Paper Info
Title
Identification Of Risk-Significant Components In Nuclear Power Plants To Reduce Cs-137 Radioactive Risk
Abstract
The amount and frequency of Cs-137 release in a nuclear accident are regulated to enhance environmental radiation protection. While significant improvements have been accomplished, including the preparation of severe accident mitigation equipment and systems to satisfy Cs-137 regulations, no attempt has yet been made along these lines to manage the structures, systems and components (SSCs) in nuclear power plants. Therefore, this paper proposes a new approach to identify the significant SSCs by quantifying related risk importance measures using release frequency and Cs-137 radioactivity. The new approach includes a Level 1 and Level 2 probabilistic safety assessment (PSA) linked model to obtain the frequency and Cs-137 radioactivity in all accident scenarios. The developed approach was applied to an OPR-1000 full-power internal events PSA model, and as a result, the top 20 SSCs were identified based on Fussell-Vesely importance, risk reduction worth, and risk achievement worth measures. The new approach can support risk-informed management for not only Cs-137 regulations but also public risk by using early and latent cancer fatalities.
Year
DOI
Venue
2021
10.1016/j.ress.2021.107613
RELIABILITY ENGINEERING & SYSTEM SAFETY
Keywords
DocType
Volume
Probabilistic safety assessment, Minimal cut set, Basic event, Risk importance measure, Fussell-Vesely, Risk achievement worth, Cs-137
Journal
211
ISSN
Citations 
PageRank 
0951-8320
0
0.34
References 
Authors
0
2
Name
Order
Citations
PageRank
Jae-Hyun Cho12011.08
Sang-Hoon Han292.25