Detailed Information

Cited 0 time in webofscience Cited 0 time in scopus
Metadata Downloads

Microstructure and mechanical properties of hydride blisters formed on Zircaloy-4 claddings

Full metadata record
DC Field Value Language
dc.contributor.authorKim, Ho-A-
dc.contributor.authorKim, Ju-Seong-
dc.contributor.authorLee, Yundong-
dc.contributor.authorKim, Sangbum-
dc.contributor.authorLee, Youho-
dc.contributor.authorKim, Yong-Soo-
dc.contributor.authorKang, Joo-Hee-
dc.contributor.authorKim, Sangtae-
dc.date.accessioned2023-11-14T08:16:00Z-
dc.date.available2023-11-14T08:16:00Z-
dc.date.issued2024-01-
dc.identifier.issn0022-3115-
dc.identifier.issn1873-4820-
dc.identifier.urihttps://scholarworks.bwise.kr/hanyang/handle/2021.sw.hanyang/192176-
dc.description.abstractTo assess the microstructural and mechanical characteristics of hydride blisters formed on Zircaloy-4 tubes, we employ the electron backscatter diffraction (EBSD) analyses and micro-cantilever failure tests directly on the hydride blister (HB) area. In the HB area, more than 70% of the blister area is characterized to be δ-hydride, and the HB area does not favor the orientation relation ((101¯1)α//(001)δ, [12¯10]α//[1¯10]δ) that is otherwise well-matched in the Zr matrix area. The geometrically necessary dislocation density is observed in the entire blister area, indicating a large amount of strain throughout the blister area. Also, the deformation strain is concentrated in both the hydride and α-Zr phases of HB areas; however, the hydride underwent intensive deformation in the Zr matrix. The average fracture toughness of the hydride blister area obtained through the micro-cantilever test is 1.81 MPam, indicating a brittle fracture that may threaten the integrity of spent nuclear fuel claddings.-
dc.format.extent13-
dc.language영어-
dc.language.isoENG-
dc.publisherElsevier BV-
dc.titleMicrostructure and mechanical properties of hydride blisters formed on Zircaloy-4 claddings-
dc.typeArticle-
dc.publisher.location네델란드-
dc.identifier.doi10.1016/j.jnucmat.2023.154777-
dc.identifier.scopusid2-s2.0-85174692909-
dc.identifier.wosid001106380500001-
dc.identifier.bibliographicCitationJournal of Nuclear Materials, v.588, pp 1 - 13-
dc.citation.titleJournal of Nuclear Materials-
dc.citation.volume588-
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.keywordPlusBackscattering-
dc.subject.keywordPlusBrittle fracture-
dc.subject.keywordPlusDuctile fracture-
dc.subject.keywordPlusElectron diffraction-
dc.subject.keywordPlusFracture toughness-
dc.subject.keywordPlusHydrides-
dc.subject.keywordPlusZirconium alloys-
dc.subject.keywordPlusZirconium compounds-
dc.subject.keywordAuthorElectron backscatter diffraction (EBSD)-
dc.subject.keywordAuthorFracture toughness-
dc.subject.keywordAuthorHydride blister-
dc.subject.keywordAuthorMicro-cantilever-
dc.subject.keywordAuthorZirconium-based claddings-
dc.identifier.urlhttps://www.sciencedirect.com/science/article/pii/S0022311523005445?via%3Dihub-
Files in This Item
Go to Link
Appears in
Collections
서울 공과대학 > 서울 원자력공학과 > 1. Journal Articles

qrcode

Items in ScholarWorks are protected by copyright, with all rights reserved, unless otherwise indicated.

Related Researcher

Researcher Kim, Sang tae photo

Kim, Sang tae
COLLEGE OF ENGINEERING (DEPARTMENT OF NUCLEAR ENGINEERING)
Read more

Altmetrics

Total Views & Downloads

BROWSE