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Development of thermal creep model for reactor pressure vessel lower head and application in OLHF experimental analysis
NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2024-10-25
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    • Development of thermal creep model for reactor pressure vessel lower head and application in OLHF experimental analysis

    • “In the field of mitigating serious accidents in nuclear reactors, experts have developed the LHTCM model to accurately predict the creep behavior of the lower head, providing a solution to prevent radioactive material leakage.”
    • NUCLEAR TECHNIQUES   Vol. 45, Issue 8, Article number: 080603(2022)

    • DOI：10.11889/j.0253-3219.2022.hjs.45.080603    

      CLC： TL33

    • Received：08 June 2022，

      Revised：06 July 2022，

      Published：15 August 2022

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  • YANG Hao,ZHANG Bin,GAO Pengcheng,et al.Development of thermal creep model for reactor pressure vessel lower head and application in OLHF experimental analysis[J].NUCLEAR TECHNIQUES,2022,45(08):080603-080603. DOI： 10.11889/j.0253-3219.2022.hjs.45.080603.

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Hao YANG
Bin ZHANG
Pengcheng GAO
Shaowei TANG
Jianqiang SHAN

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School of Nuclear Science and Technology, Xi'an Jiaotong University
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