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Evaluation of thermomechanical behaviors of UO₂-5 vol% Mo nuclear fuel pellets with sandwiched configuration

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dc.contributor.authorLee, Heung Soo-
dc.contributor.authorKim, Dong-Joo-
dc.contributor.authorKim, Dong-Seok-
dc.contributor.authorKim, Dong Rip-
dc.date.accessioned2021-08-02T08:51:44Z-
dc.date.available2021-08-02T08:51:44Z-
dc.date.created2021-05-12-
dc.date.issued2020-10-
dc.identifier.issn0022-3115-
dc.identifier.urihttps://scholarworks.bwise.kr/hanyang/handle/2021.sw.hanyang/8880-
dc.description.abstractDeploying high thermal conductive materials as additives to UO₂ has been highlighted due to their enhanced thermal performance as a potential candidate of Accident-Tolerant Fuels (ATFs). Herein, we investigate thermomechanical behaviors of UO₂ - 5 vol% Mo fuel pellets with a sandwiched configuration where Mo layers are positioned on the top and bottom of a UO₂ part. The successfully fabricated sandwich-type UO₂ fuel pellets with an inclusion of 5 vol% Mo by using a conventional sintering method exhibit up to 3.0 and 2.5 times higher effective thermal conductivities at 800 degrees C than standard UO₂ and dispersion-type UO₂ - 5 vol% Mo fuel pellets, due to the effective heat transfer characteristics in the Light Water Reactor (LWR) fuel. Accordingly, the sandwich-type fuel pellets not only effectively reduce the thermal stress gradients across the pellets, but also significantly decrease the maximum tensile hoop stresses of fuel pellets. Finally, the radial deformation behaviors of the sandwich-type fuel pellets are also investigated under a simulated irradiation condition, showing that an hourglass-shaped deformation of UO₂ pellets are considerably mitigated.-
dc.language영어-
dc.language.isoen-
dc.publisherELSEVIER-
dc.titleEvaluation of thermomechanical behaviors of UO₂-5 vol% Mo nuclear fuel pellets with sandwiched configuration-
dc.typeArticle-
dc.contributor.affiliatedAuthorKim, Dong Rip-
dc.identifier.doi10.1016/j.jnucmat.2020.152295-
dc.identifier.scopusid2-s2.0-85087159527-
dc.identifier.wosid000562377500013-
dc.identifier.bibliographicCitationJOURNAL OF NUCLEAR MATERIALS, v.539, pp.1 - 9-
dc.relation.isPartOfJOURNAL OF NUCLEAR MATERIALS-
dc.citation.titleJOURNAL OF NUCLEAR MATERIALS-
dc.citation.volume539-
dc.citation.startPage1-
dc.citation.endPage9-
dc.type.rimsART-
dc.type.docTypeArticle-
dc.description.journalClass1-
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.keywordPlusENHANCED THERMAL-CONDUCTIVITY-
dc.subject.keywordPlusACCIDENT-TOLERANT FUELS-
dc.subject.keywordPlusURANIUM-DIOXIDE-
dc.subject.keywordPlusCOMPOSITE FUEL-
dc.subject.keywordPlusNEUTRON-IRRADIATION-
dc.subject.keywordPlusFABRICATION-
dc.subject.keywordPlusMOLYBDENUM-
dc.subject.keywordPlusTEMPERATURE-
dc.subject.keywordPlusPERFORMANCE-
dc.subject.keywordPlusOXIDATION-
dc.subject.keywordAuthorNuclear fuel pellet-
dc.subject.keywordAuthorAccident tolerant fuel-
dc.subject.keywordAuthorThermal conductivity-
dc.subject.keywordAuthorThermal expansion-
dc.subject.keywordAuthorUO₂-
dc.subject.keywordAuthorMolybdenum-
dc.subject.keywordAuthorSandwich-type fuel pellet-
dc.identifier.urlhttps://www.sciencedirect.com/science/article/pii/S0022311520306887?via%3Dihub-
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