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COFUN: A new tool for evaluating containment failure frequency and uncertainty

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dc.contributor.authorLim, Dohyun-
dc.contributor.authorAhn, Byeongmun-
dc.contributor.authorJae, Moosung-
dc.date.accessioned2025-08-14T06:30:32Z-
dc.date.available2025-08-14T06:30:32Z-
dc.date.issued2025-03-
dc.identifier.issn1738-5733-
dc.identifier.issn2234-358X-
dc.identifier.urihttps://scholarworks.bwise.kr/hanyang/handle/2021.sw.hanyang/208528-
dc.description.abstractThe feature of the COntainment Failure probability and Uncertainty aNalysis program (COFUN) is the quantification of the containment state. The probability factors used in probabilistic safety assessment (PSA) and the resulting outputs contain probability bands, so it is necessary to present the uncertainty bands as results. The uncertainty analysis process of the level 2 PSA is that a level 1 PSA uncertainty propagates to a level 2 PSA uncertainty. The basic event data including probability distribution were used for the level 1 PSA uncertainty analysis and probability distribution and priority of the fractional branch point were used for uncertainty analysis in a level 2 PSA. Once the input is ready, uncertainty analysis is performed via Monte-Carlo sampling. Finally, the uncertainty analysis can be performed for source term category (STC) and large early release frequency (LERF). One of the outstanding characteristics of the COFUN is to perform level 2 PSA for multi-unit accidents. The one of formats of multi-unit level 2 PSA is the combination of STCs but the combinations could be too many to acquire insight by STC combination itself. The COFUN provides a user-defined combination that makes STC combinations classified and enables the derivation of multi-unit accident LERF result.-
dc.format.extent8-
dc.language영어-
dc.language.isoENG-
dc.publisher한국원자력학회-
dc.titleCOFUN: A new tool for evaluating containment failure frequency and uncertainty-
dc.typeArticle-
dc.publisher.location대한민국-
dc.identifier.doi10.1016/j.net.2024.10.023-
dc.identifier.scopusid2-s2.0-85208491652-
dc.identifier.wosid001428509600001-
dc.identifier.bibliographicCitationNuclear Engineering and Technology, v.57, no.3, pp 1 - 8-
dc.citation.titleNuclear Engineering and Technology-
dc.citation.volume57-
dc.citation.number3-
dc.citation.startPage1-
dc.citation.endPage8-
dc.type.docTypeArticle-
dc.identifier.kciidART003173803-
dc.description.isOpenAccessY-
dc.description.journalRegisteredClassscie-
dc.description.journalRegisteredClassscopus-
dc.description.journalRegisteredClasskci-
dc.relation.journalResearchAreaNuclear Science & Technology-
dc.relation.journalWebOfScienceCategoryNuclear Science & Technology-
dc.subject.keywordAuthorLevel 2 probabilistic safety assessment-
dc.subject.keywordAuthorMulti-unit PSA-
dc.subject.keywordAuthorNuclear safety-
dc.subject.keywordAuthorSensitivity analysis-
dc.subject.keywordAuthorUncertainty analysis-
dc.identifier.urlhttps://www.sciencedirect.com/science/article/pii/S1738573324005114?via%3Dihub-
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