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非能动系统可靠性分析方法探讨

Research on reliability of passive system

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【作者】 玉宇童节娟刘涛赵军张阿玲

【Author】 YU Yu,TONG Jie-juan,LIU Tao,ZHAO Jun,ZHANG A-ling (Institute of Nuclear and New Energy Technology,Tsinghua University,Beijing 100084,China)

【机构】 清华大学核能与新能源技术研究院

【摘要】 当反应堆出现异常工况时,不依靠人为操作或外部设备的强制性干预,只依靠堆的固有安全性和非能动的自然安全机制就能使反应堆趋于正常运行或安全停闭,是非能动系统的重要特征,也是其与能动系统差异的本质所在。非能动系统因此在新一代反应堆设计,如:高温气冷堆和AP1000核电厂中,得到了充分的重视。然而,也正是因为非能动系统运行的物理过程不依靠能动部件驱动,而是依靠自然力,其驱动力与阻力都受到很多不确定因素的影响,因而物理过程失效成为导致系统运行失效的重要因素。因此,确定影响系统运行的关键因素、结合事件序列研究非能动系统运行的动态演变过程形成了非能动系统可靠性的分析框架,是采用非能动设计核电厂概率安全分析工作的重要内容。

【Abstract】 It is the important feature of passive system and the basic difference from the active system that nuclear plant can be driven to safe state or shutdown by inherent safety characters of the reactor and physical principles,independent of human interfere or the operation of outside equipments,when the reactor is in abnormal condition.So passive system is widely used in new generation nuclear power plant(NPP) such as high-temperature gas-cooled reactors and AP1000 NPPs.While physical process failure become one of the important contributors to the system operation failure since system operation is depending on natural force but not on outside power and both the driven force and resistance are influenced by many uncertain factors.Then finding the key factors for the system operation,analyzing the development of the passive system combining with the accident scenarios are the main steps of the analysis of the passive system reliability,and the important content of the probability safety assessment(PSA) of nuclear plant with the passive design.

【基金】 中国博士后基金会资助项目(20090460296)
  • 【会议录名称】 中国核科学技术进展报告——中国核学会2009年学术年会论文集(第一卷·第2册)
  • 【会议名称】“创新——核科学技术发展的不竭源泉”——中国核学会2009年学术年会
  • 【会议时间】2009-11-18
  • 【会议地点】中国北京
  • 【分类号】TM623
  • 【主办单位】中国核学会
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