期刊论文

Safety Analysis for Reactor Scram Subsystem Based on Multiple Methods

中文

核动力工程

0258-0926

2018

39

3

156-161

10.13832/j.jnpe.2018.03.0156

反应堆系统设计技术重点实验室开放基金 中核集团高可信计算学科重点实验室共同资助（HT-LW-02-2014005）

本校为第一机构

针对反应堆紧急停堆子系统,将故障模式影响分析（FMEA）、故障树分析（FTA）、系统理论的过程分析（STPA）3种独立的基本分析方法进行组合,形成仪表控制系统设计阶段的失效和故障基本项覆盖统计表格。STPA方法能够很好地弥补了FMEA和FTA方法的不足。同时,在仪控系统的设计阶段,STPA方法非常适合发现反应堆紧急停堆子系统涉及的软件类、系统交互以及通信类的故障和安全问题。

For the reactor scram subsystem, the failure and fault coverage statistics form for the instrument control system design phase is deduced by the combined use of three independent basic analysis methods FMEA, FTA, and STPA. STPA method can effectively make up for the inadequacy of FMEA and FTA method. At the same time, in the instrument control system design phase, STPA method is very suitable for finding the fault and safety issues in software, system interaction and communication for the reactor scram subsystems. © 2018, Editor...