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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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Influence of Li-7 enrichment on Th-U fuel breeding performance for molten salt reactors under different neutron spectra 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2020, 卷号: 120, 页码: -
Authors:  Zhou, J;  Chen, JG;  Wu, JH;  Xia, SP;  Zou, CY
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CYCLE  
Dynamic analysis for a 2 MW liquid-fueled molten salt reactor 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2020, 卷号: 126, 页码: -
Authors:  Cui, Y;  Cui, L;  Xia, SP;  Chen, JG;  Cai, XZ
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DELAYED NEUTRON FRACTION  CYCLE  CODE  
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  
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  
Study on background shielding for a compact photoneutron source 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2019, 卷号: 115, 页码: 74-79
Authors:  Wang, XH;  Liu, LX;  Hu, JF;  Han, JL;  Yang, P;  Zhang, GL;  Wang, NX;  Cai, XZ;  Wang, HW;  Chen, JG
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NEUTRON SOURCE  DESIGN  
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  
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  
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