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Neutronics-thermal-hydraulics-material coupling study of lead-bismuth cooled reactor single rod based on oxidative corrosion characteristics
NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间:2025-01-07
    • Neutronics-thermal-hydraulics-material coupling study of lead-bismuth cooled reactor single rod based on oxidative corrosion characteristics

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    • In the field of nuclear energy, experts have built a nuclear thermal material coupling framework based on the MOOSE platform to study the influence of lead bismuth reactor oxidation corrosion on core parameters, providing important references for the application of lead bismuth reactors.
    • NUCLEAR TECHNIQUES   Vol. 47, Issue 11, Article number: 110604(2024)
    • DOI:10.11889/j.0253-3219.2024.hjs.47.110604    

      CLC: TL99
    • Received:29 November 2023

      Revised:25 April 2024

      Published:15 November 2024

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  • JI Xu,CHAI Xiang,ZHANG Lefu,et al.Neutronics-thermal-hydraulics-material coupling study of lead-bismuth cooled reactor single rod based on oxidative corrosion characteristics[J].NUCLEAR TECHNIQUES,2024,47(11):110604. DOI: 10.11889/j.0253-3219.2024.hjs.47.110604.

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Related Author

JI Xu
CHAI Xiang
ZHANG Lefu
LIU Xiaojing
ZHANG Jing
WU Yingwei
HE Yanan
XIANG Fengrui

Related Institution

School of Nuclear Science and Engineering, Shanghai Jiao Tong University
Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, School of Nuclear Science and Technology, Xi'an Jiaotong University
Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences
Institute of Physics, Academia Sinica
Institute of High Energy Physics, Academia Sinica
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