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Comparisons of performance and operation characteristics for closed- and open-loop passive containment cooling system design

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dc.contributor.authorBang, J.-
dc.contributor.authorJerng, D.-W.-
dc.contributor.authorKim, H.-
dc.date.accessioned2021-07-16T05:41:18Z-
dc.date.available2021-07-16T05:41:18Z-
dc.date.issued2021-08-
dc.identifier.issn1738-5733-
dc.identifier.urihttps://scholarworks.bwise.kr/cau/handle/2019.sw.cau/47588-
dc.description.abstractPassive containment cooling systems (PCCSs) have been actively studied to improve the inherent safety of nuclear power plants. Hered, we present two concepts, open-loop PCCS (OL-PCCS) and closed-loop PCCS (CL-PCCS), applicable to the PWR with a concrete-type containment. We analyzed the heat-removal performance and flow instability of these PCCS concepts using the GOTHIC code. In both cases, PCCS performance improved when a passive containment cooling heat exchanger (PCCX) was installed in the lower part of the containment building. The OL-PCCS was found to be superior in terms of heat-removal performance. However, in terms of flow instability, the OL-PCCS was more vulnerable than the CL-PCCS. In particular, the possibility of flow instability was higher when the PCCX was installed in the upper part of the containment. Therefore, the installation location of the OL-PCCS should be restricted to minimize flow instability. Conversely, a CL-PCCS can be installed without any positional restriction by adjusting the initial system pressure within the loop, which eliminates flow instability. These results could be used as base data for the thermo-hydraulic evaluation of PCCS in PWR with a large dry concrete-type containment. © 2021-
dc.format.extent10-
dc.language영어-
dc.language.isoENG-
dc.publisherKorean Nuclear Society-
dc.titleComparisons of performance and operation characteristics for closed- and open-loop passive containment cooling system design-
dc.title.alternativeComparisons of performance and operation characteristics for closed- and open-loop passive containment cooling system design-
dc.typeArticle-
dc.identifier.doi10.1016/j.net.2021.01.039-
dc.identifier.bibliographicCitationNuclear Engineering and Technology, v.53, no.8, pp 2499 - 2508-
dc.identifier.kciidART002739044-
dc.description.isOpenAccessN-
dc.identifier.wosid000671556200007-
dc.identifier.scopusid2-s2.0-85101418167-
dc.citation.endPage2508-
dc.citation.number8-
dc.citation.startPage2499-
dc.citation.titleNuclear Engineering and Technology-
dc.citation.volume53-
dc.type.docTypeArticle-
dc.publisher.location대한민국-
dc.subject.keywordAuthorFlow instability-
dc.subject.keywordAuthorGOTHIC code-
dc.subject.keywordAuthorPassive containment cooling systems-
dc.subject.keywordPlus2-PHASE FLOW INSTABILITY-
dc.subject.keywordPlusAPR PLUS-
dc.subject.keywordPlusHEAT-
dc.subject.keywordPlusOSCILLATION-
dc.subject.keywordPlusVALIDATION-
dc.subject.keywordPlusSTABILITY-
dc.subject.keywordPlusREACTOR-
dc.subject.keywordPlusCODE-
dc.relation.journalResearchAreaNuclear Science & Technology-
dc.relation.journalWebOfScienceCategoryNuclear Science & Technology-
dc.description.journalRegisteredClassscie-
dc.description.journalRegisteredClassscopus-
dc.description.journalRegisteredClasskci-
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