Safety Analysis for Reactor Scram Subsystem Based on Multiple Methods

Liu Hua; Han Wenxing; Yang Xiaohua; Chen Zhi; Liu Zhaohui

doi:10.13832/j.jnpe.2018.03.0156

Volume 39 Issue 3

Jul. 2018

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Liu Hua, Han Wenxing, Yang Xiaohua, Chen Zhi, Liu Zhaohui. Safety Analysis for Reactor Scram Subsystem Based on Multiple Methods[J]. Nuclear Power Engineering, 2018, 39(3): 156-161. doi: 10.13832/j.jnpe.2018.03.0156

Citation:

Liu Hua, Han Wenxing, Yang Xiaohua, Chen Zhi, Liu Zhaohui. Safety Analysis for Reactor Scram Subsystem Based on Multiple Methods[J]. Nuclear Power Engineering, 2018, 39(3): 156-161. doi: 10.13832/j.jnpe.2018.03.0156

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Safety Analysis for Reactor Scram Subsystem Based on Multiple Methods

doi: 10.13832/j.jnpe.2018.03.0156

1.
School of Electrical Engineering, University of South China, Hengyang, Hunan, 421001, China
2. Nuclear Power Institute of CHINA, Chengdu, 610041, China
3. School of Computer Science and Engineering, University of South China, Hengyang, Hunan, 421001, China

Received Date: 2018-04-04
Rev Recd Date: 2018-05-03
Publish Date: 2018-07-20

Abstract

Abstract

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.
- Multiple method fusion,
- Reactor scram subsystem,
- Safety analysis