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Analysis of U-Pu breeding in molten salt fast reactor
SPECIAL SECTION ON THE 11TH NATIONAL CONFERENCE ON NEW AND RESEARCH REACTORS (PART III) | 更新时间:2024-10-25
    • Analysis of U-Pu breeding in molten salt fast reactor

    • “In the field of molten salt fast reactor proliferation, researchers have utilized the high solubility characteristics of uranium plutonium heavy metal salts in molten salt based on a dual fluid scheme to achieve high proliferation capability. Through calculation and analysis, the chloride salt scheme has greater proliferation advantages, providing reference for the design of molten salt fast reactors.”
    • NUCLEAR TECHNIQUES   Vol. 43, Issue 8, (2020)
    • DOI:10.11889/j.0253-3219.2020.hjs.43.080003    

      CLC: TL3
    • Received:26 April 2020,

      Revised:27 May 2020,

      Published:15 August 2020

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  • LI Dongguo,ZHOU Xuemei,LIU Guimin.Analysis of U-Pu breeding in molten salt fast reactor[J].NUCLEAR TECHNIQUES,2020,43(08):13-19. DOI: 10.11889/j.0253-3219.2020.hjs.43.080003.

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Related Author

刘桂民
LI Dongguo LIU Guimin
YANG Zhen
DAI Zhimin
ZOU Yang
YAO Yongkui
WANG Kai
WANG Chaoqun

Related Institution

University of Chinese Academy of Sciences
North-Western China Regional Office of Nuclear and Radiation Safety Inspection, National Nuclear Safety Administration
North-Western China Regional Office of Nuclear and Radiation Saftety Inspection, National Nuclear Safety Administration
ShanghaiTech University
Chengdu University of Technology
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