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Monte Carlo burnup code development based on multi-group cross section method 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2019, 卷号: 110, 期号: -, 页码: 24—29
Authors:  Zhu, GF;  Yan, R;  Dai, M;  Yu, SH;  Kang, XZ;  Yu, XH;  Cai, XZ;  Liu, GM;  Zou, Y
View  |  Adobe PDF(2163Kb)  |  Favorite  |  View/Download：3/0  |  Submit date：2019/12/30
NUCLEAR-DATA  
Thorium utilization with pebble mixing system in fluoride salt-cooled High Temperature Reactor 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2019, 卷号: 114, 期号: -, 页码: 84—90
Authors:  Zhu, GF;  Liu, SJ;  Zou, Y;  Yan, R;  Tan, ML;  Kang, XZ;  Li, MH;  Zhou, B;  Dai, Y
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URANIA FUEL  CORE  
Possible scenarios for the transition to thorium fuel cycle in molten salt reactor by using enriched uranium 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2018, 卷号: 104, 页码: 75-84
Authors:  Cui, DY;  Li, XX;  Xia, SP;  Zhao, XC;  Yu, CG;  Chen, JG;  Cai, XZ
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Breeding Ratio  Perspectives  
Fuel pebble optimization for the thorium-fueled Pebble Bed Fluoride salt-cooled high-temperature reactor (PB-TFHR) 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2018, 卷号: 108, 期号: -, 页码: 179-187
Authors:  Fang, YH;  Li, XX;  Yu, CG;  Chen, JG;  Cai, XZ
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CRITICALITY  BLANKET  BLOCKS  DESIGN  INDIA  
Neutronics modeling and analysis of the TMSR-SF1 fuel lattice and full core with explicit fuel particle distribution and random pebble loadings 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2018, 卷号: 109, 期号: -, 页码: 171-179
Authors:  Sun, KC;  Wilson, J;  Hauptman, S;  Ji, RM;  Dave, AJ;  Zou, Y;  Hu, LW
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REACTOR  PACKING  
Optimization of Th-U fuel breeding based on a single-fluid double-zone thorium molten salt reactor 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2018, 卷号: 108, 期号: -, 页码: 144-151
Authors:  Li, GC;  Cong, P;  Yu, CG;  Zou, Y;  Sun, JY;  Chen, JG;  Xu, HJ
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ADVANTAGES  DESIGN  CYCLE  MSR  
Preparation, shielding properties and mechanism of a novel neutron shielding material made from natural Szaibelyite resource 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2018, 卷号: 106, 期号: -, 页码: 140-145
Authors:  Dong, MG;  Xue, XX;  Li, ZF;  Yang, H;  Sayyed, MI;  Elbashir, BO
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GAMMA-RAY  COLEMANITE  CONCRETE  COMPOSITES  NUMBER  RUBBER  CHINA  TESTS  ORES  
The feasibility research of thorium breeding using fluoride salt as a fast reactor coolant 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2017, 卷号: 101, 期号: -, 页码: 199-208
Authors:  Peng, Y;  Zhu, GF;  Zou, Y;  Liu, YF;  Yu, XH;  Cai, XZ;  Xu, HJ
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Burn Reactors  Fuel-cycle  Sustainability  Perspectives  
Dancoff factor analysis for pebble bed fluoride salt cooled high temperature reactor 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2016, 卷号: 88, 期号: -, 页码: 332—339
Authors:  Qin, W;  Yang, K;  Chen, JE;  Cai, XZ;  Cai, XZ (reprint author), Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China.
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Fuel  
Breed-and-burn strategy in a fast reactor with optimized starter fuel 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2015, 卷号: 85, 页码: 11—16
Authors:  Huang, JF;  Han, JL;  Cai, XZ;  Ma, YW;  Li, XX;  Zou, CY;  Yu, CG;  Chen, JG;  Chen, JG (reprint author), Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China.
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Cooled Fast-reactor  Candle Burnup  Wave  Regime