Atomic Energy Science and Technology 2013 Issue z1 Preliminary Analysis on In-core Fuel Management Optimization of Molten Salt Pebble-Bed Reactor

Preliminary Analysis on In-core Fuel Management Optimization of Molten Salt Pebble-Bed Reactor
XIA Bing;LV Ying-zhong;JING Xing-qing;XU Xiao-lin

..............page:150-155

Demonstration Test of Recycled Uranium Reprocessed From PWR Spent Fuel in CANDU Reactor
FAN Shen;MENG Zhi-liang;CHEN Ming-jun;QIAO Gang

..............page:128-131

Preliminary Conceptual Design of Accelerator Driven Sub-critical System
LI Xun-zhao;WU Hong-chun;CAO Liang-zhi;ZHENG You-qi

..............page:224-228

Overview of On-line Core Monitoring System BEACON
DAI Qing;CHEN Xiao-song

..............page:99-102

Consideration in Criticality Safety Evaluation of Transport Package
YI Xuan;HUO Xiao-dong

..............page:309-311

Neutronic Behavior Analysis on Natural Uranium Equivalent Fuel
WEI Yan-qin;WANG Lian-jie;ZHENG Ji-ye;HUANG Shi-en;LI Qing

..............page:137-143

Development of Self-Reliant Three-Dimensional Core Nuclear Design Code COCO
LU Hao-liang;MO Kun;LI Wen-huai;LI Jing-gang

..............page:327-330

Experimental Rersearch of Nuclear Reaction Rate in China Experimental Fast Reactor
fan zhen dong ; chen xiao liang ; hu ding sheng ; chen xiao xian ; cao pan ; chen yi zuo ; hu zuo ; xu li ; zhang jian

..............page:107-110

Measurement and Analysis of CEFR Assembly Exchanging Reactivity Worth
zhou ke yuan ; yu hong ; cao pan ; yang xiao yan ; chen yi zuo ; zhang jian ; hu zuo ; zhao yu sen

..............page:75-78

Two-Dimensional Radiation Shielding Optimization Analysis of Spent Fuel Transport Container
TIAN Ying-nan;CHEN Yi-xue;YANG Shou-hai

..............page:176-178

Development and Preliminary Verification of Core Physics Analysis Code CORE of COSINE Code Package
chen yi xue ; liu zhan quan ; hu xiao yu ; wang su ; wang chang hui ; quan guo ping ; an wei jian ; shen feng

..............page:365-368

Measurement of Regulation Control Rod Value of China Experimental Fast Reactor
YANG Yong;XU Li;GANG Zhi;FAN Zhen-dong;CHEN Xiao-xian;ZHANG Qiang;TIAN He-chun

..............page:56-57

Loading Scheme Research on the First Criticality of China Experimental Fast Reactor
yang xiao yan ; yu hong ; gang zhi ; zhou ke yuan ; zhao jin kun ; chen yi zuo ; hu zuo ; tian he chun ; li ze hua

..............page:58-61

Development and Validation of Library MUSE-F1.0
TANG Hai-bo;CHEN Yi-xue;WU Jun

..............page:342-345

Research of Calculation Method of Assembly Equivalence With Boundary Flow Response Matrix
LIU Zhi hong;LIU Zhao-yuan;PENG Liang-hui;ZHAO Jing;ZHANG Jian

..............page:5-8

Method Study on Calculating Fuel Element Failures by Delayed Neutrons
XU Zhi-long;LIU Xing-min;LIU Yong-jin;CHANG Meng;SUN Wei;LI Chun

..............page:168-171

Research on Application of Burnable Poison in Pebble Bed HTR
WEI Chun-lin;ZHANG Jian;SHAN Wen-zhi;JING Xing-qing

..............page:156-159

Measurement of Nuclear Power Heating Starting Point in China Experimental Fast Reactor
ZHANG Jian;ZHAO Jin-kun;YANG Yong;CHEN Xiao-xian;CAO Pan;TIAN He-chun

..............page:95-98

Developing and Coupling of Steady State Two-Phase Thermal-Hydraulic Solver PATHS for PARCS
LI Lin-sen;WANG Kan;Benjamin Collins;XU Yun-lin;Thomas Downar

..............page:295-298

Preliminary Analysis of Different Driver Fuels in Thorium-Based Prismatic GT-MHR
ZHENG Yun-tao;DING Ming;ZHANG Liang;WANG Li-dong;CAO Xia-xin

..............page:216-219

Research and Validation on Two-Dimensional Transport-Depletion Program
HU Xiao-li;CHEN Yi-xue;YANG Shou-hai;WU Jun

..............page:360-364

Analysis of In-vessel Core Catcher Influencing on Neutron Irradiation of Pressure Vessel
XU Hong;YIN Zhi-tao;GANG Zhi;ZHOU Zhi-wei

..............page:234-238

Sensitivity Study of Feedback Parameters for Thermal-Hydraulic Coupling Code
WANG Cong;CAN Xin-rong

..............page:283-286

Comparison and Performance Analysis of Microscopic Depletion Equation Solving Method
BEI Hua;ZHANG Jing-yu;CHEN Qi-chang;SI Sheng-yi

..............page:335-337

Benchmark Verification of DRAGON for Neutrino Experiment
WANG Long-ze;MA Xu-bo;CHEN Yi-xue;CAO Jun;AN Feng-peng

..............page:83-87

Sensitivity and Uncertainty Analysis of Calculated keff on Benchmark Models due to Uncertainties of Nuclear Data
HU Ze-hua;WANG Jia;SUN Wei-li;LI Mao-sheng

..............page:312-317

Study on Production of 14C in CPR1000 PWR
FU Peng-tao;SHI Xiu-an;HAN Song;CAI De-chang

..............page:184-187

Verification of Calculation for Absorber Value in Pebble Bed High-Temperature Gas-Cooled Reactor
ZHANG Jing-yu;LI Fu;SUN Yu-liang;ZHOU Xia-feng

..............page:43-47

Development and Validation of 3-D Discrete Ordinates Neutron and Photon Transport Code CTDOS
ZANG Qi-yong;CHEN Yi-xue;WANG Wei-jin;HU Ye;YUAN Long-jun;ZHANG Bin;MA Xu-bo

..............page:346-349

Improved Core Design of SCWR With Double-Row-Rod Assembly
ZHAO Chuan-qi;CAO Liang-zhi;WU Hong-chun;ZHENG You-qi

..............page:265-269

Concept Research on Blanket Neutronics of Fusion-Fission Hybrid Reactor for Energy Production
SHI Xue-ming;PENG Xian-jue

..............page:255-260

Research on Calculation of Mixing Fraction for Natural Uranium Equivalent Fuel
HUANG Shi-en;ZHENG Ji-ye;WANG Lian-jie;WEI Yan-qin;LI Qing

..............page:132-136

In-core Loading Scheme and Verification of Tianwan Nuclear Power Station Unit 1 Cycle 6
LI You-yi;YANG Xiao-qiang;LI Wen-shuang;YAO Jin-guo;LI Zai-peng

..............page:160-163

Improvement of Coarse-Mesh Finite Difference Accelerated Nodal Method
XIA Zhao-dong;RUAN Ke-qiang

..............page:15-17

COSINE Software Development Based on Code Generation Technology
REN Hao;MO Wen-tao;LIU Shuo;ZHAO Guang

..............page:331-334

Development and Verification of Subchannel Analysis Code LINDEN
BAI Ning;ZHU Yuan-bing;REN Zhi-hao;CHEN Jun;ZHOU You-xin;LI Jing-gang;HE Hai-bo

..............page:299-301

Measurement and Analysis of Reactivity Temperature Coefficient of CEFR
CHEN Yi-yu;HU Yun;YANG Xiao-yan;FAN Zhen-dong;ZHANG Qiang;ZHAO Jin-kun;LI Ze-hua

..............page:88-91

Application of Discrete Ordinates Transport Calculation Methods in Analysis of Activated 41Ar Source Term in PWR NPPs
MI Ai-jun;WANG Xiao-xia;WANG Bing-heng;XUE Na;MAO Ya-wei

..............page:179-183

Development and Preliminary Validation of SN Transport Module in Lattice Code LATC of COSINE Package
LI Shuo;ZHANG Bin;LIU Zhi-yan;YAN Yu-hang;YU Hui;CHEN Yi-xue;ZHANG Guang-chun

..............page:338-341

Experimental Study of China Experimental Fast Reactor Pressure and Coolant Flow Rate Reactivity Effect
HU Yun;CHEN Xiao-liang;YU Hong;GANG Zhi;CHEN Yi-yu;ZHANG Jian;LI Ze-hua

..............page:103-106

Research on Ray Effect of Multi-dimensional SN Method Based on First Collision Source Theory
HU Ye;CHEN Yi-xue;ZHANG Bin;ZANG Qi-yong;YUAN Long-jun;MA Xu-bo

..............page:9-14

Computer Transformation and Validation of FMP System
RONG Chun-fang;ZHANG Di-fang

..............page:164-167

Neutronics Behavior Analysis for Natural Uranium Equivalent Fuel Test Irradiation
WANG Lian-jie;WEI Yan-qin;HUANG Shi-en;LI Qing;MENG Zhi-liang;CHEN Ming-jun;SU Li-zhi

..............page:144-149

Cross Section Expression Based on Neural Network Algorithm
ZHANG Han;ZHAO Qiang;LI Fu

..............page:207-210

Measurement and Analysis of Fission and Capture Fission Cross Section Ratios of 237Np/235U
wang shi xi ; yang yong ; zhang qiang ; chen xiao liang ; hu ding sheng ; wu ming yu ; chen xiao xian ; yang jia yin

..............page:117-119

Effect of Random Distribution of Coated Particle Fuel
FAN Kai;WEI Chun-lin;LI Fu

..............page:220-223

Burn-up Calculation of TOPAZ-Ⅱ Reactor
AN Wei-jian;ZHAO Shou-zhi;SHEN Feng;SUN Zheng;LIU Xing-min;WU Xiao-chun

..............page:211-215

Effect of Discharging Burnup Threshold on Average Discharging Burnup in Pebble Bed HTR
HAO Chen;LI Fu;GUO Jiong

..............page:188-191

Drift and Calibration of Inter-medial Range Channel in Qinshan Phase Ⅱ
YE Guo-dong;PAN Ze-fei;XIANG Jun-jun;YU Tao;WU Jun-yi

..............page:123-127

Sensitivity Coefficient Analysis of Fuel Nuclides on Molten Salt Reactor Experiment
LIU Ya-fen;GUO Rui;HU Ji-feng;CAI Xiang-zhou;CHEN Jin-gen

..............page:270-274

HANDF-E: A Program for TWR Burnup Calculations Based on Hexagonal Nodal Method
SUN Wei;LI Qing;WANG Kan

..............page:376-380

Emergency Reload Design for U1C6 of Tianwan Nuclear Power Station
CAO Dian-peng;WANG Hong-xia;XU Min;YAO Hong;CHENG He-ping

..............page:172-175

Neutronics Calculation for ITER TBM With 3D Deterministic Method
ZHANG Guang-chun;CAO Liang-zhi;WU Hong-chun;ZHENG You-qi

..............page:1-4

Calculation and Analysis of C5G7 Benchmark by SN2D Code
ZHAO Jing;PENG Liang-hui;LIU Zhao-yuan;LIU Zhi-hong;ZHANG Jian

..............page:18-24

Measurement and Analysis of CEFR Sodium Void Reactivity Effect
ZHOU Ke-yuan;YU Hong;HU Yun;CHEN Xiao-liang;GANG Zhi;WANG Shi-xi;LI Ze-hua

..............page:70-74

Design of Point Kinetic Module in Neutron Kinetic Program KIND of COSINE Software Package
WANG Su;YU Hui;CHEN Yi-xue;LIU Zhan-quan

..............page:302-308

Research on Pin Power Distribution in Fuel Subassembly of Fast Reactor
CAO Pan;YU Hong;XU Li;HU Yun;YANG Xiao-yan;CHEN Yi-yu

..............page:287-290

Measurement and Analysis of CEFR Safety and Shim Rod Worth
CHEN Yi-yu;YANG Yong;GANG Zhi;XU Li;YANG Xiao-yan;ZHOU Ke-yuan;HU Ding-sheng

..............page:92-94

Parallelization Method for Three Dimensional MOC Calculation
ZHANG Zhi-zhu;LI Qing;WANG Kan

..............page:38-42

Physics Startup of In-hospital Neutron Irradiator
li yi guo ; xia pu ; wu xiao bo ; zou shu zuo ; peng dan ; lu jin ; zhang zi zhu ; liu tong ; zhou yong mao

..............page:66-69

Development and Verification for Burnup Calculation Module of Lattice Code LATC of COSINE Package
YAN Yu-hang;QIU Chun-hua;ZHANG Bin;LIU Zhi-yan;LI Shuo;CHEN Yi-xue;MA Xu-bo

..............page:372-375

Research on Coupling of Neutronics and Thermal-Hydraulics Based on Stochastic Method of Neutron Transport
LI Lin-sen;WANG Kan;YUAN Hao-min;ZANG Jin-guang

..............page:291-294

Preliminary Analysis of Fuel Utilization Scenarios for Traveling Wave Reactor
GANG Zhi;ZHAO Jin-kun;ZHOU Ke-yuan;XIONG Xin

..............page:229-233

Measurement Experimental Research of 238U Fission Reaction Rate In China Experimental Fast Reactor
CHEN Xiao-xian;FAN Zhen-dong;WANG Yong;ZHAO Jin-kun;CHEN Xiao-liang;HU Ding-sheng;ZHAO Yu-shen

..............page:120-122

Measurement and Analysis of Fission Cross Section Ratio and Capture-Fission Cross Section Ratio of 238U/235U
ZHANG Qiang;YANG Yong;HU Ding-sheng;CHEN Xiao-liang;WU Ming-yu;YANG Jia-yin

..............page:114-116

Improved Method and Its Verification for Cell-Wise Homogenization Calculation
LIU Zhao-yuan;LIU Zhi-hong;ZHAO Jing;ZHANG Jian;PENG Liang-hui

..............page:29-32

Research on Monte Carlo Improved Quasi-Static Method for Reactor Space-Time Dynamics
XU Qi;WANG Kan;LI Shi-rui;YU Gang-lin

..............page:275-279

Research on Calculation of Gaseous and Liquid Radioactive Release During Normal Operation for Pressurized Water Reactor Plant
LV Wei-feng;XIONG Jun;TANG Shao-hua;LIU Jie

..............page:197-201

Nodal Integral Method for Convection-Diffusion Equation in Cylindrical Geometry
DENG Zhi-hong;SUN Yu-liang;LI Fu;Rizwan-uddin

..............page:25-28

Source Term Calculation of Spent Fuel Assembly of PWR Nuclear Power Plants
ZHANG Pu-zhong;SHAO Zeng;MAO Ya-wei;GAO Gui-ling;CHEN Yi-xue

..............page:192-196

Improvement of Discontinuous Factor for Strong Absorber Region
GUO Jiong;LI Fu

..............page:33-37

Physical Scheme Study of 10 MW Accelerator Driven Sub-critical Reactor
FU Yuan-guang;ZHAO Jing;GU Long;YANG Yong-wei

..............page:261-264

Effect of VVER Fuel Assembly Deformation on Quadrant Power Tilt
CAO Dian-peng;HUO Xiao-dong

..............page:79-82

Equilibrium Cycle Design for LLFPs Transmutation in PWRs
LIU Kun;WU Hong-chun;CAO Liang-zhi;ZHENG You-qi

..............page:202-206

Research of Criticality Test for China Experimental Fast Reactor
yu hong ; yang xiao yan ; zhou ke yuan ; chen xiao liang ; yang yong ; hu zuo ; fan zhen dong ; gang zhi ; zhao jin kun

..............page:62-65

Solving Parallelly 3-D Neutron Diffusion Equation Based on HYPRE
WU Wen-bin;LI Qing;WANG Kan

..............page:48-51

Development and Validation of Resonance Module in Lattice Parameter Code LATC of COSINE Package
LIU Zhi-yan;ZHANG Bin;LI Shuo;YU Hui;YAN Yu-hang;CHEN Yi-xue

..............page:350-354

Parallel Computation Research of Neutron Time-Spatial Kinetics Program for Fast Reactor
XU Li;MA Da-yuan;SHI Gong;YU Hong;LI Ze-hua

..............page:369-371

Preliminary Neutronics Calculation of Fusion-Fission Hybrid Reactor Breeding Spent Fuel Assembly
MA Xu-bo;CHEN Yi-xue;GAO Bin

..............page:245-249

Three-Dimensional Core Preliminary Analysis on Breeding Capability of Super Fast Reactor
LIU Bao-lin;WU Hong-chun;CAO Liang-zhi;ZHENG You-qi

..............page:239-244

Research on V&V Strategy of Reactor Physics Code of COSINE
LIU Zhan-quan;YANG Chao;DANG Ha-lei;CHEN Yi-xue

..............page:323-326

Power Confirming for Critical Facility Based on Activation Method and MCNP Code
YANG Yong-mu;MU Ke-liang;HUANG Li-yuan;NIU Jiang

..............page:111-113

Analysis of Method in Core Power Reconstruction
LI Wen-huai;MO Kun;LU Hao-liang;LI Jing-gang

..............page:280-282

Minor Actinide Transmutation Analysis of Fusion-Driven Subcritical System
YANG Chao;CAO Liang-zhi;WU Hong-chun;ZHENG You-qi;ZU Tie-jun

..............page:250-254

Design of NECL Subgroup Data Module and Arbitrary Geometry Resonance Calculation Code in Neutronics Evaluation Comprehensive Package
HE Lei;WU Hong-chun;CAO Liang-zhi;ZHANG Hong-bo

..............page:355-359

Neutron Spectrum Measurement of China Experimental Fast Reactor
chen xiao liang ; chen xiao xian ; yu hong ; yang yong ; zhang qiang ; wang shi xi ; hu ding sheng ; zhao yu sen

..............page:52-55

Design and Development of Neutron Kinetics Code KIND in COSINE Code Package
YU Hui;WANG Su;LIU Zhan-quan;WANG Chang-hui;CHEN Yi-xue

..............page:318-322