coexistence and shape evolution of 157Yb, Vol. 83, No. 1, 014318. XU C( Peking Univ, Sch Phys), et al., ZHU L H, WU X G, LI G S, HE C Y, et al. 2) Magnetic rotation in 112In, Vol. 83, No. 2, 024309. HE C Y, LI X Q, WU X G, LIU Y, PAN B, LI G S, LI L H, WANG Z M 3) Nuclear modification factors of phi mesons in d plus Au, Cu plus Cu, and Au plus Au collisions at root s(NN)=200 GeV, Vol. 83, No. 2, 024909. ADARE A( Univ Colorado, Boulder), et al., LI X, ZHOU S, et al. 4) Properties of the rotational bands in 161Er, Vol. 83, No. 3, 034318. CHEN L( Chinese Acad Sci, Inst Modern Phys), et al., ZHU L H, WU X G 5) Role of the coupling between neck and radial degrees of freedom in evolution from dinucleus to mononucleus, Vol. 83, No. 4, 044613. LIU Zu-hua, et al. 6) Nonequilibrium dynamics in heavy-ion collisions at low energies available at the GSI Schwerionen Synchrotron, Vol. 83, No. 4, 044617. LI Qing-feng(Huzhou Teachers Coll, Sch Sci), et al., LI Zhu-xia, et al. 7) Azimuthal correlations of electrons from heavy-flavor decay with hadrons in p plus p and Au plus Au collisions at root sNN=200 GeV, Vol. 83, No. 4, 044912. ADARE A( Univ Colorado, Boulder), et al., LI X, ZHOU S, et al. 8) Systematic study of tensor effects in shell evolution, Vol. 83, No. 5, 054305. WANG Y Z, GU J Z, DONG J M, ZHANG X Z 9) Spin-isospin excitations as quantitative constraints for the tensor force, Vol. 83, No. 5, 054316. BAI C L, ZHANG H Q, ZHANG X Z, et al. 10) Properties of the pi h11/2 band in the stable nucleus 193Ir, Vol. 83, No. 5, 054323. FANG Y D(Chinese Acad Sci, Inst Modern Phys), et al., WU X G, HE C Y, ZHENG Y, WANG Z M 11) Can one identify the intrinsic structure of the yrast states in 48Cr after the backbending? Vol. 83, No. 5, 057303. GAO Z C, CHEN Y S, CHEN Y J, et al. 12) Observation of high-spin oblate band structures in Pm-141, Vol. 83, No. 6, 064303. GU L( Tsinghua Univ, Dept Phys), et al., ZHU L H, WU X G, HE C Y, LI G S, WANG L L, ZHENG Y, ZHANG B 13) Signature inversion in odd-odd 114Rh: First identification of high-spin states in very neutron-rich 114Rh and application of the triaxial projected shell model, Vol. 83, No. 6, 064310. LIU S H(Vanderbilt Univ, Dept Phys & Astron), et al., CHEN Y S, GAO Z C, et al. 14) 4He microscopic optical model potential, Vol. 83, No. 6, 064618.


GUO Hai-rui, XU Yong-li, LIANG Hai-ying, HAN Yin-lu, SHEN Qing-biao 15) Identified charged hadron production in p plus p collisions at root s=200 and 62.4 GeV, Vol. 83, No. 6, 064903. ADARE A( Univ Colorado, Boulder), et al., LI X, ZHOU S, et al. 16) Effects of tensor interaction on pseudospin energy splitting and shell correction, Vol. 84, No. 1, 014303. DONG J M, GU J Z, WANG Y Z, ZHANG X Z 17) Further improvements on a global nuclear mass model, Vol. 84, No. 1, 014333. LIU Min(Guangxi Normal Univ, Dept Phys), et al., WU Xi-zhen 18) Identification of high-spin states in the stable nucleus 195Pt, Vol. 84, No. 1, 017301. FANG Y D( Chinese Acad Sci, Inst Modern Phys), et al., WU X G, HE C Y, HENG Y, WANG Z M, et al. 19) Suppression of away-side jet fragments with respect to the reaction plane in Au plus Au collisions at root sNN=200 GeV, Vol. 84, No. 2, 024904. ADARE A( Univ Colorado), et al., LI X, ZHOU S, et al. 20) Calculation of the evaporation residue cross sections for the synthesis of the superheavy element Z=119 via the 50Ti+249Bk hot fusion reaction, Vol. 84, No. 3, 031602. LIU Zu-hua, et al. 21) Strange quark suppression and strange hadron production in pp collisions at energies available at the BNL Relativistic Heavy Ion Collider and the CERN Large Hadron Collider, Vol. 84, No. 3, 034905.

LONG Hai-yan(China Three Gorges Univ, Coll Sci, Dept Phys), et al., YAN Yu-liang, MA Hai-liang, SA Ben-hao 22) Longitudinal fluctuations in the partonic and hadronic initial state, Vol. 84, No. 3, 034911.

CHENG Yun(Huazhong Normal Univ, Inst Particle Phys), YAN Yu-liang, SA Ben-hao, et al. 23) Identification of the gamma-vibrational band built on the 11/2－ [505] orbital in 165Er, Vol. 84, No. 3, 037303. WANG S T( Chinese Acad Sci, Inst Modern Phys), et al., ZHU L H, WU X G 24) Tensor effects on the proton sd states in neutron-rich Ca isotopes and bubble structure of exotic nuclei, Vol. 84, No. 4, 044333. WANG Y Z, GU J Z, ZHANG X Z, DONG J M 25) Production of omega mesons in p plus p, d plus Au, Cu plus Cu, and Au plus Au collisions at root sNN=200 GeV, Vol. 84, No. 4, 044902. ADARE A( Univ Colorado), et al., LI X, ZHOU S 26) Heavy-quark production in p plus p and energy loss and flow of heavy quarks in Au plus Au collisions at root sNN=200 GeV, Vol. 84, No. 4, 044905. ADARE A( Univ Colorado), et al., LI X, ZHOU S 27) In-beam gamma spectr scopy of the odd-Z nucleus Pm-139, Vol. 84, No. 5, 054302. ZHANG N T( Chinese Acad Sci, Dept Modern Phys), et al., DING B, HUANG W J, WANG S T, et al. 28) Determination of the emission probability of the 21.54 keV gamma ray in the decay of 151Sm, Vol. 84, No. 5, 054307. SHEN Hong-tao, HE Ming, DONG Ke-jun, JIANG Shan 29) Diverse collective excitations in 159Er up to high spin, Vol. 84, No. 5, 054320. MUSTAFA M(Univ Liverpool, Oliver Lodge Lab), et al., MA H L, et al. 30) Influence of transport variables on isospin transport ratios, Vol. 84, No. 5, 054603. COUPLAND D D S(Michigan State Univ, Dept Phys & Astron, Natl Superconducting Cyclotron Lab),


et al., ZHANG Yin-gxun 31) J/psi suppression at forward rapidity in Au plus Au collisions at root sNN=200 GeV, Vol. 84, No. 5, 054912. ADARE A( Univ Colorado), et al., LI X, ZHOU S 32) In-beam gamma spectroscopy of the odd-Z nucleus Pm-139, Vol. 84, No. 5, 057302. ZHANG N T(Chinese Acad Sci, Dept Modern Phys), et al., WU X G, ZHENG Y 33) Effects of nuclear deformation and neutron transfer in capture processes, and fusion hindrance at deep sub-barrier energies, Vol. 84, No. 6, 064614. SARGSYAN V V, ZHANG H Q

43 Physical Review D, 2011 1) Cross section and double helicity asymmetry for eta mesons and their comparison to pi(0) production in p plus p collisions at root s=200 GeV, Vol. 83, No. 3, 032001. CHANG W C(Acad Sinica, Inst Phys), et al., LI X, ZHOU S, et al. 2) Measurement of neutral mesons in p plus p collisions at root s=200 GeV and scaling properties of hadron production, Vol. 83, No. 5, 052004. ADARE A( Univ Colorado), et al., LI X, ZHOU S 3) Event structure and double helicity asymmetry in jet production from polarized p plus p collisions at root s=200 GeV, Vol. 84, No. 1, 012006. ADARE A( Univ Colorado), et al., LI X, ZHOU S 4) Femtoscopy of pp collisions at root s=0.9 and 7 TeV at the LHC with two-pion Bose-Einstein correlations, Vol. 84, No. 11, 112004. AAMODT K( Univ Bergen, Dept Phys & Technol), et al., LI X, et al.

44 Physical Review Letters, 2011 1) Centrality dependence of the charged-particle multiplicity density at midrapidity in Pb-Pb collisions at root sNN=2.76 TeV, Vol. 106, No. 3, 032301. AAMODT K( Univ Bergen, Dept Phys & Technol), et al., LI X, et al. 2) Cross section and parity-violating spin asymmetries of W-+/- boson production in polarized p plus p collisions at root s=500 GeV, Vol. 106, No. 6, 062001. ADARE A( Univ Colorado), et al., LI X, ZHOU S 3) Higher harmonic anisotropic flow measurements of charged particles in Pb-Pb collisions at root sNN=2.76 TeV, Vol. 107, No. 3, 032301. AAMODT K( Univ Bergen, Dept Phys & Technol), et al., LI X, et al. 4) Single spin asymmetries in charged pion production from semi-inclusive deep inelastic scattering on a transversely polarized 3He target at Q2=1.4-2.7 GeV2, Vol. 107, No. 7, 072003. QIAN X( Duke Univ), et al., LI X, LI Y, et al. 5) Cold nuclear matter effects on J/psi yields as a function of rapidity and nuclear geometry in d plus a collisions at root sNN=200 GeV, Vol. 107, No. 14, 142301. ADARE A( Univ Colorado), et al., LI X, ZHOU S 6) Suppression of back-to-back hadron pairs at forward rapidity in d plus Au collisions at root sNN=200 GeV, Vol. 107, No. 17, 172301. BASYE A T( Abilene Christian Univ), et al., LI X, ZHOU S 7) Measurements of higher order flow harmonics in Au plus Au collisions at root sNN=200 GeV, Vol. 107, No. 25, 252301. ADARE A( Univ Colorado), et al., LI X, ZHOU S


45 Physical Review Special Topics: Accelerators and Beams, Vol. 14, 2011 1) Towards quantitative simulations of high power proton cyclotrons, No. 5, 054402. BI Y J, ZHANG T J, et al.

46 Physics Letters B, 2011 1) Impact of parton rescattering on analysis of p plus p collision data at LHC energies, Vol. 694, No.4-5, p. 435. ZHOU Dai-mei(Huazhong Normal Univ, Inst Particle Phys), et al., YAN Yu-liang, LI Xiao-mei, SA Ben-hao 2) Suppression of charged particle production at large transverse momentum in central Pb-Pb collisions at root sNN=2.76 TeV, Vol. 696, No. 1-2, p. 30. APPELSHAEUSER H( Goethe Univ Frankfurt, Inst Kernphys), et al., LI X, et al. 3) Two-pion Bose-Einstein correlations in central Pb-Pb collisions at root sNN=2.76 TeV, Vol. 696, No. 4, p. 328. AAMODT K( Univ Bergen, Dept Phys & Technol), et al., LI X, et al. 4) Effect of the splitting of the neutron and proton effective masses on the nuclear symmetry energy at finite temperatures, Vol. 697, No. 3, p. 246. OU Li, LI Zhu-xia, ZHANG Ying-xun, et al. 5) Evidence for shape coexistence at medium spin in 76Rb, Vol. 701, No. 3, p. 306.

WADSWORTH R(Department of Physics, University of York), et al., MA Hai-liang, et al. 6) Rapidity and transverse momentum dependence of inclusive J/psi production in pp collisions at root s=7 TeV, Vol. 704, No. 5, p. 442. ALESSANDRO B( Sezione Ist Nazl Fis Nucl), et al., LI X, et al. 7) Correlation between muonic levels and nuclear structure in muonic atoms, Vol. 704, No. 5, p. 600. DONG J M, GU J Z, et al.

47 Powder Technology, Vol. 207, 2011 1) Simulation of cohesive particle motion in a sound-assisted fluidized bed, No. 1-3, p. 65. WANG Shuai(Harbin Inst Technol, Sch Energy Sci & Engn), LI Xiang, et al.

48 Progress in Particle and Nuclear Physics, Vol. 66, 2011 1) Constraints on the density dependence of the symmetry energy from heavy-ion collisions, No. 2, p. 400. TSANG M B( Michigan State Univ, Natl Superconducting Cyclotron Lab), et al., ZHANG Y X

49 Progress of Theoretical Physics, Vol. 125, 2011 1) Equations of motion for the system of interest under time-dependent environment, No. 2, p. 359. SAKATA F(Chinese Acad Sci, Inst Theoret Phys), et al., ZHUO Yi-zhong, et al.

50 Solid State Sciences, Vol. 13, 2011 1) Structural, magnetic and dielectric properties of Sc modified (1－y) BiFeO3-yBaTiO3 ceramics, No. 10, p. 1 885. SHI Chen-yang(Chinese Acad Sci, Grad Univ, Coll Chem & Chem Engn), et al., LIU Xin-zhi, et al.

51 Superconductor Science & Technology, Vol. 24, 2011 1) Systematic growth of BaFe2－xNixAs2 large crystals, No. 6, 065004.


CHEN Yan-chao, et al.

52 Chinese Physics Letters, Vol. 28, 2011 1) Astrophysical rates for the 6He(p, gamma)7Li reaction, No. 5, 052102.

LI Er-tao, LI Zhi-hong, SU Jun, GUO Bing, LI Yun-ju, YAN Sheng-quan, BAI Xi-xiang, WANG You-bao, WANG Bao-xiang, LIAN Gang, ZENG Sheng, FANG Xiao, LIU Wei-ping 2) AMS measurement of Mn-53 at CIAE, No. 7, 070703. DONG Ke-jun, HE Ming, LI Chao-li, HU Hao, LI Zhen-yu, WU Shao-yong, Liu Jian-cheng, YOU Qu-bo, JIN Chun-sheng, YUAN Jian, JIANG Shan 3) Collective flow of lambda hyperons within covariant kaon dynamics, No. 9, 092502. XING Yong-zhong(Tianshui Normal Univ, Dept Phys), et al., ZHENG Yu-ming 4) Tensor effect on bubble nuclei, No. 10, 102101. WANG Yan-zhao, GU Jian-zhong, ZHANG Xi-zhen, DONG Jian-min, et al. 5) Shape evolution in rotating 178Os, No. 11, 112101.

HAO Xin(Shenzhen Univ, Coll Phys & Technol), et al., WU Xiao-guang, HE Chuang-ye, ZHENG Yun, LI Li-hua, LI Guang-sheng 6) Nuclear dynamical quadrupole deformations in heavy-ion reactions, No. 12, 122401. DOU Liang(Shenzhen Univ, Coll Phys), et al., DOU Liang, et al.

53 Radiation and Environmental Biophysics, Vol. 50, 2011 1) Study on evaluating dose to fishes based on its anatomic model, No. 3, p. 475. LI Jing-jing, LIU Sen-lin, WANG Chun-hong, LIU Rui-rui

54 Acta Physica Sinica, Vol. 60, 2011 1) Influence of nucleon motion on the effective mass and energy of kaon in dense nuclear matter, No. 1, 012501. XING Yong-zhong(Tianshui Normal Univ, Dept Phys), et al., ZHENG Yu-ming 2) L-shell X-ray emission cross section of tantalum by 20-45 MeV O5+bombardment, No. 9, 093202.

XU Qiu-mei(Chinese Acad Sci, Inst Modern Phys), et al., DU Shu-bin, CHANG Hong-wei, ZHANG Yan-ping

55 Chinese Physics B, Vol. 20, 2011 1) First principles simulation technique for characterizing single event effects, No. 6, 068501. ZHANG Ke-ying(NW Inst Nucl Tech), et al., GUO Gang, et al.

56 Chinese Physics C, Vol. 35, 2011 1) Expanding and improving the LEADS code for dynamics design and multiparticle simulation, No. 3, p. 293. LI Jin-hai, REN Xiu-yan, MA Yan-yun 2) Prompt neutron multiplicity distribution for 235U(n, f) at incident energies up to 20 MeV, No. 4, p. 344. CHEN Yong-jing, LIU Ting-jin 3) Cross section measurements for (n, p) reaction on stannum isotopes at neutron energies from 13.5 to 14.6 MeV, No. 5, p. 449. ZHOU S H 4) Determination of the time resolution for neutron scintillation detectors by multi-coincidence


measurement, No. 5, p. 475. LI Yong-ming, RUAN Xi-chao, ZHOU Bin, MA Zhong-yuan 5) Reinvestigation of the high spin states in 161Er and enhanced E1 transitions in the N=93 isotones, No. 6, p. 545. CHEN Liang(Chinese Acad Sci, Inst Modern Phys), et al., ZHU Li-hua, WU Xiao-guang 6) Isospin dependence of nuclear multifragmentation in statistical model, No. 6, p. 567. ZHANG Lei(Hangzhou Dianzi Univ, Sch Informat Engn), et al., ZHANG Yan-ping, et al. 7) Exploring nuclear symmetry energy with isospin dependence in neutron skin thickness of nuclei, No. 7, p. 629. LIU Min(Beijing Normal Univ, Coll Nucl Sci & Technol), et al., LI Zhu-xia, et al. 8) The structure of the spherical tensor forces in the USD and GXPF1A shell model Hamiltonians, No. 8, p. 753. WANG Han-kui, GAO Zao-chun, CHEN Yong-shou, CHEN Yong-jing, et al. 9) New band structures in 107Ag, No. 11, p. 1 009.

ZHANG Biao, HE Chuang-ye, WU Xiao-guang, ZHENG Yun, YU Bei-bei, LI Guang-sheng, YAO Shun-he, WANG Lie-lin 10) Timing properties and pulse shape discrimination of LAB-based liquid scintillator, No. 11, p. 1 026. LI Xiao-bo(Chinese Acad Sci, Inst High Energy Phys), et al., RUAN Xi-chao, et al.

57 Science China-Physics Mechanics & Astronomy, Vol. 54, 2011 1) Helium-3 global optical model potential with energies below 250 MeV, No. 11, p. 2 005. XU Yong-li, GUO Hai-rui, HAN Yin-lu, SHEN Qing-biao 2) A possible proton pygmy resonance in 17Ne, S1, p. 1. MA Zhong-yu, TIAN Yuan 3) Heavy ion reactions around the Coulomb barrier, S1, p. 6. ZHANG Huan-qiao, LIN Cheng-jian, JIA Hui-ming, ZHANG Chun-lei, ZHANG Gao-long, YANG Feng, LIU Zu-hua, AN Guang-peng, WU Zhen-dong, XU Xin-xing, JIA Fei 4) BRIF and CARIF progress, S1, p. 14.

LIU Wei-ping, LI Zhi-hong, BAI Xi-xiang, WANG You-bao, GUO Bing, PENG Chao-hua, YANG Yi, SU Jun, CUI Bao-qun, ZHOU Shu-hua, ZHU Sheng-yun, XIA Hai-hong, GUAN Xia-ling, ZENG Sheng, ZHANG Huan-qiao, CHEN Yong-shou, TANG Hong-qing, HUANG Li, FENG Bei-yuan 5) Properties of the 3/2－[521] band in the odd-N rare-earth nuclei, S1, p. 37. CHEN Liang(Institute of Modern Physics, Chinese Academy of Sciences), et al., ZHU Li-hua 6) A possible proton pygmy resonance in 17Ne, S1, p. 49. MA Zhong-yu, TIAN Yuan 7) Study of the primordial lithium abundance, S1, p. 67. LI Zhi-hong, LI Er-tao, SU Jun, LI Yun-ju, BAI Xi-xiang, GUO Bing, WANG You-bao, CHEN Yong-shou, HOU Su-qing, ZENG Sheng, LIAN Gang, LIU Wei-ping 8) Experimental research into the two-proton emissions from 17, 18Ne, 28P and 28, 29S, S1, p. 73. LIN Cheng-jian, XU Xin-xing, JIA Hui-ming, YANG Feng, JIA Fei, WU Zhen-dong, ZHANG Shi-tao, LIU Zu-hua, ZHANG Huan-qiao 9) The design and construction of a pulsed beam generation system based on high intensity cyclotron, S2, p. 210. AN Shi-zhong, YIN Zhi-guo, LI Peng-zhan, SONG Guo-fang, WU Long-cheng, GUAN Feng-ping,


XIE Huai-dong, JIA Xian-lu, LU Yin-long, ZHANG Tian-jue 10) High performance computation on beam dynamics problems in high intensity compact cyclotrons, S2. p. 249. YANG Jian-jun, ZHANG Tian-jue, WANG Feng, AN Shi-zhong 11) The present situation and the prospect of medical cyclotrons in China, S2, p. 260. ZHANG Tian-jue, WEI Su-min, YANG Fang 12) The physics design of magnet in 14 MeV cyclotron, S2, p. 266. ZHONG Jun-qing, ZHANG Tian-jue, LI Ming, LV Yin-long, CUI Tao, YANG Jian-jun, XING Jian-sheng

58 Science of the Total Environment, Vol. 409, 2011 1) Urban air quality in the Asian region, No. 19, p. 4 140. HOPKE P K( Clarkson Univ, Ctr Air Resources Engn & Sci, Dept Chem & Biomol Engn), et al., NI Bang-fa, et al.

59 Chinese Science Bulletin, Vol. 56, 2011 1) Comprehensive test stand for high-intensity cyclotron development, No. 3, p. 238. ZHANG Tian-jue, LI Zhen-guo, CHU Cheng-jie, XING Jian-sheng, GUAN Feng-ping, ZHONG Jun-qing, JI Bin, GE Tao, YIN Zhi-guo, HOU Shi-gang, PAN Gao-feng, YAO Hong-juan, LU Yin-long, WANG Zhen-hui, WU Long-cheng, LIN Jun, JIA Xian-lu, WEI Su-min, WEN Li-peng, WANG Feng, XIA Le, CAI Hong-ru, XIE Huai-dong, CHEN Rong-fan, ZHANG Yan, ZHANG Su-ping, LIU Geng-shou, ZOU Jian, AN Shi-zhong,YANG Jian-jun, BI Yuan-jie, YANG Fang 2) A competitive dual-label time-resolved fluoroimmunoassay for the simultaneous determination of chloramphenicol and ractopamine in swine tissue, No. 15, p. 1 543. ZHANG Zhen(Chinese Acad Sci, State Key Lab Environm Chem & Ecotoxicol, Res Ctr Ecoenvironm Sci), et al., YAO Yan, et al.

60 Tsinghua Science and Technology, Vol. 16, 2011 1) Block cipher design:generalized single-use-algorithm based on chaos, No. 2, p. 194. ZHAO Geng(Key Laboratory of Information Security and Secrecy, Beijing Electronic Science and Technology Institute), et al., FANG Jing-qing, et al.

61 AIP Conference Proceedings, Vol. 1 409, 2011

1) Recent experimental results of two-proton correlated emission form the excited states of 17,18Ne and 28,29S, p. 98.

LIN Cheng-jian, XU Xin-xing, JIA Hui-ming, YANG Feng, JIA Fei

62 Journal of Physics Conference Series, Vol. 312, 2011 1) Current progress of nuclear astrophysical reaction and decay study at CIAE

LIU W P, LI Z H, GUO B, WANG Y B, SU J, BAI X X, LIAN G, WANG B X, YAN S Q, ZENG S, LI Y J, LI E T, JIN S J, LIU X

63 Advanced Materials Research, 2011 1) The optimization of material thickness for neutron shielding with Monte Carlo method

CHEN C, WANG M


2) Investigation on nonlinear constitutive relationship for a honeycomb sandwich composite, Vol. 291-294, p. 1 025-1 038.

64 Science China: Physics, Mechanics and Astronomy, 2011 1) Study of the primordial lithium abundance, p. 1-6.

LI Zhi-hong, LI Er-tao, SU Jun, LI Yun-ju, BAI Xi-xiang, GUO Bing, WANG You-bao, CHEN Yong-shou, HOU Su-qing, ZENG Sheng, LIAN Gang, SHI Jian-rong, LIU Wei-ping

65 Nuclear Power Engineering, Vol. 32, 2011 1) Stress analysis and evaluation of heavy double-hole pipe clip, p. 117-119. LI Hai-long, GAO Fu-hai, LI Nan

66 Book 1) Heat transfer—Theoretical analysis, experimental investigations and industrial systems Chapter 9. Heat transfer in film boiling of flowing water CHEN Yu-zhou


List of Scientific Publication in Chinese in 2011

1 Acta Physica Sinica, Vol. 60, 2011

1) Influence of nucleon motion on the effective mass and energy of kaon in dense nuclear matter, No. 1, 012501. XING Yong-zhong(Department of Physics, Tianshui Normal University), et al., ZHENG Yu-ming 2) L-shell X-ray emission cross section of tantalum by 20－45 MeV O5+ bombardment, No. 9, 093202. XU Qiu-mei(Institute of Modern Physics, Chinese Academy of Sciences), et al., ZHANG Yan-ping

2 Transactions of Materials and Heat Treatment, Vol. 32, 2011 1) Formation kinetics of interfacial intermetallic compounds of TA2/316L welding joints, No. 2, p. 61. HAN Li-qing, LONG Bin, QIAO Jian-sheng

3 Transactions of the China Welding Institution, 2011 1) Characteristics of welding-brazed joint between Nb-1Zr alloy and 304 stainless steel, No. 3, p. 105. LI Xin, ZHENG Jian-ping, ZHAO Jun

4 Journal of Aeronautical Materials, Vol. 31, 2011 1) 3D finite element simulation and experimental test on residual stress field by hole cold expansion, No. 2, p. 24.

LIU Xiao-long, LIU Yun-tao, CHEN Dong-feng

5 Chemical Analysis and Meterage, Vol. 20, 2011 1) Application of Raman spectroscopy in nuclear research field, No. 1, p. 92.

ZHANG Qian-ci, LIU Quan-wei, LI Ding-ming, WANG Ling

6 Science & Technology Review, Vol. 29, 2011 1) MA transmutation strategy, No. 7, p. 29. ZUO Guo-ping, KE Guo-tu, et al. 2) Readers’voices, No. 26, p. 82.

FANG Jin-qing

7 Automation & Instrumentation，2011 1) 51 SCM AT89C52 zirconia oxygen measuring system YIN Wei, XIE Jiao-rong, XIANG Lan-xiang, CONG Zhong-dou, HUANG Ji-dong

8 China Nuclear Power, 2011 1) The influence factors of the construction progress for the CEFR, No. 1, p. 24. LI He

9 Environmental Protection of Chemical Industry, Vol. 31, 2011 1) Adsorption of Cu2+ in wastewater on bamboo charcoal, No. 1, p. 26. LI Xiao-yan, et al.

APPENDIX·List of Scientific Publication in Chinese in 2011 261

10 Journal of East China University of Science and Technology: Natural Science Edition, Vol. 37, 2011

1) Influence of alkaline earth metal ions on luminescent properties of aluminoborate glass, No. 2, p. 179. LI Yao(East China University of Science and Technology), et al., LUO Zhi-ping

11 Chemical Research and Application, 2011 1) Synthesis and characterization of a novel extractant for the separation of trivalent actinides from lanthanides, No. 5, p. 597. HONG Zhe, YE Guo-an, TANG Hong-bin, HE Hui

12 Uranium Mining and Metallurgy, Vol. 30, 2011 1) Evaluation of uncertainty for determination of trace thorium in U3O8 by isotope dilution inductively coupled plasma mass spectrometry, No. 2, p. 79. CHU Quan-li, et al.

13 Complex Systems and Complexity Science, Vol. 8, 2011 1) Memorial to nobel winner Ⅰ. Prigogine for his 94 birthday, No. 2, p. 75. FANG Jin-qing 2) Summary report on "the 7th China National Forum on Network Science—Frontier Issue Workshop", No. 2, p. 92. FANG Jin-qing, et al. 3) Rapid developing of blogs-micro-blogs networks and its great effects on the world, No. 4, p. 68. FANG Jin-qing, LIU Qiang, LI Yong 4) Hybrid ratios effect on dynamic synchronization ability under the unified hybrid network framework, No. 4, p. 86. LIU Qiang, FANG Jin-qing, LI Yong

14 High Voltage Engineering, Vol. 37, 2011 1) Comprehensive analysis of lightning performance of overhead power distribution line with varied ground obliquity, No. 4, p. 848. LIU Jing, et al.

15 Journal of North China Electric Power University: Natural Science Edition, Vol. 38, 2011

1) Small punch test of the domestic A508-3 steel and issue argumentation, No. 3, p. 106. QIAO Jian-sheng, ZHONG Wei-hua, YANG Wen

16 Marine Environmental Science, Vol. 30, 2011

1) Temperature rise limits in the edge of mixing zone for thermal discharged from nuclear power plants—A case of a nuclear power plant, No. 3, p. 414. LI Jing-jing, ZHANG Yong-xing, LIU Yong-ye, YU Fan

17 Journal of Isotopes, Vol. 24, 2011 1) Biodistribution of 99Tcm labelled colloidal rhenium sulphide for sentinel node detection:the effects of


dosage and concentration of gelatin LI Hong-yu, LIANG Ji-xin, LUO Hong-yi, CHEN Bao-jun, YANG Chun-hui, ZHENG De-qiang 2) Establishment of an enzyme linked immunosorbent assay for triiodothyronine, No. 2, p. 98. GUAN Guo-ying, LI Li-bo, LIU Zhong-rui, XU Wen-ge, HAN Shi-quan 3) 177Lu-DTPA-BIS-BIOTIN binding of octreotide-dextran-avidinated PANC-1 cell lines in vitro, No. 3. DENG Xin-rong, ZHAI Shi-zhen, Shen Yi-jia, LUO Zhi-fu 4) Establishment of a production line for the fabrication of mega-curie sealed 60Co sources, No. 4, p. 154. LIU Xin-yue, YIN Zhen-guo, WANG Xin, LIANG Zheng-qiang 5) Normal and abnormal extraosseous uptake of 99Tcm-MDP on bone scintigraphy, No. 4, p. 246.

GUO Hai-bo, et al. 6) Research progress in radiolabeling,imaging mechanism and clinical applications of 18F-FDG, S1, p. 59.

ZHAI Shi-zhen, DU Jin, et al. 7) Concentration and application of common stable isotopes preparation, S1, p. 121. LI Gong-liang, CAI Yue-xin, MI Ya-jing, DU Xue-yuan, WU Ling-mei

18 Chinese Journal of Immunology, Vol. 27, 2011 1) Preparation and identification of monoclonal antibody against progesterone, No. 6, p. 548. WANG Bin, LIU Yi-bing, FENG Ting-ting, XU Wen-ge, HAN Shi-quan

19 Journal of China-Japan Friendship Hospital, Vol. 25, 2011 1) 131I-metaiodobenzylguanidine as treatment to patients with refractory high risk neuroblastoma: A three cases report and literature review, No. 3, p. 148. LIAN Hong-yun(The Affiliated Beijing Children Hospital, Capital University of Medical Sciences), et al., CHEN Yang

20 Chinese Journal of Nuclear Science and Engineering, Vol. 31, 2011 1) Study on operation simulation for PSFRP, No. 1, p. 28.

ZHANG Hou-ming, DUAN Tian-ying, LIU Guo-fa 2) The experimental research on the sodium spray fire, No. 1, p. 41.

DU Hai-ou, WANG Rong-dong, HU Wen-jun 3) CEFR information management system solution, No. 1, p. 48. LU Fei, ZHAO Jia-ning 4) Safety properties of China experimental fast reactor, No. 2, p. 116. XU Mi 5) BN800: The advance sodium cooled fast reactor plant based on dose fuel cycle, No. 2, p. 127. WU Xing-man 6) The determination of carbon in sodium by vacuum distillation—potentiometry, No. 3, p. 230. XIE Chun, JIA Yun-teng, GAO Yao-peng 7) The FSI seismic analysis for FBR core assemblies, No.3, p. 238. MO Ya-fei, WEN Jing, LI Hai-long 8) Development of ferritic/martensitic steels used as advanced duct material for fast reactor, No. 3, p. 245. FENG Wei, HUANG Chen, DU Ai-bing, et al. 9) Study of track development kinetics for CR-39 detectors in nanometer size, No. 3, p. 263. FANG Mei-hua(Nanjing University of Aeronautics & Astronautics), et al., LI Guang-wu, GUO Gang


10) Research in the detection of black powder based on nuclear quadrupole resonance technology, No. 3, p. 270. LI Kang-ning, YU Shuo, LI Xing, ZHANG Xiang-yang 11) R&D on advanced cladding materials ODS alloys for fast reactor, No. 4, p. 305. CUI Chao, HUANG Chen, SU Xi-ping, et al. 12) Spectrophotometric determination of nitrogen in sodium as indophenol, No. 4, p. 310. XIE Chun, LI Xu, XU Chi, JIA Yun-teng, YU Xiao-chen

21 Progress in Chemistry, Vol. 23, 2011 1) Some thinking of nuclear fuel reprocessing/recycling in China, No. 7, p. 1 264. GU Zhong-mao, et al. 2) A review on the development of spent nuclear fuel reprocessing and its related radiochemistry, No. 7, p. 1 289. YE Guo-an, ZHANG Hu

22 Journal of Hengyang Normal University, Vol. 32, 2011 1) Measurement method of soil radon, No. 3, p. 45. SHEN Chao(University of South China), et al., CHEN Ling, et al.

23 Journal of University of South China: Science and Technology, Vol. 25, 2011 1) Discuss the technology for decrease the detection limit of NaI(Tl) gamma spectrometer, No. 1, p. 6. GUO Xiao-bin, LIU Zhi-ying, WANG Hong-yan, WANG Lie-ming

24 Journal of University of South China: Social Science Edition, Vol. 12, 2011 1) The influence and inspiration of Fukushima nuclear power plant nuclear accident on the development of nuclear power in China, No. 2, p. 1. ZOU Shu-liang(University of South China), ZOU Yang

25 High Power Laser and Particle Beams, Vol. 23, 2011 1) Enhancement of accelerated proton yield in intense laser irradiating double-layer targets, No. 1, p. 107. TAN Zhi-xin, LAN Xiao-fei, LU Jian-xin, WANG Lei-jian, HUANG Yong-sheng, YANG Da-wei, WANG Nai-yan 2) Measurement and application of Be(d, n) reaction neutron source, No. 1, p. 209. ZHANG Jian-fu(Northwest Institute of Nuclear Technology), RUAN Xi-chao, HOU Long, LI Xia, ZHANG Guo-guang, BAO Jie, HUANG Han-xiong, NIE Yang-bo 3) Imaging-velocity interferometer system for any reflector for shock diagnostics , No. 3, p. 661. WANG Zhao, GAO Shuang, LIANG Jing, TIAN Bao-xian, HE Yi-guang, LU Ze, TANG Xiu-zhang 4) TRIUMF ARIEL e-linac design study, No. 3, p. 791. YAN Fang, et al. 5) Thermophysical properties of helium using molecular dynamics simulations, No. 6, p. 1 649. HE Yi-guang, WANG Zhao, LIANG Jing, GAO Shuang, TIAN Bao-xian, TANG Xiu-zhang 6) Measure probes on X-pinch compact pulsed power source, No. 6, p. 1 687. ZOU Jian, WANG Chuan, ZHENG Xia, ZENG Nai-gong, ZHANG Tian-jue, JIANG Xing-dong


26 Materials China, Vol. 30, 2011 1) Irradiation property of pressure vessel materials in China, No. 5, p. 7. LIN Yun, ZHANG Chang-yi, NING Guang-sheng, TONG Zhen-feng, YANG Wen

27 Journal of Chinese Mass Spectrometry Society, Vol. 32, 2011 1) Measurement of znic isotopes and it s application in environmental geochemistry and nutriology, No. 3, p. 138. LU Hai, LI Jin-ying 2) Determination of the 94Nb/93Nb ratio by MC-ICP-MS, S1, p. 39. ZHANG Ji-long, ZHU Liu-chao, ZHAO Yong-gang, HE Guo-zhu, JIANG Xiao-yan 3) Study on analyzing of single uranium particle by FT-TIMS, S1, p. 41. CHEN Yan, SHEN Yan, ZHAO Yong-gang, CHANG Zhi-yuan, LI Li-li, WANG Fan, et al. 4) Production of monodisperse uranium oxide particles and their application in the measurement of isotopic ratio by SIMS, S1, p. 43. WANG Fan, CHEN Yan, CHANG Zhi-yuan, ZHAO Yong-gang, ZHANG Yan, WANG Tong-xing, SHEN Yan, LI Jing-huai, CUI Hai-ping 5) Research on analyzing minor-isotopic ration of uranium-containing particle by SIMS, S1, p. 46. SHEN Yan, ZHANG Yan, WANG Tong-xing 6) Study on analysis of 234U /238U isotope ratio in U-Pb particles by SIMS, S1, p. 48. WANG Tong-xing, WANG Fan, ZHANG Yan, ZHAO Yong-gang 7) Study on the determination of selenium isotopes abundance with MC-ICP-MS, S1, p. 50. ZHU Liu-chao, ZHAO Yong-gang, ZHANG Ji-long, JIANG Xiao-yan, LI Shao-wei 8) Primary studies on the burnup estimation of irradiated uranium by determining 234U/238U in contaminated environmental samples, S1, p. 52. JIANG Xiao-yan, CHANG Zhi-yuan, ZHANG Ji-long, ZHAO Yong-gang 9) Preliminary study of influencing in analysis by glow discharge mass spectrometry, S1, p. 322. XU Chang-kun, ZHAO Yong-gang, et al.

28 Nuclear Techniques, Vol. 34, 2011 1) Dose response of artificial irradiation of fluvial sediment sample for ESR dating, No. 2, p. 95. LIU Chun-ru(State Key Laboratory of Earthquake Dynamics, Institute of Geology; China Earthquake Administration), et al., LIN Min 2) Determination of γ emission probability of 123Xe, No. 5, p. 362. HE Xiao-bing(Northwest Institute of Nuclear Technology), et al., YU Wei-xiang 3) Effect of dose and DNA concentration on DNA damage induced by protons, No. 6, p. 447. SUI Li, WANG Xiao, NI Mei-nan, KONG Fu-quan, YANG Lei, LIU Jian-cheng, ZHAO Kui 4) The separation of 89Rb from fission products, No. 7, p. 499. YE Hong-sheng, XU Li-jun, XIA Wen, CHEN Ke-sheng, LIN Min 5) A new method to check the change in α-decay half-life of 210Po in metal at 4.2 K, No. 7, p. 503. HE Xian-wen, JIANG Shan, HE Ming, HE Guo-zhu, DONG Ke-jun, LI Chao-li

29 Academic Periodical of Farm Products Processing, 2011 1) Review for effect of gamma radiation on reduction of mycotoxins in agricultural products, No. 8, p. 142. WANG Xiong, WU Ji-zong, et al.


30 Journal of Astronautic Metrology and Measurement, Vol. 31, 2011 1) Survey on the Monto Carlo calculation of the atmospheric cosmic radiation field, No. 3, p. 50. LI Chun-juan, CHEN Jun, ZHANG Wei-hua

31 Atomic Energy Science and Technology, Vol. 45, 2011 1) Hydrodynamics analysis of inlet in anti-siphon equipment of China Experimental Fast Reactor, No. 1, p. 25. PENG Yan, ZHANG Dong-hui, DING Zhen-xin 2) Analysis of moderator temperature effect for TOPAZ-Ⅱ reactor, No. 1, p. 48. XIE Jia-chun, ZHAO Shou-zhi, SHEN Feng 3) Preparation process of Li4SiO4 Pebbles as tritium breeding materials, No. 1, p. 73.

YIN Bang-yue, NIU Kai 4) Black carbon in airborne particulate matter by means of reflection method, No. 1, p. 102.

QIN Ya-li, ZHANG Hai-qing, ZHANG Gui-ying, NI Bang-fa, WANG Ping-sheng, NIE Peng, HUANG Dong-hui, CHEN Zhe 5) Vacuum suction-impact collection for recovering uranium particles from swipe sample, No. 1, p. 112. WANG Tong-xing, LI Jing-huai, ZHANG Yan, ZHAO Yong-gang, CHANG Zhi-yuan, LI Shao-wei, WANG Fan, SHEN Yan 6) Quest for chiral doublet bands in A～110 mass region, No. 2, p. 129.

HE Chuang-ye, ZHU Li-hua, WU Xiao-guang, WEN Shu-xian, LI Guang-sheng, WANG Zhi-min, LIU Ying, CUI Xing-zhu, ZHANG Zhen-long, MENG Rui, LI Xue-qin, ZHENG Yun, MA Rui-gang, YANG Chun-xiang 7) Preparation of 99Tcm(CO)3-CNRGD and its biologic evaluation, No. 2, p. 134. ZHAI Chuang-yan, HU Ji, CHEN Bao-jun 8) Development and implementation of full-automatic supervision and control programme for CEFR refueling control system, No. 2, p. 141. ZHU Hao, DONG Sheng-guo, et al. 9) Numerical simulation on heat transfer behavior of supercritical water in vertical pipe, No. 2, p. 146. ZHAO Min-fu, ZHANG Guo-xin, CHEN Yu-zhou 10) Calculation on radiation doses to mullet in anatomic model and comparison to unitary model, No. 2, p. 150. LI Jing-jing, LIU Sen-lin, WANG Chun-hong 11) Determination of uranium isotope abundance by fast neutron-induced fission, No. 2, p. 156. QIAO Ya-hua, ZHANG Min, WU Ji-zong, YANG Yi, LIU Shi-long 12) Primary neutronics research on Venus 2# reactor operating in critical mode, No. 2, p. 186. WU Xiao-chun, SHEN Feng, LIU Xing-min, SUN Zhi-yong, KE Guo-tu 13) Fabrication mechanisms of hypostichiometric UO2－x fuel pellets, No. 2, p. 206. YIN Bang-yue, WU Xue-zhi, QU Zhe-hao, NIU Kai 14) Wedge-disturbing effect of segmented gamma scanner, No. 2, p. 211. GAO Qiang, WANG Zhong-qi, WANG Yi-bo, LU Wen-guang 15) Performance testing and primary use of multi-anode gas ionization chamber, No. 2, p. 240. MENG Xian-fang(Beijing Radiation Application Research Center ), et al., LIN Min 16) Measurement of L-Shell X-ray production cross section of Pb by fluorine ion bombardment, No. 3, p. 257. LÜ Niu, CHANG Hong-wei, ZHANG Yan-ping, DU Shu-bin 17) First principles study of rare-gas solids under high compression, No. 3, p. 262.


HE Yi-guang, WANG Zhao, LIANG Jing, GAO Shuang, TIAN Bao-xian, TANG Xiu-zhang 18) Kinetics of reaction between Pu(Ⅳ) and hydroxysemicarbazide in nitric acid solution, No. 3, p. 277. XIAO Song-tao, YE Guo-an, LIU Xie-chun, LUO Fang-xiang, LAN Tian, LI Feng-feng 19) Technologies for minimization of radioactive waste during operating and decommissioning for nuclear facilities, No. 3, p. 293. YUE Wei-hong 20) Principle and application of sub-threshold correcting for sensitivity calibration by single particle, No. 3, p. 351. TAN Xin-jian(Key Laboratory of Particle & Radiation Imaging, Ministry of Education, Department of Engineering Physics, Tsinghua University), et al., RUAN Xi-chao 21) Time resolution research of BaF2 detector used for α particle detection at different temperatures, No. 3, p. 365.

CHEN Xiao-xian, ZHONG Qi-ping, ZHANG Qi-wei, ZHOU Zu-ying, RUAN Xi-chao, HUANG Han-xiong, NIE Yang-bo, LI Yong-ming, QI Bo, WANG Fan 22) Kinetics of reaction between hydroxysemicarbazide and HNO2 in perchloric acid solution, No. 4, p. 402. XIAO Song-tao, YE Guo-an, LIU Xie-chun, LUO Fang-xiang, LI Hui-rong, LI Feng-feng 23) Material recognition by using 252Cf source, No. 4, p. 479. HAO Xin, et al. 24) Systematic test on fast time resolution parallel plate avalanche counter, No. 4, p. 491. CHEN Yu, LI Guang-wu, GU Xian-bao, CHEN Yan-chao 25) Study and application of transmission ionization chamber for monitoring low energy proton beam intensity, No. 4, p. 495. CHEN Yi-zhen, LIN Min, CHEN Ke-sheng, XU Li-jun, XIA Wen, WANG Feng, SONG Min-na 26) Beam test of 10 MeV high intensity cyclotron, No. 5, p 588. LI Zhen-guo, WU Long-cheng, GE Tao, YAO Hong-juan, JI Bin, YIN Zhi-guo, GUAN Feng-ping, HOU Shi-gang, ZHANG Tian-jue, ZHONG Jun-qing, XING Jian-sheng, LÜ Yin-long, PAN Gao-feng 27) Preliminary study of loading patterns optimization without shuffling for equilibrium cycle of China Experimental Fast Reactor, No. 6, p. 705. YANG Xiao-yan, XU Mi, LI Ze-hua 28) Applications of Bragg detector for AMS, No. 6, p. 730. LI Chao-li, WANG Wei, WANG Xiang-gao, HE Ming, WU Shao-yong, DONG Ke-jun, JIANG Shan 29) Adjoint equation of ADS sub-critical reactor, No. 7, p. 775. WANG Su, SHEN Feng 30) Study on triangular wave technique for reactivity measurement, No. 7, p. 801. LIANG Shu-hong, LIU Zhen-hua, YAN Feng-wen 31) Design of magnetic field system for high power irradiation accelerator, No. 7, p. 868. REN Xiu-yan, LÜ Yu-zhu 32) Simulation of cosmic ray muons detecting high-Z materials, No. 7, p. 872. PANG Hong-chao, LIU Sen-lin, WANG Hong-yan, XU Yong-jun, YANG Hong-wei, WANG Lie-min 33) 〈110〉 tilt grain boundaries in BCC Fe studied by molecular dynamics, No. 8, p. 902. HE Xin-fu, YANG Wen 34) Progress of apoptosis imaging using Annexin Ⅴ labeled with positron radionuclides, No. 8, p. 908.


GUO Fei-hu, CHEN Da-ming, LIU Zhuo, WEN Kai, DU Jin 35) Precise determination of uranium by extraction spectrophotometry, No. 8, p. 915. ZHU Hai-qiao, WU Ji-zong, LUO Zhong-yan 36) Numerical simulation of thermal-hydraulic analysis for triplex horizontal thermal-shielding in CEFR, No. 8, p. 925. LÜ Chuan-feng, ZHANG Dong-hui, QIAO Xue-dong, WU Chun-liang 37) Peak efficiency calibration of HPGe detectors for volume sources based on virtual point detector model, No. 8, p. 999. XIONG Wen-bin, QIU Chun-hua, DUAN Tian-ying, LIU Hao-jie, PAN Jun-yan, CHEN Hai-tao 38) Analysis of single uranium particle by FT-TIMS, No. 9, p. 1 031. CHEN Yan, SHEN Yan, CHANG Zhi-yuan, ZHAO Yong-gang 39) Interface microstructure of welding-brazed joint between Nb-1Zr alloy and 304 stainless steel, No. 9, p. 1 100. LI Xin, ZHAO Jun, ZHENG Jian-ping 40) Retrieval and conditioning of high level radioactive solid waste from pit-type storage facilities, No. 10, p. 1 181. ZHANG Cun-ping, LI Mei-shan, JI Yong-hong, CHU Li-li, LIU Chun-xiu, YE Guo-an 41) Application of Monte Carlo method in calibration technology of proton absorbed dose, No. 10, p. 1 270. WANG Feng, LIN Min, XU Li-jun, CHEN Yi-zhen, CUI Ying, XIA Wen, CHEN Ke-sheng, LI Hua-zhi, YE Hong-sheng 42) Point kinetic equation of ADS sub-critical reactor, No. 11, p. 1 300. SHEN Feng, WANG Su 43) Experimental measurement of zero power reactor transfer function, No. 11, p. 1 305. LIANG Shu-hong 44) Preparation and anti-infrared property of CR-39 modified with nuclear tracks and silver nano-particles, No. 11, p. 1 377. LIU Cun-xiong, HU Lian, NI Bang-fa, TIAN Wei-zhi, FAN Qi-wen, XIAO Cai-jin, NIE Peng,

WANG Ping-sheng, ZHANG Gui-ying, HUANG Dong-hui 45) Current and voltage measurements of LightⅡ-B pulsed power generator, No. 12, p. 1 502. ZOU Jian, ZENG Nai-gong, WANG Chuan, ZHANG Tian-jue, JIANG Xing-dong

32 China Railway Science, Vol. 32, 2011 1) A new method for calculating the lightning parameter of catenary, No. 4, p. 76. LIU Jing, et al.

33 Cryogenics & Superconductivity, Vol. 39, 2011 1) The development of cryostat for superconducting linear accelerator, No. 8, p. 1. ZHANG Xuehua(The 16th Institute of CETC), et al., LIU Bao-qing, ZHOU Li-peng, PENG Zhao-hua, ZHENG Jian, LU Zhao

34 Radiation Protection, Vol. 31, 2011 1) Simulation study for cosmic ray muons to detecte fissile nuclear materials, No. 2, p. 72. PANG Hong-chao, LIU Sen-lin, WANG Hong-yan, YANG Hong-wei 2) Study on long-term alteration behavior of the simulated HLW glass in the low-oxygen underground


water, No. 2, p. 76. GAN Xue-ying, ZHANG Zhen-tao, WANG Lei, XIN Hai-qing, BAI Yang, MA Hui 3) Studies of Tc oxidation states in humic acid solutions, No. 4, p. 215. WANG Bo, LIU De-jun, YAO Jun, CHEN Xi, JIANG Tao, GUAN Hong-zhi, SONG Zhi-xin, BAO Liang-jin, ZHANG Yan, ZHOU Duo, LONG Hao-qi, FAN Xian-hua 4) Dose-effect relationship of micronuclei established with human peripheral blood lymphocytes after different LET low dose irradiation, No. 4, p. 229. WANG Chuan-gao, WANG Zhong-wen 5) Environmental issues in construction of inland nuclear power plants in China, No. 5, p. 257. LIU Yong-ye, LIU Sen-lin 6) Enhanced natural radiation exposure enhanced by human activity—The largest contributor to the Chinese population dose, No. 6, p. 323. PAN Zi-qiang(Science and Technology Commission, China National Nuclear Corporation), LIU Yan-yang 7) Investigation of radiological environment impact from exploitation of Bayan Obo mine, No. 6, p. 364. WU Qi-fan(Department of Engineering Physics of Tsinghua University), et al., WANG Hong-yan

35 Nuclear Safety, 2011 1) On the decommissioning strategies, No. 1, p. 13. LUO Shang-geng 2) New method of safety assessment for pressure vessel of nuclear power plant-brief introduction of master curve approach, No. 2, p. 7. YANG Wen-dou

36 Nuclear Physics Review, Vol. 28, 2011 1) Modification of dipole homogeneity field, No. 1, p. 55. TANG Bing, CUI Bao-qun, MA Rui-gang, JIANG Chong, MA Ying-jun, CHEN Li-hua, JIANG Wei-sheng 2) Accelerator mass spectrometry measurement of 53Mn and its applications in earth sciences, No. 1, p. 78.

DONG Ke-jun, HE Ming, LI Chao-li, YOU Qu-bo, LIU Jian-cheng, WU Shao-yong, WANG Xiang-gao, SHEN Hong-tao, LI Zhen-yu, LI Shi-zhuo, GONG Jie, ZHANG Wei, HE Guo-zhu, HE Xian-wen, JIN Chun-sheng, WANG Wei, YUAN Jian, JIANG Shan 3) Dynamics of heavy ion collisions within a large energy regime, No. 2, p. 142. LI Qing-feng(School of Science, Huzhou Teachers College), LI Zhu-xia 4) Calibration of LS301 fast-neutron detector efficiency, No. 2, p. 195. ZHANG Wen-hui, LI Guang-wu, ZHANG Gang, CHEN Yu, YAN Guo-hong 5) X-ray radiation in interaction of ultra-short and ultra-intense laser-pulse with Mo target, No. 2, p. 241. XU Qiu-mei(Institute of Modern Physics, Chinese Academy of Sciences), et al., DU Shu-bin 6) Measurement of excitation function at zero degree for 15N(p, n) 15O reaction neutron source, No. 2, p. 251. QI Bo, RUAN Xi-chao, CHEN Guo-chang, HUANG Han-xiong, ZHOU Bin, MA Zhong-yuan, ZHONG Qi-ping, NIE Yang-bo, ZHOU Zu-ying 7) Measurement of secondary neutron emission double-differential cross section for 9Be induced by 8.19 MeV neutrons, No. 3, p. 366. ZHANG Ya-ling, RUAN Xi-chao, HUANG Han-xiong, LI Xia, ZHOU Zu-ying, TANG Hong-qing,


NIE Yang-bo, BAO Jie 8) Extracting the symmetry energy information with heavy ion collisions, No. 4, p. 377. ZHANG Ying-xun, LU Xiao-hua, ZHAO Kai, LI Zhu-xia

37 Nuclear Electronics & Detection Technology，Vol. 31, 2011 1) Introduction for method of nondestructive burnup measurement, No. 2, p. 148. YANG Li-jun 2) Development of quasi macroscopic neutron noise measurement and analysis system, No. 7, p. 732. ZHANG Wei, ZHU Qing-fu, LUO Huang-da, SHI Yong-qian, LUO Zhang-lin 3) Study of 4π spherical 3He neutron detector design, No. 7, p. 747. YANG Qiao-rong, JIANG Li-yang, YU Wei-xiang 4) Application of gray relational cluster method in muon tomography, No. 8, p. 871. WANG Yue(Department of Automation of University of Science and Technology of China), et al., WAGN Hong-yan, YANG Hong-wei 5) Muon tomography algorithms for fissile nuclear materials detection, No. 8, p. 874. WANG Lie-ming, WANG Hong-yan, LIU Zhi-ying, YANG Hong-wei, PANG Hong-chao 6) Observation methods of CR-39 solid state nuclear track detectors, No. 9, p. 1 008. HUANG San-bo(Collage of Astronautics, Nanjing University of Aeronautics and Astronautics), et al., LI Guang-wu, GUO Gang 7) A project to determine the radiation dose of irradiation electron linac, No. 9, p. 1 035. GUO Xiong-bin(Institute of Energy and Nuclear Technique Applications of Zhejiang Province Hangzhou), et al., WANG Hong-yan

38 Radiation Protection Bulletin,Vol. 31, 2011 1) Exposure of public and carers to medical 131I in China YANG Duan-jie(Nuclear and Radiation Safety Centre of Ministry of Environmental Protection), et al., ZHANG Hai-xia 2) Analysis of differential gene expression profile induced by ionizing radiation in the progeny of normal human liver cells, No. 2, p. 6. ZUO Ya-hui(China Institute for Radiation Protection), et al., WANG Zhong-wen 3) Doses to the public from radioactive effluents released from nuclear power plants on China mainland, No. 3, p. 1. CHEN Xiao-qiu(Nuclear and Radiation Safety Center, MEP), et al., JIAO Zhi-juan 4) Preliminary design of radioactive waste minimization management system, No. 6, p. 12. ZHAO Min-yang(School of Computer Science and Technology, University of South China), et al., YUE Feng, XU Yong-jun 5) Application of hemisphere CdZnTe gamma spectrometer for measurement of “hotspot” during nuclear decommissioning, No. 6, p. 16. LIU Rui-rui, XIAO Xue-fu, HAN Yong-chao, XIAO Wen-hui 6) Lessons learned from two events of source trouble in irradiation units, No. 6, p. 24. XIAO Xue-fu

39 Acta Metallurgica Sinica, Vol. 47, 2011 1) Molecular dynamics simulation of matrix radiation damage in Fe-Cu alloy, No. 7, p. 954. HE Xin-fu, YANG Peng, YANG Wen


2) Effects of radiation and He on microstruc-tures of low active ferritic/martensitic steel F82H, No. 9, p. 965. TONG Zhen-feng, YANG Wen, YANG Qi-fa 3) Small punch testing of the effect of irradiation on mechanical property of RPV steel, No. 9, p. 1 205.

ZHONG Wei-hua, TONG Zhen-feng, ZHANG Chang-yi, QIAO Jian-sheng, YANG Wen

40 Explosive Materials, 2011 1) Review on detection technology for explosives, No. 5, p. 33.

DING Wen(School of Chemical Engineering, Nanjing University of Science and Technology), DOU Yu-ling, WANG Guo-bao

41 Development and Application of Materials, Vol. 26, 2011 1) Preparation and properties of platinum electrode used in oxygen sensor for automobile, No. 5, p. 45. ZHOU Xin-yan, XIANG Lan-xiang, SHA Shun-ping, LU Sheng-hui, ZHAO Lu

42 Journal of Jilin University: Earth Science Edition, Vol. 41, 2011 1) Grain size analysis and 36Cl dating of early pleistocene sediments of Dunhuang basin, tectonic uplift implication, No. 5, p. 1 380.

REN Shou-mai(Strategic Research Center of Oil & Gas Resources, Ministry of Land & Resources) et al., HE Ming

43 Journal of Nuclear and Radiochemistry, Vol. 33, 2011 1) Kinetics of reaction between methylhydrazine and neptunium(Ⅴ), No. 1, p. 1. LI Xiao-gai, HE Hui, YE Guo-an, TANG Hong-bin, JIANG De-xiang, LI Bin 2) Analysis of radiolytic products of TBP extraction system, No. 1, p. 12. SONG Feng-li, LI Jin-ying, ZHOU Chang-xin, LI Hui-bo, SU Zhe, WANG Xiao-rong, LIN Can-sheng 3) Effect of temperature on sorption of Np(Ⅳ)/ Np(Ⅴ) on beishan granite, No. 1. p. 25. JIANG Tao, YAO Jun, ZHOU Duo, BAO Liang-jin, ZHANG Yan, CHEN Xi, FAN Xian-hua 4) Solubility of Np(Ⅳ) in beishan groundwater at different temperatures, No. 2, p. 78. JIANG Tao, YAO Jun, WANG Bo, GUAN Hong-zhi, LONG Hao-qi, SONG Zhi-xin, SU Xi-guang 5) Colloidal behavior of americium, No. 2, p. 85. GUAN Hong-zhi, ZHOU Duo, LONG Hao-qi, YAO Jun, WANG Bo, JIANG Tao, SONG Zhi-xin 6) Simultaneous determination of uranium, nitric acid and nitrous acid by direct spectrophotometry, No. 2, p. 89. LI Li, ZHANG Hu, YE Guo-an, SUN Bin 7) Electrochemical behavior of uranium(Ⅵ) in 1-butyl-3-methylimidazolium chloride, No. 2, p. 101. ZHANG Qiu-yue, HUANG Xiao-hong, TANG Hong-bin, HE Hui 8) Sorption and diffusion on technetium in the bentonite from gaomiaozi, No. 2, p. 124. ZHANG Yan, SONG Zhi-xin, BAO Liang-jin, YAO Jun, JIANG Tao, LONG Hao-qi, WANG Bo,

CHEN Xi, SU Xi-guang 9) Retention of nitrato complexes of nitrosylruthenium by radiolyzed TBP-n-dodecane-HNO3, No. 3, p. 148. SONG Feng-li, SU Zhe, LI Hui-bo, WANG Xiao-rong, LIN Can-sheng 10) CECE process on liquid catalytic isotopic exchange of H2O-H2, No. 3, p. 156. RUAN Hao, HU Shi-lin, ZHANG Li, DOU Qin-cheng 11) Some considerations on the construction of a spent nuclear fuel reprocessing plant in China, No. 4, p. 204 LI Jin-ying, SHI Lei 12) Main Ru-retaining complexing agents produced by radiolysis, No. 4, p. 211. SONG Feng-li, LI Jin-ying, SU Zhe, LI Hui-bo, WANG Xiao-rong, LIN Can-sheng


13) Influence of pretreatment on the stability of Np(Ⅴ), No. 4, p. 220. BIAN Xiao-yan, ZHOU Yi-ping, ZHENG Wei-fang, ZHANG Bai-qing, YAN Tai-hong, ZUO Chen, ZHANG Yu 14) Coordination and redox reaction of dihydroxyurea with Fe(Ⅲ), No. 4, p. 224.

YAN Tai-hong, ZHANG Bai-qing, ZHENG Wei-fang, ZHANG Hu, ZUO Chen, ZHANG Yu, XIAN Liang, BIAN Xiao-yan, LI Chuan-bo 15) Preparation of SnO2 used as absorbent of 68Ge-68Ga generator, No. 4, p. 240. FU Hong-yu, LUO Wen-bo, SHEN Yi-jia, LI Jiang-hang, LI Jin-fu, ZHANG Jun-li, WANG Gang 16) Analyzing method of N, N-dimethylhydroxylamine and methylhydrazine in Purex process, No. 5, p. 268. LI Chuan-bo, LIU Jin-ping, YAN Tai-hong, ZHANG YU, ZHENG Wei-fang 17) Pulse radiolysis of aqueous methylhydrazine solutions, No. 5, p. 274. CHEN Hui, HE Hui, YE Guo-an 18) Application of purified and carboxylic multi-walled carbon nanotubes for uranium(Ⅵ) Ions adsorptive removal from aqueous solution, No. 5, p. 285. LIU Shu-juan, LI Jin-ying 19) Measurement of mercury in reprocessing process, No. 5, p. 318. SU Yu-lan, ZHAO Li-fei, YING Zhe-cong, WU Ji-zong 20) Extraction of alkali earth metal ions from aqueous nitric acid solutions with TODGA-DHOA in n-dodecane, No. 6, p. 328. ZHU Wen-bin, YE Guo-an, LI Feng-feng, JIANG De-xiang, LI Hui-rong 21) Hydraulic performance of φ20 mm centrifugal extractor, No. 6, p. 349. LI Chuan-bo, ZHANG Yu ,YAN Tai-hong, ZHENG Wei-fang, ZUO Chen, YUAN Zhong-wei

44 Chinese General Practice, Vol. 14, 2011 1) The short-term therapeutic effect of 131I in the treatment of 199 patients with graves disease, No. 5, p. 545. LIU Hai-chun, CHEN Yang, LI Dong-wei, ZHENG Yu

45 Chinese Journal of Difficult and Complicated Cases, Vol. 10, 2011 1) The effects of low dose atorvastatin on blood lipids and high sensitive C-reactive protein in patients with obesity and metabolic syndrome, No. 2, p. 94. MEI Rui

46 China Medical Herald, Vol. 10, 2011 1) The observation to stability of the gingival papilla between the implants which remolded by replanting bones, No. 17 p. 59. ZHU Xiuying, LIANG Li-shan

47 Chinese Journal of Difficult and Complicated Cases, Vol. 11, 2011 1) Experience of hypophysoma resection through single nostril-sphenoid sinus approach, No. 8, p. 1 542. ZHANG Shu-guang, PANG Hua, CHEN Wu

48 Nondestructive Testing, Vol. 11, 2011 1) Neutron reflectometry and its application in corrosion science, No. 11, p. 60. LI Tian-fu, LIU Yun-tao, CHEN Dong-feng, LI Jun-hong, GAO Jian-bo, HAN Wen-ze, HU Rui, LIU Rong-deng


List of Lectures in International Meetings in 2011

No. Report title Meeting title Time and place Reporter 1 近畿大学反应堆应用合作研究

过程报告书 2010 年度 IC の放射性廃棄物管理への

適用に向けた光子、中性子に

対する耐性評価に関する研

究

WANG Shao-lin

2 The 3rd Asian Conference on Molten Salts and Ion Liquids

Cathodic Process of Ce(Ⅲ) in LiF-CaF2 Media

Jan., Harbin, China

LIN Ru-shan

3 The 3rd Asian Conference on Molten Salts and Ion Liquids

Electrochemical Behavior of Ce(Ⅲ) in LiF-BaF2 Melts

Jan., Harbin, China

LIN Ru-shan

4 The Collaboration Laboratory Seminar on Materials Ageing and Lifetime Management of PWR

Radiation Effects Research on RPV Steels in CIAE

Mar., 1-3, Wuhan, China

TONG Zhen-feng

5 The 5th Int. Sym. SCWR (ISSCWR-5)

An Experimental Study of Critical Heat Flux in a Tube for Near-Critical Pressure

Mar., 13-16, Vanconver, Canada

CHEN Yu-zhou

6 Recent Progresses in Complex Network Research Mini- Workshop

A Framework of Non-equilibrium and Equilibrium Statistical Ensemble Formalism for Complex Systems

Mar.,14-18, Beijing, China

FANG Jin-qing

7 13th International Conference on Modern Trends in Activation Analysis

The Study on Sampling Behavior of Multielement in New Stream Sediment Material by Using Nuclear Analytical Methods

Mar.,16, University of Texas A&M, USA

XIAO Cai-jin

8 13th International Conference on Modern Trends in Activation Analysis

A Brief Introduction to NAA Facilities of China advance Research Reactor at CIAE

Mar.,16, University of Texas A&M, USA

NI Bang-fa

9 IAEA/RCA Final Progress Review Meeting, IAEA/RCA/ RAS7015, Country Report

Mar., 16, IAEA

LIU Cun-xiong

10 The 12th International Conference on Accelerator Mass Spectrometry

Major Programs of AMS at the CIAE in Recent 12 Years

Mar., 19-26, New Zealand

JIANG Shan


Progress in Measurement of 182Hf With AMS at CIAE


HE Ming


An Absolute AMS Method for Determination of 79Se Half-Life


HE Ming

APPENDIX·List of Lectures in International Meetings in 2011 273

13 Central Nuclear Fission Cooperation in the Third Workshop

ADS Study in China Mar., 21-25, Beijing, China

XIA Hai-hong

14 The Dark Matter Seminar Nuclear Recoil Quenching Factor Measurement for HPGe Detector

Mar., 23-30, Beijing, China

RUAN Xi-chao

15 International Radiation Advisory Committee Nineteenth Meeting of Third Division

Neutron Metrology Activities at the CIAE

Mar., France CHEN Jun

16 "Nuclear Structure and Decay Data Evaluation of International Cooperation Network" Technology Conference

The Progress of Researches on ADS in China

Apr., 2-8, USA XIA Hai-hong

17 The 19th IAEA Technical Meeting on the "Co-ordination of the International Network of Nuclear Structure and Decay Data (NSDD) Evaluators"

Status Report of the Nuclear Structure and Decay Data Evaluation in China

Apr., 4-8, Vienna

HUANG Xiao-long

18 TA&M-Commerce, Annual Research Symposium

Neutron-Proton Pairing and Symmetry Energy

Apr., 7, USA TIAN Yuan

19 High Energy Physics and Related Areas in the Workshop

Connection of the Hydrodynamics and Transport Model

Apr., 22-27, Wuhan, China

XU Xin-xing

20 The 3rd ANPhA Symposium The progress of Researches on ADS in CIAE

Apr., 29-30, Lanzhou, China

XIA Hai-hong

21 5th International Conference (FUSION11)

Fusion-Fission and Quasi- Fission Competition in the 32S+184W Reaction

May, 2-6, France

ZHANG Huan-qiao

22 5th International Conference (FUSION11)

Nuclear Reactions Studied by Quasi-elastic Measurements With High Precision at Backward Angles

May, 2-6, France

LIN Cheng-jian

23 Technical Meeting of the WPEC Subgroup 33 on "Methods and Issues for the Combined Use of Integral"

Current Status of CIAE Activities on Nuclear Data Adjustment

May, 10-11, France

WU Hai-cheng

24 2011 NEA/WPEC Meeting Progress Report on Experimental Activities of Nuclear Data in China

May, 10-11, France

GE Zhi-gang

25 Technical Meeting on the International Network of Nuclear Reaction Data Centers,

2010/11 Status Report May, 23, Vienna

GE Zhi-gang

26 Advances in Radioactive Isotope Science (ARIS2001)

Recent Experimental Results of Two-Proton Correlated Emis-

May, 29-Jun., 3, Belgium

LIN Cheng-jian


sion From the Excited States of 17,18Ne and 28,29S

27 Advances in Radioactive Isotope Science (ARIS2001)

Experimental Study of two-Alpha Emission From High-Lying Excited States of 17,18Ne by Complete- Kinematics Measurements

May, 29-Jun., 3, Belgium

XU Xin-xing

28 Proton-Emitting Nuclei and Related Topics PROCON 2011

Recent Experimental Results of Two-Proton Correlated Emis- sion From the excited States of 17,18Ne and 28,29S

Jun., 6-10, France

LIN Cheng-jian

29 Proton-emitting Nuclei and Related Topics PROCON 2011

Experimental Study of Two-alpha Emission from High-lying Excited States of 17,18Ne

Jun., 6-10, France

XU Xin-xing

30 Review Meeting on CRIB Activities

Elastic Scattering of 17F on 12C target at 60 MeV

Jun., 21, Japan ZHANG Huan-qiao

31 56th Health Physics Society Annual Meeting

The Research on Low Altitude Measurement Technique for Nuclear Terrorism Emergency Case Study on the Detection of Radiological Dispersal Device

Jun., 25, USA LIU Rui-rui

32 ISORD-6 The Internal Radiation Measurement Technology Based on the CZT Detector Array

July, 12-14, Malaysia

QU Yan-tao

33 Particle Analysis of Environmental Samples for Safeguards

Study on Analyzing of Single Uranium Particle by FT-TIMS

July, Vienna CHEN Yan

34 Particle Analysis of Environmental Samples for Safeguards

Test Samples Analysis July, Vienna WANG Tong-xing

35 Technical meeting on radiation induced defects in semiconductors and insulators

Defects Induced by Heavy-ion and Fast Neutron Irradiation in GaAs

July, Vienna ZUO Yi

36 Third Workshop on Hadron Physics in China and Opportunities in USA

The Progress of PHENIX RPC Production in China

Aug., 8-11, Weihai, China

HU Shou-yang


The Work of GEM foil at CIAE Aug., 8-11, Weihai, China

YE Li


GEM In-Beam Test at JLab Aug., 8-11, Weihai, China

BAI Zhan-xin



Heavy Ion Reactions Around the Coulomb Barrier

Aug., 8-11, Weihai, China

ZHANG Huan-qiao

40 International Summer School on Subatomic Physics: The 6th course: New Frontiers of Nuclear Physics ISSSP2011

Experimental Progress in Two-Proton Correlated Emission

Aug., 27-31, Beijing, China

LIN Cheng-jian

41 7th ANL/INT/JINA/MSU annual FRIB workshop

Extracting the Symmetry Energy Information With Transport Model

Aug., 12 ZHANG Ying-xun

42 The 2nd Asian Nuclear Reaction Database Development Workshop

Neutron Nuclear Data Evaluation of Actinide Nuclei for CENDL-3.1

Sep., 5-9, Beijing, China

CHEN Guo-chang


Systematics of (n, 2n) Reaction Excitation Function


WANG Ji-min


Systematics of (n, g) Reaction Excitation Function


TAO Xi


The Secondary Neutron Emission Double-Differential Cross Section Measurements at CIAE


RUAN Xi-chao


Nuclear Data Activities at CIAE


GE Zhi-gang

47 The 4th International Conference on the Chemical and Physics of the of Transactinide Elements

Search for the Super Heavy Element in Nature With AMS

Sep., 5-12, Russia

JIANG Shan

48 IAEA Technical Meeting on "Inelastic Scattering and Capture Cross-Section Data of Major Actinides in the Fast Neutron Region"

The Theoretical Calculation of n+232Th, 233,235,238U, 239Pu Reactions

Sep., 6-9, Vienna

HAN Yin-lu

49 Particle and Nuclear Astrophysics, International Workshop on Nuclear Physics, 32nd Course

Constraints on the Density Dependence of the Symmetry Energy From Heavy-Ion Collisions

Sep., 16-24, Italy

ZHANG Y X

50 The 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14)

An Experimental Study of Critical Heat Flux in a Tube for Near-Critical Pressure

Sep., 25-29, Canada

CHEN Yu-zhou

51 2011 Fall Joint Meeting Texas Section of APS and AAPT and

Neutron-Proton Pairing and Symmetry Energy in Nuclear

Oct., 7, USA TIAN Yuan


Zone 13 SPS matter 52 The Fifth China-Korea

Workshop on Nuclear Reactor Thermal Hydraulics

Recent Progress on Research of Thermal-Hydraulics for SCWR in CIAE

Oct., 10-12, Sichuan, China

CHEN Yu-zhou

53 The Fifth China-Korea Workshop on Nuclear Reactor Thermal Hydraulics

The Numerical Simulation of the Characteristics of Three-Dimensional Vortex Shedding of a Cylinder Fixed at on End


ZHAO Min-fu, DUAN

Ming-hui

54 The Fifth China-Korea Workshop on Nuclear Reactor Thermal Hydraulics

Effect of Entrance and Aspect Ratio on Rectangular Micro-channel Flow and Heat Transfer


LÜ Yu-feng

55 IAEA–Technical Meeting on Research Reactor Ageing, Modernization, & Refurbishment

Ageing Management of New Research Reactor—CARR (China Advanced Research Reactor)

Oct., 10-14 HUA Xiao

56 ICFRM-15 Interstitial Helium Diffusion Mechanisms in <110> Tilt Grain Boundaries in BCC FeCr Alloys: An Atomistic Study

Oct., 16-22, USA

HE Xin-fu

57 ICFRM-15 Small Punch Test Technology for Irradiated Specimens in CIAE

Oct., 16-22, USA

ZHONG Wei-hua

58 ICFRM-15 Recent Progress in R&D on the In-Pile Irradiation and Tritium In-Situ Extraction experiment for the HCCB Pebble Bed in CARR

Oct., 16-22, USA

YANG Qi-fa, YANG Hong-guang

59 ICFRM-15 Characteristics of the Hydrogen Isotopes Absorption & Adsorption by La-Ni-Al Tritium Storage Materials

Oct., 16-22, USA

YANG Hong-guan

60 ICFRM-15 Characterization of the Alumina Film with Doped Cerium on the Iron-Aluminide Diffusion Coating

Oct., 16-22, USA

ZHAN Qin

61 ICFRM-15 Absorption Kinetics of Hydrogen Isotope for ZrCo

Oct., 16-22, USA

SONG Ying-ming

62 5th-IAASS Launch Vehicle Fire Accident Preliminary Analysis of A Liquid-Metal Cooled Thermionic Nuclear Reactor: TOPAZ-Ⅱ

Oct., 18, France

HU Gu


63 Nuclear Physics Symposium in China and Canada

Spectroscopic Setups Related to Experiments With n-rich Beams

Oct., 20-22, Beijing, China

WANG You-bao

64 Technical Meeting on Long-term Needs for Nuclear Data Development

Parameter Libraries for Nuclear Data Model Calculations

Nov., 2-4, Vienna

GE Zhi-gang

65 International conference on safe management and effective application of RR

Operation Management and Effective Application of CARR

Nov., 14-18 DING Li

66 The Material Origin and Evolution of Galaxies International Seminar

Indirect Measurements of Reactions in the Hot p-p Chain and CNO Cycle

Nov., 14-17, Japan

WANG You-bao

67 1st Asia-Oceania Conference on Neutron Scattering

Current Status and Future Development of a Chinese National Neutron Facility- Science and User Support at CARR

Nov., 20-24, TSUKUBA, Japan

CHEN Dong-feng


The Current Status and Future Plan of Engineer Instruments At CARR


LIU Yun-tao


An Introducation of a Thermal Neutron Triple-Axis Spectrometer at CARR


HAO Li-jie


RSD and TD in CARR Nov., 20-24, TSUKUBA, Japan

LI Jun-hong


Thermal and Cold Neutron Radiography at CARR


WU Mei-mei

72 2011 FNCA Workshop on Neutron Activation Analysis

Country Report Nov., 21-24, 2011, Australia

NI Bang-fa

73 2011 FNCA Workshop on Neutron Activation Analysis

U, Th and K Measurement Using Neutron Activation Analysis

Nov., 21-24, 2011, Australia

NI Bang-fa

74 2011 Pacific-Rim: Laser Damage Optical Materials for High Power Lasers

Investigation of Optical Surfacer Damage With Laser Induced Fluorescence Microscopy

Nov., Shanghai, China

GAO Zhi-xing

75 Second Neutron Spectrum Technology Conference

The Calculation of 235U+n Energy Spectrum

Dec., 12-16，IAEA

SHU Neng-chuan,

CHEN Yong-jing

76 AFR Workshop on Non-proliferation Nuclear Forensics

Activities Related to Nuclear Forensics in China

Dec., Bangkok ZHAO Yong-gang


77 Global 2011 Adjustment of Valence State of Pu and Np in Nitric Solution Containing DMHAN and MMH

Dec., Japan ZHANG Hu

78 Global 2011 Kinetics of Reaction Between Actic Acid and Ag2+ in Nitric Acid Medium

Dec., Japan LI Gao-liang

79 The 9th International Workshop on Asian Network for ADS and Nuclear Transmutation Technology

Investgation on One-Way Coupling Venus-1 Based MCNP Code

Dec., 6, Hengyang, China

WU Xiao-bo

80 The 9th International Workshop on Asian Network for ADS and Nuclear Transmutation Technology

Fission Rate Distribution Research for ADS Sub-critical Assembly ‘Venus-1’

Dec., 6, Hengyang, China

WANG Fan, ZHU

Qing-fu, SHI Yong-qian

81 Institute of Physical and Chemical Research of Large EURICA Device Workshop

Collective Properties of Neutron-Rich Pd and Cd Isotopes

Dec., 14, Beijing, China

WANG You-bao

82 The 4th East-Asia AMS Conference

Status report of AMS System at CIAE

Dec., 15-19, Japan

HE Ming

83 The 4th East-Asia AMS Conference

Development of 53Mn AMS Measurement Method at CIAE

Dec., 15-19, Japan

DONG Ke-jun

84 2011 JEFF Meeting Introduction of Nuclear Data Activities in China

GE Zhi-gang

85 2011 International Conference on Electrical Machines and Systems

Efficiency optimization of induction motors using genetic algorithm and hybrid genetic algorithm

TAI Yong

86 2011 International Conference on Electrical Machines and Systems

Efficiency improvement measures analysis of induction motors

TAI Yong

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