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Finite element analysis model for estimating the dynamic crush strength of the spacer grid assembly for PWRs

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dc.contributor.authorSong, Kee Nam-
dc.contributor.authorYoon, Kyung Ho-
dc.contributor.authorLee, Jae Jun-
dc.contributor.authorPark, Kyung Jin-
dc.date.accessioned2021-06-23T22:39:30Z-
dc.date.available2021-06-23T22:39:30Z-
dc.date.issued2006-11-
dc.identifier.issn1013-9826-
dc.identifier.issn1662-9795-
dc.identifier.urihttps://scholarworks.bwise.kr/erica/handle/2021.sw.erica/45381-
dc.description.abstractThe spacer grid assembly, which is an interconnected array of slotted grid straps and welded at the intersections to form an egg crate structure, is one of the main structural components of the nuclear fuel assemblies of a Pressurized light Water Reactor (PWR). The spacer grid assembly is structurally required to have enough crush strength under lateral loads due to lateral seismic accelerations, lateral Loss Of Coolant Accident (LOCA) blowdown forces, and shipping and handling loads so that the fuel rods are maintained within a coolable geometry, and that the control rods are able to be inserted. The ability of the spacer grid assembly to resist the lateral loads is usually characterized in terms of its dynamic and static crush strengths, which are acquired from the relevant tests. In this study, dynamic buckling tests and finite element analyses on spacer grid assembly specimens are carried out. As a result of the comparisons, the analysis results are in good agreement with the test results to within an 8 % difference range. Therefore, we could predict the crush strength of a spacer grid assembly in advance before performing the dynamic buckling test.-
dc.format.extent4-
dc.language영어-
dc.language.isoENG-
dc.publisherTrans Tech Publications Ltd.-
dc.titleFinite element analysis model for estimating the dynamic crush strength of the spacer grid assembly for PWRs-
dc.typeArticle-
dc.publisher.location스위스-
dc.identifier.doi10.4028/www.scientific.net/KEM.324-325.1011-
dc.identifier.scopusid2-s2.0-33750902773-
dc.identifier.wosid000243377000249-
dc.identifier.bibliographicCitationKey Engineering Materials, v.324-325, pp 1011 - 1014-
dc.citation.titleKey Engineering Materials-
dc.citation.volume324-325-
dc.citation.startPage1011-
dc.citation.endPage1014-
dc.type.docTypeConference Paper-
dc.description.isOpenAccessN-
dc.description.journalRegisteredClassscie-
dc.description.journalRegisteredClassscopus-
dc.relation.journalResearchAreaMaterials Science-
dc.relation.journalResearchAreaMechanics-
dc.relation.journalWebOfScienceCategoryMaterials Science, Ceramics-
dc.relation.journalWebOfScienceCategoryMechanics-
dc.relation.journalWebOfScienceCategoryMaterials Science, Composites-
dc.subject.keywordPlusBuckling-
dc.subject.keywordPlusFinite element method-
dc.subject.keywordPlusLoss of coolant accidents-
dc.subject.keywordPlusNuclear fuels-
dc.subject.keywordPlusStrength of materials-
dc.subject.keywordPlusCrush strength-
dc.subject.keywordPlusLateral loads-
dc.subject.keywordPlusNuclear fuel assembly-
dc.subject.keywordPlusSpacer grid assembly-
dc.subject.keywordPlusPressurized water reactors-
dc.subject.keywordAuthorCrush strength-
dc.subject.keywordAuthorNuclear fuel assembly-
dc.subject.keywordAuthorPWR-
dc.subject.keywordAuthorSpacer grid assembly-
dc.identifier.urlhttps://www.scientific.net/KEM.324-325.1011-
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