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Fatigue status assessment for reactor pressure vessel based on actual operational transient
更新时间:2021-06-03
    • Fatigue status assessment for reactor pressure vessel based on actual operational transient

    • NUCLEAR TECHNIQUES   Vol. 36, Issue 4, Article number: 040641(2013)
    • DOI:10.11889/j.0253-3219.2013.hjs.36.040641    

      CLC: TL351.6
    • Published:2013

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  • ZHU Guangqiang LIAO Changbin DAI Bing GUI Chun. Fatigue status assessment for reactor pressure vessel based on actual operational transient[J]. Nuclear techniques, 2013, 36(4): 040641 DOI: 10.11889/j.0253-3219.2013.hjs.36.040641.

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Related Author

HE Yinbiao
HUI Hu
LI Hui
XUAN Fuzhen
CAO Yupeng
陶宏新
沈睿
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Related Institution

Key Laboratory of Pressure System and Safety, Ministry of Education, East China University of Science and Technology
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