Advance Search
Volume 43 Issue 5
Oct.  2022
Turn off MathJax
Article Contents
Chang Yuan, Shi Xueyao, Wang Henan, Wang Hui. Uncertainty Analysis and Application of Source Term under Bypass Release Accident of HPR1000[J]. Nuclear Power Engineering, 2022, 43(5): 70-75. doi: 10.13832/j.jnpe.2022.05.0070
Citation: Chang Yuan, Shi Xueyao, Wang Henan, Wang Hui. Uncertainty Analysis and Application of Source Term under Bypass Release Accident of HPR1000[J]. Nuclear Power Engineering, 2022, 43(5): 70-75. doi: 10.13832/j.jnpe.2022.05.0070

Uncertainty Analysis and Application of Source Term under Bypass Release Accident of HPR1000

doi: 10.13832/j.jnpe.2022.05.0070
  • Received Date: 2021-10-18
  • Rev Recd Date: 2022-01-20
  • Publish Date: 2022-10-12
  • The radioactive source term analysis of serious accidents in nuclear power plants is the focus of attention in the field of nuclear safety, and the source term analysis has great uncertainty. In this paper, based on the best estimate plus uncertainty (BEPU) analysis method, HPR1000 serious accident analysis model is established by using the integrated serious accident analysis program. For the first time, from the point of view of the whole accident process, a process suitable for source term uncertainty analysis of HPR1000 serious accident is developed, and this method is used to analyze the source term uncertainty of containment bypass release category. The research content of this paper enriches the source term analysis of the serious accident of HPR1000, and also lays a foundation for the development of the three-level probabilistic safety analysis (PSA) technology of HPR1000.

     

  • loading
  • [1]
    MATTIE P, GAUNTT R, ROSS K, et al. Uncertainty analysis of the unmitigated long-term station blackout of the peach bottom atomic power station[R]. Washington: U. S. Nuclear Regulatory Commission, 2016.
    [2]
    ROSS K, BIXLER N, WEBER S, et al. Uncertainty analysis of the unmitigated short-term station blackout of the Surry power station[R]. Draft Report, 2016.
    [3]
    GAUNTT R O, BIXLER N E, WAGNER K C. An uncertainty analysis of the hydrogen source term for a station blackout accident in Sequoyah using MELCOR 1.8. 5[R]. Albuquerque: Sandia National Lab. , 2014.
    [4]
    TIBORCZ L, HOLLANDS T. Uncertainty and sensitivity analysis of the Phébus FPT3 test[J]. Nuclear Engineering and Design, 2021, 380: 111315. doi: 10.1016/j.nucengdes.2021.111315
    [5]
    PARK S, AHN K I, SONG Y M, et al. Uncertainty analysis of the potential hazard of MCCI during severe accidents for the CANDU6 plant[J]. Science and Technology of Nuclear Installations, 2015, 2015: 462941.
    [6]
    郎明刚,高祖瑛. 压水堆部分堆芯参数敏感性分析[J]. 核科学与工程,2002, 22(2): 104-107. doi: 10.3321/j.issn:0258-0918.2002.02.002
    [7]
    郭连城,曹学武. 核电厂大LOCA始发严重事故下氢气源项的敏感性分析[J]. 核动力工程,2007, 28(5): 69-74,108. doi: 10.3969/j.issn.0258-0926.2007.05.016
    [8]
    张亮,黄庆勇,张琪彬,等. MACCS估算反应堆严重事故后果的不确定度分析[J]. 核动力工程,2016, 37(S1): 93-95.
    [9]
    冉旭,吴丹,陈炳德,等. 最佳估算加不确定性分析方法及其应用研究[J]. 核动力工程,2013, 34(3): 120-123. doi: 10.3969/j.issn.0258-0926.2013.03.027
  • 加载中

Catalog

    通讯作者: 陈斌, bchen63@163.com
    • 1. 

      沈阳化工大学材料科学与工程学院 沈阳 110142

    1. 本站搜索
    2. 百度学术搜索
    3. 万方数据库搜索
    4. CNKI搜索

    Figures(6)  / Tables(3)

    Article Metrics

    Article views (189) PDF downloads(38) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return