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核电厂事件快速筛选方法研究 被引量:1

Study on Quick Screening of Nuclear Power Plant Events
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摘要 运行安全监督与运行经验反馈是保障和提高核电厂安全的两种非常有效的措施。核电厂事件分析是运行安全监督和运行经验反馈的重要依据。核电厂每年发生的事件数目庞大,重要的是从中筛选出安全重要的、典型而有反馈价值的事件。在现有的核电厂事件分析方法基础上,引入风险的观点,探讨了一种核电厂事件快速筛选的方法。重点介绍了支持这种筛选方法的风险分析工具——重要度确定过程。以一个与电厂实际发生的事件类似的事件作为示例,分别使用重要度确定过程分析软件和实际的PSA模型来计算事件给电厂带来的风险增量ΔCDF,验证重要度确定过程的可用性。分析显示,重要度确定过程给出的ΔCDF的量级和实际的PSA模型计算的ΔCDF的量级一致。表明重要度确定过程的定量化结果足够支持它所支持的应用。最后,指出了目前版本重要度确定过程的局限性,讨论了以后可能的扩展和应用。 Operation safety surveillance and operation experience feedback are two effective measures to ensure and improve nuclear safety, the basis of which is nuclear power plant events analysis. A substantial number of events occur every year in nuclear power plant, thus screening for safety important and typical events which are valuable for experience feedback is important. Combining with risk insights, a new method for quick screening of nuclear power plant events is proposed on the basis of present event analysis method. A risk assessment tool to determination process (SDP), is introduced support the new method, i.e. significance in details. An example event is analyzed to obtain ACDF using SDP software and PSA model respectively, to verify the capability of SDP. The quantification results show agreement betweenACDF of SDP and PSA models. It is concluded that the quantification results of SDP are capable for applicationsit supports. Limitations of present SDP software are pointed out and its future extension and potential applications are discussed.
作者 方俊 赵博
出处 《核科学与工程》 CSCD 北大核心 2013年第3期305-313,共9页 Nuclear Science and Engineering
关键词 事件分析 筛选 重要度确定过程 运行经验反馈 概率安全分析 event analysis screening significance determination process operationexperience feedback probabilistic safety analysis
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参考文献4

  • 1郝晓峰.民用核设施运行经验反馈[J].核动力工程,1998,19(1):83-88. 被引量:7
  • 2IAEA. Standards Series No. NS-G-2.4, The Operating Organization for Nuclear Power Plants [S]. Vienna: IAEA, 2001.
  • 3IAEA. Standards Series No. 288, Safety of Nuclear Power Plants Operation, A National System for Feedback of Experience from Events in Nuclear Power Plants[S]. IAEA, 1999.
  • 4NRC. IMC 0609, Significance determination process [R].

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