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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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Study on dynamic characteristics of activated products source term in secondary loop of integrated molten salt reactor 期刊论文
RADIATION PHYSICS AND CHEMISTRY, 2020, 卷号: 171, 页码: -
Authors:  Zhou, B;  Yu, XH;  Liu, YF;  Zou, Y;  Yang, P;  Yu, SH;  Kang, XZ;  Zhu, GF;  Yan, R
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Study on dynamic characteristics of fission products in 2 MW molten salt reactor 期刊论文
NUCLEAR SCIENCE AND TECHNIQUES, 2020, 卷号: 31, 期号: 2, 页码: -
Authors:  Zhou, B;  Yu, XH;  Zou, Y;  Yang, P;  Yu, SH;  Liu, YF;  Kang, XZ;  Zhu, GF;  Yan, R
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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
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URANIA FUEL  CORE  
A novel concept for a molten salt reactor moderated by heavy water 期刊论文
ANNALS OF NUCLEAR ENERGY, 2019, 卷号: 132, 页码: 391-403
Authors:  Wu, JH;  Chen, JG;  Kang, XZ;  Li, XX;  Yu, CG;  Zou, CY;  Cai, XZ
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FUEL-CYCLE  BREEDING RATIO  CORE DESIGN  GRAPHITE  
Low enriched uranium and thorium fuel utilization under once-through and offline reprocessing scenarios in small modular molten salt reactor 期刊论文
INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2019, 卷号: 43, 期号: 11, 页码: 5775-5787
Authors:  Zhu, GF;  Zou, Y;  Yan, R;  Tan, ML;  Zou, CY;  Kang, XZ;  Chen, JG;  Guo, W;  Dai, Y
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DESIGN  
Neutron flux distribution and conversion ratio of Critical Experiment Device for molten salt reactor research 期刊论文
ANNALS OF NUCLEAR ENERGY, 2019, 卷号: 133, 页码: 707-717
Authors:  Liu, YF;  Yan, R;  Zou, Y;  Kang, XZ;  Zhou, B;  Yu, SH
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NUCLEAR-SCIENCE  CROSS-SECTION  CAPTURE  GRAPHITE  LIBRARY  
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  
熔盐实验堆堆芯物理参数研究 期刊论文
核技术, 2019, 卷号: 42, 期号: 03, 页码: 79-84
Authors:  于世和;  李晓晓;  刘亚芬;  康旭忠;  杨璞;  冀锐敏;  朱贵凤;  周波;  严睿;  邹杨
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熔盐堆  熔盐堆实验  堆芯物理参数  临界参数