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Strength check and fatigue analysis method for nuclear Class 1 pressure-bearing equipment based on ASME code
NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2026-02-13

    • Strength check and fatigue analysis method for nuclear Class 1 pressure-bearing equipment based on ASME code

    • “Experts in the field of nuclear energy adopted a thermal fluid solid multi physics field coupling method to conduct structural strength verification and fatigue analysis of a certain type of reactor pipeline system according to ASME specifications. The results showed that the stress classification of the pipeline system met the requirements of the specifications, and the cumulative fatigue usage factor at key positions was less than 1, without exceeding the limit, providing strong support for ensuring the safe operation of the reactor.”
    • NUCLEAR TECHNIQUES   Vol. 49, Issue 2, Article number: 020602(2026)

    • DOI：10.3724/j.0253-3219.2026.hjs.49.250268    

      CLC： TL334;TL341

    • Received：30 June 2025，

      Revised：2025-08-03，

      Published：15 February 2026

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  • JIANG Yanming,LI Xiaochang,TIAN Ruifeng,et al.Strength check and fatigue analysis method for nuclear Class 1 pressure-bearing equipment based on ASME code[J].NUCLEAR TECHNIQUES,2026,49(02):020602. DOI： 10.3724/j.0253-3219.2026.hjs.49.250268. CSTR： 32193.14.hjs.CN31-1342/TL.2026.49.250268.

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Related Author

TANG Feifei
LIN Junjie
LI Tutao
GAO Yongjun
ZHAO Xielin
ZHOU Jinxiong
贺寅彪
陶宏新

Related Institution

Suzhou Nuclear Power Research Institute Co., Ltd.
State Key Laboratory for Strength and Vibration of Mechanical Structures, School of Aerospace, Xi'an Jiaotong University
Shanghai Nuclear Engineering Research & Design Institute
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