基于DFM的AP1000壳内压力超限ESF驱动可靠性分析  

AP1000 In-Containment Pressure Over-limit ESF Actuation Reliability Analysis Based on DFM

作　　者：王志超[1,2] 王豪[1] 周赟 

机构地区：[1]上海交通大学自动化系,上海200240 [2]国核工程有限公司,上海200233

出　　处：《仪器仪表用户》2016年第8期1-6,41,共7页Instrumentation

摘　　要：本文运用美国核管会(NRC)报告NUREG/CR-6465提出的动态流图(DFM)可靠性分析方法,以AP1000核电站安全壳压力超限专设安全设施(ESF)驱动系统为对象进行可靠性分析。该方法体现过变量输入输出的因果关系、动态特性、部件状态变化和软件逻辑对系统可靠性的影响,将数字化保护系统与工艺系统有机结合。其分析结果是带时间标签的质蕴含(PI)集合,对进一步地定量分析以及提高系统的可靠性具有很重要的指导意义。This paper making use of Dynamic Flowgraph Methodology （DFM） which is the rehability analysis method proposed in （NRC） report NUREG/CR-6465 to analyze the reliability of AP1000 nuclear power plant containment pressure over- limit safety feature facility （ESF） actuation system. This method reflects the impact of process input and output variable causal relationship, dynamic characteristics, component state variation and software logic to the system reliability, and organically combines the digital protect system and process system. The result of the analysis is the set of time-stamped Prime Implicant （PI） which has a highly important guiding significance to the further quantitative analysis and the improvement of the reliability of the

关 键 词：AP1000 非能动安全壳冷却系统 专设安全设施 动态流图 

分 类 号：TP302.7[自动化与计算机技术—计算机系统结构]