DC Field | Value | Language |
---|---|---|
dc.contributor.author | Khalaquzzman, Mohammad | ko |
dc.contributor.author | Kang, Hyun-Gook | ko |
dc.contributor.author | Kim, Man-Cheol | ko |
dc.contributor.author | Seong, Poong-Hyun | ko |
dc.date.accessioned | 2013-03-11T23:01:50Z | - |
dc.date.available | 2013-03-11T23:01:50Z | - |
dc.date.created | 2012-02-06 | - |
dc.date.created | 2012-02-06 | - |
dc.date.issued | 2010-10 | - |
dc.identifier.citation | NUCLEAR ENGINEERING AND DESIGN, v.240, no.10, pp.2963 - 2971 | - |
dc.identifier.issn | 0029-5493 | - |
dc.identifier.uri | http://hdl.handle.net/10203/100598 | - |
dc.description.abstract | Modeling of spurious activations in safety instrumented systems has been studied for over a decade. The spurious activation of a plant protection system in nuclear power plants (NPPs) leads to increased electricity generation cost. An in-depth view on spurious activation of digital plant protection systems of NPPs for human errors in maintenance tasks is presented in this paper. A new model which considers human errors in maintenance and periodic tests to predict component failure rates is presented. The model has been applied to OPR-1000 reactor protection system for quantification of spurious trip frequency by fault-tree analysis. The major causes of spurious activation in a nuclear reactor protection system are identified. A set of case studies has been performed with the variation of magnitudes of human errors probability and maintenance strategies, in which, the human errors in maintenance are found to significantly influence reactor spurious trip frequency. This study is expected to provide a useful mean to designers as well as maintainers of the digital reactor protection system to improve plant availability and safety. (C) 2010 Elsevier B.V. All rights reserved. | - |
dc.language | English | - |
dc.publisher | ELSEVIER SCIENCE SA | - |
dc.subject | SAFETY INSTRUMENTED SYSTEMS | - |
dc.title | A model for estimation of reactor spurious shutdown rate considering maintenance human errors in reactor protection system of nuclear power plants | - |
dc.type | Article | - |
dc.identifier.wosid | 000284079000071 | - |
dc.identifier.scopusid | 2-s2.0-77957702545 | - |
dc.type.rims | ART | - |
dc.citation.volume | 240 | - |
dc.citation.issue | 10 | - |
dc.citation.beginningpage | 2963 | - |
dc.citation.endingpage | 2971 | - |
dc.citation.publicationname | NUCLEAR ENGINEERING AND DESIGN | - |
dc.contributor.localauthor | Seong, Poong-Hyun | - |
dc.contributor.nonIdAuthor | Kang, Hyun-Gook | - |
dc.contributor.nonIdAuthor | Kim, Man-Cheol | - |
dc.type.journalArticle | Article; Proceedings Paper | - |
dc.subject.keywordPlus | SAFETY INSTRUMENTED SYSTEMS | - |
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