Discussion of reactor core damage probability under condition of multiple reactor years

被引:0
|
作者
Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China [1 ]
机构
关键词
D O I
暂无
中图分类号
学科分类号
摘要
5
引用
收藏
页码:289 / 291
相关论文
共 50 条
  • [1] RADIATION EXPOSURE AND DAMAGE OF REACTOR COMPONENTS OUTSIDE REACTOR CORE
    SCHULTZ, H
    HEHN, G
    [J]. ATOMKERNENERGIE, 1977, 29 (02): : 73 - 74
  • [2] Creep deformation and damage behavior of reactor pressure vessel under core meltdown scenario
    Mao, J. F.
    Zhu, J. W.
    Bao, S. Y.
    Luo, L. J.
    Gao, Z. L.
    [J]. INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2016, 139 : 107 - 116
  • [3] Further discussion on appropriate interpretation of core damage probability
    Zhao, Rui-Chang
    Tong, Jie-Juan
    Zhou, Lin-Jun
    Zhang, Yong-Fa
    Huang, Ting
    Zhang, Zuo-Yi
    [J]. Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2009, 43 (12): : 1057 - 1061
  • [4] Evaluation of the core damage frequency of the marine reactor X
    Matsuoka, T
    Yamaji, A
    Mitomo, N
    Hukuhara, Y
    Ishida, T
    [J]. PROBABILISTIC SAFETY ASSESSMENT AND MANAGEMENT (PSAM 4), VOLS 1-4, 1998, : 1296 - 1301
  • [5] Numerical Analysis of Flow Distribution Characteristics at Core Inlet of Small Reactor under Rolling Condition
    Liu, Yirui
    Dong, Xiuchen
    Zhang, Xin
    Yuan, Jiangtao
    [J]. Hedongli Gongcheng/Nuclear Power Engineering, 2022, 43 (05): : 89 - 94
  • [6] Risk-Informing Nuclear Reactor Safety: The Prediction of the Probability of Core Damage Due to Loss of Power and Cooling
    Duffey, Romney B.
    Zio, Enrico
    [J]. ASCE-ASME JOURNAL OF RISK AND UNCERTAINTY IN ENGINEERING SYSTEMS PART B-MECHANICAL ENGINEERING, 2024, 10 (03):
  • [7] 25 YEARS OPERATION OF THE ROSSENDORF-RESEARCH-REACTOR - 20 YEARS OPERATION OF THE ROSSENDORF-ANNULAR-CORE-REACTOR
    BRINCKMANN, HF
    WEIBRECHT, R
    [J]. KERNENERGIE, 1982, 25 (12): : 453 - 454
  • [8] Structural integrity assessment of the reactor pressure vessel under the external reactor vessel cooling condition
    Kim, JS
    Jin, TE
    [J]. NUCLEAR ENGINEERING AND DESIGN, 1999, 191 (02) : 117 - 133
  • [9] Flow and Heat Transfer Analysis in Lead-bismuth Reactor Core under Rod Bending Condition
    Qiu, Hanrui
    Li, Jun
    Wang, Mingjun
    Zhang, Jing
    Tian, Wenxi
    Su, Guanghui
    [J]. Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2023, 57 (08): : 1514 - 1524
  • [10] Condition monitoring of an advanced gas-cooled nuclear reactor core
    Pang, Y.
    Giovanini, L.
    Monari, M.
    Grimble, M.
    [J]. PROCEEDINGS OF THE INSTITUTION OF MECHANICAL ENGINEERS PART I-JOURNAL OF SYSTEMS AND CONTROL ENGINEERING, 2007, 221 (I6) : 833 - 842