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Development of deformation model for simulation of mechanical behaviors of coated-cladding

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dc.contributor.authorKim, Dong-Hyun-
dc.contributor.authorKim, Hyo Chan-
dc.contributor.authorShin, Chang Hwan-
dc.contributor.authorKim, Hak-Sung-
dc.date.accessioned2021-08-02T12:54:19Z-
dc.date.available2021-08-02T12:54:19Z-
dc.date.created2021-05-11-
dc.date.issued2018-10-
dc.identifier.issn0022-3131-
dc.identifier.urihttps://scholarworks.bwise.kr/hanyang/handle/2021.sw.hanyang/16061-
dc.description.abstractA coated fuel cladding is one of the promising accident tolerant fuel (ATF) cladding concepts to enhance the fuel safety for accident conditions. In this study, a new analytical model called Fuel Rod and Cladding Analysis Subcode-Coated Cladding (FRACAS-CT), used to evaluate the mechanical behaviors of the ATF cladding, has been developed employing both thick-walled theory and some methodologies of the FRACAS. Based on the methodology of FRACAS, two different regimes of pellet-cladding mechanical interactions according to the gap status were considered as follows: one is an open-gap regime, and the other is a closed-gap regime. FRACAS-CT was developed within a limited scope of an elastic solution under the assumption of the prescribed creep, irradiation growth, and thermal deformation. To verify the FRACAS-CT model, an equivalent finite element (FE) model was proposed, and the mechanical behaviors of FRACAS-CT were compared with those of the equivalent FE model. As a result, it was determined that the stress results of FRACAS-CT are highly consistent with those of the equivalent FE model. Furthermore, FRACAS-CT was implemented into the FRAPCON4.0P1 code system to evaluate the mechanical behaviors of the ATF cladding using in-reactor conditions.-
dc.language영어-
dc.language.isoen-
dc.publisherTAYLOR & FRANCIS LTD-
dc.titleDevelopment of deformation model for simulation of mechanical behaviors of coated-cladding-
dc.typeArticle-
dc.contributor.affiliatedAuthorKim, Hak-Sung-
dc.identifier.doi10.1080/00223131.2018.1486243-
dc.identifier.scopusid2-s2.0-85048757876-
dc.identifier.wosid000444568300016-
dc.identifier.bibliographicCitationJOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.55, no.10, pp.1225 - 1234-
dc.relation.isPartOfJOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY-
dc.citation.titleJOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY-
dc.citation.volume55-
dc.citation.number10-
dc.citation.startPage1225-
dc.citation.endPage1234-
dc.type.rimsART-
dc.type.docTypeArticle-
dc.description.journalClass1-
dc.description.isOpenAccessN-
dc.description.journalRegisteredClassscie-
dc.description.journalRegisteredClassscopus-
dc.relation.journalResearchAreaNuclear Science & Technology-
dc.relation.journalWebOfScienceCategoryNuclear Science & Technology-
dc.subject.keywordPlusACCIDENT-TOLERANT FUEL-
dc.subject.keywordPlusREACTOR-FUEL-
dc.subject.keywordAuthorAccident tolerant fuel (ATF)-
dc.subject.keywordAuthorcoated-cladding-
dc.subject.keywordAuthormechanical behaviors-
dc.subject.keywordAuthoranalytical model-
dc.subject.keywordAuthorequivalent finite element model-
dc.subject.keywordAuthorFRACAS-CT-
dc.subject.keywordAuthorFRAPCON4.0P01-
dc.identifier.urlhttps://www.tandfonline.com/doi/full/10.1080/00223131.2018.1486243-
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