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Cited 26 time in webofscience Cited 30 time in scopus
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dc.contributor.authorGigax Jonathan G.-
dc.contributor.authorKennas Miltiadis-
dc.contributor.authorKim Hyosim-
dc.contributor.authorMaier Benjamin R.-
dc.contributor.authorYeom Hwasung-
dc.contributor.authorJohnson Greg O.-
dc.contributor.authorSridharan Kumar-
dc.contributor.authorShao Lin-
dc.date.accessioned2023-09-22T02:41:04Z-
dc.date.available2023-09-22T02:41:04Z-
dc.date.created2023-09-21-
dc.date.issued2019-06-
dc.identifier.issn0022-3115-
dc.identifier.urihttps://oasis.postech.ac.kr/handle/2014.oak/118885-
dc.description.abstractFeCrAl has been proposed as a coating layer to enhance accident tolerance of Zircaloy-4 fuel cladding. In this study, we systematically examined the diffusion kinetics and interface compound formation of the spray-coated FeCrAl and Zircaloy-4 substrate. After vacuum annealing at 923 K, 963 K, and 998 K for various time periods, a mixed Zr2Fe phase and Zr3Fe formed at the interface. The formation energies of these two phases were found to be 65 kJ/mol and 58 kJ/mol for Zr2Fe and Zr3Fe, respectively. Bending tests of cantilevers prepared by a focused ion beam technique showed good interface bonding between the coating layer and the substrate. Nanoindentation and micropillar compression tests in the cross-section of polished samples show different mechanical responses of each phase. The substrate exhibited the lowest hardness and most ductile deformation under compression, while interfacial Zr2Fe and Zr3Fe possessed the highest hardness and brittle failure. (C) 2019 Elsevier B.V. All rights reserved.-
dc.languageEnglish-
dc.publisherElsevier BV-
dc.relation.isPartOfJournal of Nuclear Materials-
dc.titleInterface reactions and mechanical properties of FeCrAl-coated Zircaloy-4-
dc.typeArticle-
dc.identifier.doi10.1016/j.jnucmat.2019.03.004-
dc.type.rimsART-
dc.identifier.bibliographicCitationJournal of Nuclear Materials, v.519, pp.57 - 63-
dc.identifier.wosid000465088900007-
dc.citation.endPage63-
dc.citation.startPage57-
dc.citation.titleJournal of Nuclear Materials-
dc.citation.volume519-
dc.contributor.affiliatedAuthorYeom Hwasung-
dc.identifier.scopusid2-s2.0-85063378885-
dc.description.journalClass1-
dc.description.journalClass1-
dc.description.isOpenAccessN-
dc.type.docTypeArticle-
dc.description.journalRegisteredClassscie-
dc.description.journalRegisteredClassscopus-

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염화성YEOM, HWASUNG
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