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Sensitivity/uncertainty comparison and similarity analysis between TMSR-LF1 and MSR models 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2020, 卷号: 122, 页码: -
Authors:  Liu, YF;  Yan, R;  Zou, Y;  Yu, SH;  Zhou, B;  Kang, XZ;  Hu, JF;  Cai, XZ
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NUCLEAR-SCIENCE  SALT  CORE  LR-0  SENSITIVITY  CRITICALITY  LIBRARY  DESIGN  
Evaluation of Mo-99 production in a small modular thorium based molten salt reactor 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2020, 卷号: 124, 页码: -
Authors:  Kang, XZ;  Zhu, GF;  Yan, R;  Liu, YF;  Zou, Y;  Dai, Y;  Cai, XZ
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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
Adobe PDF(3067Kb)  |  Favorite  |  View/Download:55/10  |  Submit date:2019/12/30
URANIA FUEL  CORE  
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
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NUCLEAR-DATA  
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
Adobe PDF(2633Kb)  |  Favorite  |  View/Download:39/5  |  Submit date:2019/12/17
ADVANTAGES  DESIGN  CYCLE  MSR  
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
Adobe PDF(2488Kb)  |  Favorite  |  View/Download:32/2  |  Submit date:2019/12/17
REACTOR  PACKING  
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  
Uranium utilization with thorium blanket in Pebble Bed Fluoride salt-cooled high temperature reactor 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2015, 卷号: 83, 页码: 374—386
Authors:  Zhu, GF;  Zou, Y;  Xu, HJ;  Dai, Y;  Li, MH;  Yan, R;  Xu, HJ (reprint author), Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China.
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Light-water Reactors  Fuel  Design