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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
View  |  Adobe PDF(895Kb)  |  Favorite  |  View/Download:5/0  |  Submit date:2021/09/06
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
View  |  Adobe PDF(3067Kb)  |  Favorite  |  View/Download:63/11  |  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
View  |  Adobe PDF(2163Kb)  |  Favorite  |  View/Download:55/6  |  Submit date:2019/12/30
NUCLEAR-DATA  
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