Advance Search
Volume 42 Issue 4
Aug.  2021
Turn off MathJax
Article Contents
Fang Xing, Weng Wenqing, Ye Shuixiang, Zhang Wei, Li Jianbo. Study on Extension of Containment ILRT Cycle of CPR1000[J]. Nuclear Power Engineering, 2021, 42(4): 222-227. doi: 10.13832/j.jnpe.2021.04.0222
Citation: Fang Xing, Weng Wenqing, Ye Shuixiang, Zhang Wei, Li Jianbo. Study on Extension of Containment ILRT Cycle of CPR1000[J]. Nuclear Power Engineering, 2021, 42(4): 222-227. doi: 10.13832/j.jnpe.2021.04.0222

Study on Extension of Containment ILRT Cycle of CPR1000

doi: 10.13832/j.jnpe.2021.04.0222
  • Received Date: 2020-06-22
  • Rev Recd Date: 2020-07-13
  • Publish Date: 2021-08-15
  • The containment ILRT for 10 years occupies the critical path of refueling for about 100 hours. 94 nuclear power units in the United States have extended the containment ILRT cycle to 15 years based on containment performance evaluation. This paper introduces the performance evaluation requirements of the relevant containment in the United States in detail, and analyzes the extension of the ILRT cycle by the CPR1000 unit, and the availability of historical test data and inspection data. Taking a CPR1000 demonstration unit as an example, the risk after prolonging the safety test of the containment is calculated, and the risk increment is very small. The results show that the CPR1000 unit basically is with the conditions to extend the test period of the containment seal.

     

  • loading
  • [1]
    Nuclear Energy Institute. Industry guideline for implementing performance-based option of 10 CFR 50, Appendix J[R]. NEI94-01, Revision 3-A, Washington: Nuclear Energy Institute, 2012.
    [2]
    Nuclear Energy Institute. Industry guideline for implementing performance: based option of 10 CFR 50, Appendix J[R]. NEI94-01, Revision 2-A, Washington: Nuclear Energy Institute, 2008.
    [3]
    Nuclear Energy Institute. Industry guideline for implementing performance-based option of 10 CFR 50, Appendix J[R]. NEI94-01, Revision 0, Washington: Nuclear Energy Institute, 1995.
    [4]
    American Nuclear Society. American national standard for containment system leakage testing requirements: ANSI/ANS-56.8-1994[S]. American: American Nuclear Society, 1994.
    [5]
    The American Society of Mechanical Engineers. Rules for inservice inspection of nuclear power plant components: ASME BPVC-XI-2013[S]. New York: ASME, 2013
    [6]
    Electric Power Research Institute. Risk impact assessment of extended integrated leak rate testing intervals: 1009325[R]. California: Electric Power Research Institute, 2008.
    [7]
    Electricte De France. 900兆瓦(电)压水堆核电站土建工程设计和建造法则: RCC-G[Z]. 水利电力部苏州热工研究所, 译. 苏州: 水利电力部苏州热工研究所, 1983
    [8]
    Nuclear Regulatory Commission. Inservice inspection of prestressed concrete containment structures with grouted tendons[Z]. Washington: Nuclear Regulatory Commission, 2012 .
    [9]
    Nuclear Regulatory Commission. An approach for using probabilistic risk assessment in risk-informed decisions on plant specific changes to the licensing basis: regulatory guide 1.174, revision 2[R]. Washington: Nuclear Regulatory Commission, 2011.
    [10]
    Nuclear Regulatory Commission Office of Nuclear Regulatory Research. An approach for plant-specific, risk-informed decisionmaking: technical specifications: regulatory guide 1.177, revision 1[Z]. Washington: Nuclear Regulatory Commission, 2011.
    [11]
    Nuclear Regulatory Commission Office of Nuclear Regulatory Research. An approach for determining the technical adequacy of probabilistic risk assessment results for risk-informed activities: regulatory guide 1.200[Z]. Washington: U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2009
    [12]
    国家核安全局. 关于发布《概率安全分析技术在核安全领域中的应用》(试行)的通知: 国核安发[2010] 12号[R]. 北京: 国家核安全局, 2010.
    [13]
    U. S. Nuclear Regulatory Commission. Vogtle electric generating plant technical specification revision request integrated leakage rate testing interval extension[R]. Washington: U. S. Nuclear Regulatory Commission, 2003.
    [14]
    Calvert Cliffs Nuclear Power Plant. License amendment request: one-time integrated leakage rate test extension[R]. Washington: U. S. Nuclear Regulatory Constellation, 2002.
  • 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

    Tables(3)

    Article Metrics

    Article views (287) PDF downloads(22) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return