Full Text

Turn on search term navigation

Copyright © 2020 Qingzhu Liang et al. This is an open access article distributed under the Creative Commons Attribution License (the “License”), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited. Notwithstanding the ProQuest Terms and Conditions, you may use this content in accordance with the terms of the License. https://creativecommons.org/licenses/by/4.0/

Abstract

The aim of this study is to verify if the reliability of a digital four-channel RPS under the design phase satisfies the specified target and to identify the weakness of system design and potential solutions for system reliability improvement. The event-tree/fault-tree (ET/FT), which is the method used in the current probabilistic safety assessment (PSA) framework of nuclear power plants (NPPs), was adopted to developed reliability modeling for the RPS with the Top Events defined as the system failure to generate reactor trip signal and the system generating spurious trip signal. The evaluation results indicate that the probability of the system failure on demand and the frequency of spurious trip signal generation are 1.47 × 10−6 with a 95% upper bound of 4.63 × 10−6 and 7.94 × 10−4/year with a 95% upper bound of 2.50 × 10−3/year, respectively. The importance and sensitivity analyses were conducted and it was found that undetected unsafe common cause failures (CCFs) of signal conditioning modules (SCMs) dominate the system reliability. Two preliminary optimization schemes relative to reducing periodic test interval and adapting two kinds of diverse SCMs were proposed. Results of the quantitive evaluation of the schemes show that neither of them could determinedly improve the system reliability to the target level. In the future, more detailed optimization analysis shall be required to determine a feasible system design optimization scheme.

Details

Title
Reliability Assessment for a Safety-Related Digital Reactor Protection System Using Event-Tree/Fault-Tree (ET/FT) Method
Author
Liang, Qingzhu 1 ; Liu, Mingxing 2 ; Xiao, Peng 2 ; Guo, Yun 1 ; Xiao, Jun 3   VIAFID ORCID Logo  ; Peng, Changhong 1 

 School of Nuclear Science and Technology, University of Science and Technology of China, Hefei, China 
 Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, China 
 Nuclear and Radiation Safety Center, Ministry of Ecology and Environment (MEE) of the People’s Republic of China, Beijing, China 
Editor
Massimo Zucchetti
Publication year
2020
Publication date
2020
Publisher
John Wiley & Sons, Inc.
ISSN
16876075
e-ISSN
16876083
Source type
Scholarly Journal
Language of publication
English
ProQuest document ID
2469680304
Copyright
Copyright © 2020 Qingzhu Liang et al. This is an open access article distributed under the Creative Commons Attribution License (the “License”), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited. Notwithstanding the ProQuest Terms and Conditions, you may use this content in accordance with the terms of the License. https://creativecommons.org/licenses/by/4.0/