摘要
核电安全性始终是世界公众关注的焦点。目前概率安全评价已成为核电厂安全评价的标准方法之一,用概率论的方法对核电厂各个系统进行可靠性评价也已成为必不可少的分析手段。中国实验快堆是我国第一座池式钠冷快中子反应堆,其概率安全评价和可靠性评价对其安全运行具有重要意义。本文建立了中国实验快堆保护系统的故障树,并进行了定性和定量分析,计算得出了系统的不可用度,并进行重要度、敏感度和不确定度分析,对典型位置的部件进行共因评价。分析结果表明:由于多个冗余通道的设计,系统最小割集的发生概率分布比较均匀,该系统的设计是平衡的,不存在明显的薄弱环节,能够满足反应堆发生异常事件时的停堆要求。
Nuclear safety is always the focus of public concern. At present, probabilistic safety assessment is one of the standard methods to assess the safety of nuclear power plants. It is also necessary to use probabilistic method to do the reliability analysis of each system of the nuclear power plant. China Experimental Fast Reactor （CEFR） is the first pool type sodium cooling fast breeder reactor in China. It is significant to carry through its probabilistic safety assessment and reliability analysis. In this paper, the fault trees of CEFR protection and safety monitoring system are constructed. The unavailability, importance, sensitivity and uncertainty are calculated. The common cause failures of the components in the typical positions are assessed. The analysis results indicate that the distribution of system minimal cut sets is well-proportioned. The design of this system is balanced, and do not have obvious weakness. The requirements of reactor shutdown during abnormal events are satisfied.
出处
《核科学与工程》
CSCD
北大核心
2012年第2期125-132,共8页
Nuclear Science and Engineering
