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dc.contributor.author김용수-
dc.date.accessioned2016-05-23T08:01:23Z-
dc.date.available2016-05-23T08:01:23Z-
dc.date.issued2015-01-
dc.identifier.citationJOURNAL OF NUCLEAR MATERIALS, v. 456, Page. 246-252en_US
dc.identifier.issn0022-3115-
dc.identifier.urihttp://hdl.handle.net/20.500.11754/21264-
dc.identifier.urihttp://www.sciencedirect.com/science/article/pii/S0022311514006229-
dc.description.abstractA study of the radial hydride formation in cold worked and stress relieved (CWSR) Zircaloy-4 cladding was performed using a ring tensile method and finite element analysis. Un-irradiated Zircaloy-4 cladding ring specimens charged with hydrogen were tested at various temperatures and loading conditions. Measured threshold stresses at loaded temperatures of 400 degrees C, 335 degrees C, 300 degrees C, and 235 degrees C turned out to be 60 +/- 5 MPa, 68 +/- 5 MPa, 75 +/- 6 MPa, and 90 +/- 6 MPa, respectively, demonstrating the tendency of decreasing threshold stress with increasing temperature. These stresses were lower than previously reported ones and close to the lower bound of collected data from the literature. These results reveal that high temperature preheating seems to affect an initiation of the reorientation. This implies that temperature increase caused by the vacuum drying of spent fuel assemblies for transportation can promote the hydride reorientation, leading to mechanical deterioration of the cladding. (C) 2014 Elsevier B.V. All rights reserved.en_US
dc.description.sponsorshipThis work was partly supported by the Nuclear Safety Research Program through the Korea Radiation Safety Foundation (KORSAFe) and the Nuclear Safety and Security Commission (NSSC), South Korea (Grant No. 1305009).-
dc.language.isoenen_US
dc.publisherELSEVIER SCIENCE BVen_US
dc.subjectEMBRITTLEMENTen_US
dc.subjectSPENT FUEL INTEGRITYen_US
dc.subjectINTERIM DRY STORAGEen_US
dc.subjectMECHANICAL-PROPERTIESen_US
dc.subjectTERMINAL SOLUBILITYen_US
dc.subjectORIENTED HYDRIDESen_US
dc.subjectFORMING METALSen_US
dc.subjectPRESSURE TUBEen_US
dc.subjectHYDROGENen_US
dc.subjectZIRCONIUMen_US
dc.titleA study on hydride reorientation of Zircaloy-4 cladding tube under stressen_US
dc.typeArticleen_US
dc.relation.volume456-
dc.identifier.doi10.1016/j.jnucmat.2014.09.032-
dc.relation.page246-252-
dc.relation.journalJOURNAL OF NUCLEAR MATERIALS-
dc.contributor.googleauthorKim, Yong-Soo-
dc.contributor.googleauthorKim, Young-Jun-
dc.contributor.googleauthorKim, Ju-Seong-
dc.contributor.googleauthorKook, Dong-Hak-
dc.relation.code2015003423-
dc.sector.campusS-
dc.sector.daehakCOLLEGE OF ENGINEERING[S]-
dc.sector.departmentDEPARTMENT OF NUCLEAR ENGINEERING-
dc.identifier.pidyongskim-
Appears in Collections:
COLLEGE OF ENGINEERING[S](공과대학) > NUCLEAR ENGINEERING(원자력공학과) > Articles
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