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The influence of solid solution hydrogen and precipitated hydride on the creep behavior of Zircaloy-4

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dc.contributor.authorKim, Ho-A-
dc.contributor.authorChoi, Sungjun-
dc.contributor.authorKim, Yong-Soo-
dc.contributor.authorPark, Jiwon-
dc.contributor.authorKang, Joo-Hee-
dc.contributor.authorKim, Sangtae-
dc.date.accessioned2024-11-28T08:27:42Z-
dc.date.available2024-11-28T08:27:42Z-
dc.date.issued2024-11-
dc.identifier.issn0022-3115-
dc.identifier.issn1873-4820-
dc.identifier.urihttps://scholarworks.bwise.kr/hanyang/handle/2021.sw.hanyang/195111-
dc.description.abstractThe effect of hydrogen on the creep rates of Zircaloy-4 claddings especially in the low hydrogen concentration remains largely unexplored while creep is considered a main mechanism for spent nuclear fuel failure along with hydride-induced mechanisms. Here, we study the influence of hydrogen on the creep behavior of low burnup Zircaloy-4 cladding from a microstructural perspective. The creep tests at 450 °C and 120 MPa reveal that specimens with hydrogen contents below the terminal solid solubility for dissolution (TSSD) at the test temperature exhibited decreased creep resistance as hydrogen concentration increased, while those with hydrogen contents above the TSSD demonstrated increased creep resistance with higher hydrogen concentration. The lowest creep resistance occurs at the hydrogen concentration corresponding to the TSSD. Additional microstructural analyses using electron backscattered diffraction (EBSD) show the increasing intra-granular/inter-granular hydride ratio in the post-crept specimens as the hydrogen concentration decreases, suggesting that hydrogen atoms in solid solution aid creep progression. Also, an increased amount of twin boundaries is observed in post-crept specimens with hydrogen concentration above TSSD. These results suggest that creep assessment in spent nuclear fuels may require caution especially in low-burnup regime.-
dc.format.extent13-
dc.language영어-
dc.language.isoENG-
dc.publisherElsevier BV-
dc.titleThe influence of solid solution hydrogen and precipitated hydride on the creep behavior of Zircaloy-4-
dc.typeArticle-
dc.publisher.location네델란드-
dc.identifier.doi10.1016/j.jnucmat.2024.155244-
dc.identifier.scopusid2-s2.0-85198010771-
dc.identifier.wosid001281632700001-
dc.identifier.bibliographicCitationJournal of Nuclear Materials, v.600, pp 1 - 13-
dc.citation.titleJournal of Nuclear Materials-
dc.citation.volume600-
dc.citation.startPage1-
dc.citation.endPage13-
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.keywordPlusSTACKING-FAULT ENERGY-
dc.subject.keywordPlusDELTA-HYDRIDE-
dc.subject.keywordPlusGRAIN-SIZE-
dc.subject.keywordPlusASSISTED CRACKING-
dc.subject.keywordPlusTHERMAL CREEP-
dc.subject.keywordPlusNUCLEAR-FUEL-
dc.subject.keywordPlusDRY STORAGE-
dc.subject.keywordPlusDEFORMATION-
dc.subject.keywordPlusZIRCONIUM-
dc.subject.keywordPlusMECHANISMS-
dc.subject.keywordAuthorElectron backscatter diffraction (EBSD)-
dc.subject.keywordAuthorMicrostructure-
dc.subject.keywordAuthorSpent nuclear fuel (SNF) cladding-
dc.subject.keywordAuthorThermal creep-
dc.subject.keywordAuthorZirconium hydride-
dc.identifier.urlhttps://www.sciencedirect.com/science/article/pii/S0022311524003465?via%3Dihub-
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