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Radial hydride fraction with various rod internal pressures and hydrogen contents for Zr-Nb alloy cladding tube

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dc.contributor.authorKim, Dongyeon-
dc.contributor.authorWoo, Dahyeon-
dc.contributor.authorLee, Youho-
dc.date.accessioned2023-01-02T08:33:40Z-
dc.date.available2023-01-02T08:33:40Z-
dc.date.created2022-12-12-
dc.date.issued2022-12-
dc.identifier.citationJournal of Nuclear Materials, Vol.572, p. 154036-
dc.identifier.issn0022-3115-
dc.identifier.urihttps://hdl.handle.net/10371/188838-
dc.description.abstractHydride reorientation experiments for unirradiated Zr-Nb alloy cladding tubes under multi-axial stress states induced by internal pressurization were performed with peak cladding temperature set to 400 degrees C. Applied internal pressure was held constant during cooling down stage. PROPHET was used to analyze Radial Hydride Fraction (RHF) of tested cladding tubes. The attained RHF behavior for a wide range of rod internal pressure (7.5-18.5 MPa) and hydrogen content (0-1100 wppm) were investigated. Empirical models for RHF with respect to rod internal pressure and hydride contents were developed. Ring com-pression tests (RCTs) were conducted to investigate toughness (strain energy density) change with radial hydride formation. In order to take the multi-axial stress effect into account, rod internal pressure-based regulation is necessary. Hydride reorientation threshold rod internal pressure is-9.32 MPa. The rod in-ternal pressure corresponding to hoop stress of 90 MPa is 11.5 MPa, indicating that hydride reorientation in multi-axially stressed Zircaloy cladding tube occurs at hoop stresses below 90 MPa. The presented thermodynamic model for threshold rod internal pressure gives improved agreement with experimen-tally measured threshold with input the directly measured orientation relationship between 8-hydride and a-Zr.(c) 2022 Elsevier B.V. All rights reserved.-
dc.language영어-
dc.publisherElsevier BV-
dc.titleRadial hydride fraction with various rod internal pressures and hydrogen contents for Zr-Nb alloy cladding tube-
dc.typeArticle-
dc.identifier.doi10.1016/j.jnucmat.2022.154036-
dc.citation.journaltitleJournal of Nuclear Materials-
dc.identifier.wosid000884909900001-
dc.identifier.scopusid2-s2.0-85139398157-
dc.citation.startpage154036-
dc.citation.volume572-
dc.description.isOpenAccessN-
dc.contributor.affiliatedAuthorLee, Youho-
dc.type.docTypeArticle-
dc.description.journalClass1-
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