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Effect of mitigation strategies in the severe accident uncertainty analysis of the OPR1000 short-term station blackout accident

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dc.contributor.authorChoi, Wonjun-
dc.contributor.authorAhn, Kwang-Il-
dc.contributor.authorKim, Sung Joong-
dc.date.accessioned2023-05-03T14:19:23Z-
dc.date.available2023-05-03T14:19:23Z-
dc.date.created2022-09-08-
dc.date.issued2022-12-
dc.identifier.issn1738-5733-
dc.identifier.urihttps://scholarworks.bwise.kr/hanyang/handle/2021.sw.hanyang/185390-
dc.description.abstractIntegrated severe accident codes should be capable of simulating not only specific physical phenomena but also entire plant behaviors, and in a sufficiently fast time. However, significant uncertainty may exist owing to the numerous parametric models and interactions among the various phenomena. The primary objectives of this study are to present best-practice uncertainty and sensitivity analysis results regarding the evolutions of severe accidents (SAs) and fission product source terms and to determine the effects of mitigation measures on them, as expected during a short-term station blackout (STSBO) of a reference pressurized water reactor (optimized power reactor (OPR)1000). Three reference scenarios related to the STSBO accident are considered: one base and two mitigation scenarios, and the impacts of dedicated severe accident mitigation (SAM) actions on the results of interest are analyzed (such as flammable gas generation). The uncertainties are quantified based on a random set of Monte Carlo samples per case scenario. The relative importance values of the uncertain input parameters to the results of interest are quantitatively evaluated through a relevant sensitivity/importance analysis.-
dc.language영어-
dc.language.isoen-
dc.publisherKorean Nuclear Society-
dc.titleEffect of mitigation strategies in the severe accident uncertainty analysis of the OPR1000 short-term station blackout accident-
dc.typeArticle-
dc.contributor.affiliatedAuthorKim, Sung Joong-
dc.identifier.doi10.1016/j.net.2022.07.029-
dc.identifier.scopusid2-s2.0-85136093429-
dc.identifier.wosid000903546400004-
dc.identifier.bibliographicCitationNuclear Engineering and Technology, v.54, no.12, pp.4534 - 4550-
dc.relation.isPartOfNuclear Engineering and Technology-
dc.citation.titleNuclear Engineering and Technology-
dc.citation.volume54-
dc.citation.number12-
dc.citation.startPage4534-
dc.citation.endPage4550-
dc.type.rimsART-
dc.type.docTypeArticle-
dc.identifier.kciidART002902829-
dc.description.journalClass1-
dc.description.isOpenAccessY-
dc.description.journalRegisteredClassscie-
dc.description.journalRegisteredClassscopus-
dc.description.journalRegisteredClasskci-
dc.relation.journalResearchAreaNuclear Science & Technology-
dc.relation.journalWebOfScienceCategoryNuclear Science & Technology-
dc.subject.keywordPlusTUBE CREEP-RUPTURE-
dc.subject.keywordPlusPROGRESSION-
dc.subject.keywordAuthorOPR1000-
dc.subject.keywordAuthorSevere accident-
dc.subject.keywordAuthorShort-term station blackout-
dc.subject.keywordAuthorSevere accident mitigation-
dc.subject.keywordAuthorUncertainty and sensitivity analysis-
dc.identifier.urlhttps://www.sciencedirect.com/science/article/pii/S1738573322003618?via%3Dihub-
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