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Cited 12 time in webofscience Cited 15 time in scopus
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Numerical characterization of micro-cell UO₂-Mo pellet for enhanced thermal performance

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dc.contributor.authorLee, Heung Soo-
dc.contributor.authorKim, Dong-Joo-
dc.contributor.authorKim, Sun Woo-
dc.contributor.authorYang, Jae Ho-
dc.contributor.authorKoo, Yang-Hyun-
dc.contributor.authorKim, Dong Rip-
dc.date.accessioned2021-07-30T04:58:49Z-
dc.date.available2021-07-30T04:58:49Z-
dc.date.issued2016-08-
dc.identifier.issn0022-3115-
dc.identifier.issn1873-4820-
dc.identifier.urihttps://scholarworks.bwise.kr/hanyang/handle/2021.sw.hanyang/2534-
dc.description.abstractMetallic micro-cell UO₂ pellet with high thermal conductivity has received attention as a promising accident-tolerant fuel. Although experimental demonstrations have been successful, studies on the potency of current metallic micro-cell UO₂ fuels for further enhancement of thermal performance are lacking. Here, we numerically investigated the thermal conductivities of micro-cell UO₂-Mo pellets in terms of the amount of Mo content, the unit cell size, and the aspect ratio of the micro-cells. The results showed good agreement with experimental measurements, and more importantly, indicated the importance of optimizing the unit cell geometries of the micro-cell pellets for greater increases in thermal conductivity. Consequently, the micro-cell UO₂-Mo pellets (5 vol% Mo) with modified geometries increased the thermal conductivity of the current UO₂ pellets by about 2.5 times, and lowered the temperature gradient within the pellets by 62.9% under a linear heat generation rate of 200 W/cm.-
dc.format.extent7-
dc.language영어-
dc.language.isoENG-
dc.publisherElsevier BV-
dc.titleNumerical characterization of micro-cell UO₂-Mo pellet for enhanced thermal performance-
dc.typeArticle-
dc.publisher.location네델란드-
dc.identifier.doi10.1016/j.jnucmat.2016.05.005-
dc.identifier.scopusid2-s2.0-84966293186-
dc.identifier.wosid000377327000011-
dc.identifier.bibliographicCitationJournal of Nuclear Materials, v.477, pp 88 - 94-
dc.citation.titleJournal of Nuclear Materials-
dc.citation.volume477-
dc.citation.startPage88-
dc.citation.endPage94-
dc.type.docTypeArticle-
dc.description.isOpenAccessN-
dc.description.journalRegisteredClassscie-
dc.description.journalRegisteredClassscopus-
dc.relation.journalResearchAreaMaterials Science-
dc.relation.journalResearchAreaNuclear Science & Technology-
dc.relation.journalWebOfScienceCategoryMaterials Science, Multidisciplinary-
dc.relation.journalWebOfScienceCategoryNuclear Science & Technology-
dc.subject.keywordPlusFABRICATION-
dc.subject.keywordPlusCONDUCTIVITY-
dc.subject.keywordPlusFUELS-
dc.subject.keywordAuthorMicro-cell pellet-
dc.subject.keywordAuthorNuclear fuel pellet-
dc.subject.keywordAuthorAccident tolerant fuel-
dc.subject.keywordAuthorThermal conductivity-
dc.subject.keywordAuthorUO₂-
dc.subject.keywordAuthorMolybdenum-
dc.identifier.urlhttps://www.sciencedirect.com/science/article/pii/S0022311516301830?via%3Dihub-
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