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Indefinite sustainability of passive residual heat removal system of small modular reactor using dry air cooling tower

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dc.contributor.authorNa, Min Wook-
dc.contributor.authorShin, Doyoung-
dc.contributor.authorPark, Jae Hyung-
dc.contributor.authorLee, Jeong Ik-
dc.contributor.authorKim, Sung Joong-
dc.date.accessioned2021-08-02T09:27:48Z-
dc.date.available2021-08-02T09:27:48Z-
dc.date.created2021-05-12-
dc.date.issued2020-05-
dc.identifier.issn1738-5733-
dc.identifier.urihttps://scholarworks.bwise.kr/hanyang/handle/2021.sw.hanyang/9829-
dc.description.abstractThe small modular reactors (SMRs) of the integrated pressurized water reactor (IPWR) type have been widely developed owing to their enhanced safety features. The SMR-IPWR adopts passive residual heat removal system (PRHRS) to extract residual heat from the core. Because the PRHRS removes the residual heat using the latent heat of the water stored in the emergency cooldown tank, the PRHRS gradually loses its cooling capacity after the stored water is depleted. A quick restoration of the power supply is expected infeasible under station blackout accident condition, so an advanced PRHRS is needed to ensure an extended grace period. In this study, an advanced design is proposed to indirectly incorporate a dry air cooling tower to the PRHRS through an intermediate loop called indefinite PRHRS. The feasibility of the indefinite PRHRS was assessed through a long-term transient simulation using the MARS-KS code. The indefinite PRHRS is expected to remove the residual heat without depleting the stored water. The effect of the environmental temperature on the indefinite PRHRS was confirmed by parametric analysis using comparative simulations with different environmental temperatures.-
dc.language영어-
dc.language.isoen-
dc.publisherKOREAN NUCLEAR SOC-
dc.titleIndefinite sustainability of passive residual heat removal system of small modular reactor using dry air cooling tower-
dc.typeArticle-
dc.contributor.affiliatedAuthorKim, Sung Joong-
dc.identifier.doi10.1016/j.net.2019.11.003-
dc.identifier.scopusid2-s2.0-85075360620-
dc.identifier.wosid000526899400011-
dc.identifier.bibliographicCitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.52, no.5, pp.964 - 974-
dc.relation.isPartOfNUCLEAR ENGINEERING AND TECHNOLOGY-
dc.citation.titleNUCLEAR ENGINEERING AND TECHNOLOGY-
dc.citation.volume52-
dc.citation.number5-
dc.citation.startPage964-
dc.citation.endPage974-
dc.type.rimsART-
dc.type.docTypeArticle-
dc.identifier.kciidART002584323-
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.keywordPlusSTATION BLACKOUT SCENARIO-
dc.subject.keywordPlusTRANSIENT ANALYSES-
dc.subject.keywordPlusSAFETY FEATURES-
dc.subject.keywordPlusNATURAL CIRCULATION-
dc.subject.keywordPlusDESIGN-
dc.subject.keywordPlusPERFORMANCE-
dc.subject.keywordPlusSIMULATION-
dc.subject.keywordPlusCONVECTION-
dc.subject.keywordAuthorPassive residual heat removal system-
dc.subject.keywordAuthordry air cooling tower-
dc.subject.keywordAuthorSmall modular reactor-
dc.subject.keywordAuthorEmergency cooling sustainability-
dc.subject.keywordAuthorGrace period-
dc.subject.keywordAuthorMARS-KS-
dc.identifier.urlhttps://www.sciencedirect.com/science/article/pii/S1738573319305662?via%3Dihub-
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