Comparison of two approaches for establishing performance criteria related to Maintenance Rule
DC Field | Value | Language |
---|---|---|
dc.contributor.author | Jerng, Dong-Wook | - |
dc.contributor.author | Kim, Man Cheol | - |
dc.date.available | 2019-03-08T18:00:16Z | - |
dc.date.issued | 2015-01 | - |
dc.identifier.issn | 0022-3131 | - |
dc.identifier.issn | 1881-1248 | - |
dc.identifier.uri | https://scholarworks.bwise.kr/cau/handle/2019.sw.cau/9978 | - |
dc.description.abstract | Probabilistic safety assessment (PSA) serves as a tool for systemically analyzing the safety of nuclear power plants. This paper explains and compares two approaches for the establishment of performance criteria related to the Maintenance Rule: (1) the individual reliability-based approach, and (2) the PSA importance measure-based approach. Different characteristics of the two approaches were compared in a qualitative manner, while a quantitative comparison was performed through application of the two approaches to a nuclear power plant. It was observed that the individual reliability-based approach resulted in more conservative performance criteria, compared to the PSA importance measure-based approach. It is thus expected that the PSA importance measure-based approach will allow for more flexible maintenance policy under conditions of limited resources, while providing for a macroscopic view of overall plant safety. Based on insights derived through this analysis, we emphasize the importance of a balance between reliability and safety significance, and propose a balance measure accordingly. The conclusions of this analysis are likely to be applicable to other types of nuclear power plants. | - |
dc.format.extent | 9 | - |
dc.language | 영어 | - |
dc.language.iso | ENG | - |
dc.publisher | TAYLOR & FRANCIS LTD | - |
dc.title | Comparison of two approaches for establishing performance criteria related to Maintenance Rule | - |
dc.type | Article | - |
dc.identifier.doi | 10.1080/00223131.2014.933682 | - |
dc.identifier.bibliographicCitation | JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.52, no.1, pp 122 - 130 | - |
dc.description.isOpenAccess | N | - |
dc.identifier.wosid | 000346587100011 | - |
dc.identifier.scopusid | 2-s2.0-84919868384 | - |
dc.citation.endPage | 130 | - |
dc.citation.number | 1 | - |
dc.citation.startPage | 122 | - |
dc.citation.title | JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | - |
dc.citation.volume | 52 | - |
dc.type.docType | Article | - |
dc.publisher.location | 영국 | - |
dc.subject.keywordAuthor | safety assessment | - |
dc.subject.keywordAuthor | PSA | - |
dc.subject.keywordAuthor | performance criteria | - |
dc.subject.keywordAuthor | risk achievement worth | - |
dc.subject.keywordAuthor | Maintenance Rule | - |
dc.subject.keywordAuthor | reliability | - |
dc.subject.keywordAuthor | Poisson distribution | - |
dc.relation.journalResearchArea | Nuclear Science & Technology | - |
dc.relation.journalWebOfScienceCategory | Nuclear Science & Technology | - |
dc.description.journalRegisteredClass | sci | - |
dc.description.journalRegisteredClass | scie | - |
dc.description.journalRegisteredClass | scopus | - |
Items in ScholarWorks are protected by copyright, with all rights reserved, unless otherwise indicated.
84, Heukseok-ro, Dongjak-gu, Seoul, Republic of Korea (06974)02-820-6194
COPYRIGHT 2019 Chung-Ang University All Rights Reserved.
Certain data included herein are derived from the © Web of Science of Clarivate Analytics. All rights reserved.
You may not copy or re-distribute this material in whole or in part without the prior written consent of Clarivate Analytics.