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Cited 4 time in webofscience Cited 4 time in scopus
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dc.contributor.authorLee, CH-
dc.contributor.authorKasada, R-
dc.contributor.authorKimura, A-
dc.contributor.authorLee, BS-
dc.contributor.authorSuh, DW-
dc.contributor.authorLee, HC-
dc.date.accessioned2016-03-31T08:26:38Z-
dc.date.available2016-03-31T08:26:38Z-
dc.date.created2013-11-05-
dc.date.issued2013-11-
dc.identifier.issn1598-9623-
dc.identifier.other2013-OAK-0000028130-
dc.identifier.urihttps://oasis.postech.ac.kr/handle/2014.oak/15317-
dc.description.abstractThe influence of nickel on the neutron irradiation embrittlement of Ni-Mo-Cr reactor pressure vessel (RPV) steels was investigated using alloys containing nickel in the range of 0.9-3.5 wt%. In all investigated alloys, the neutron irradiation with two dose conditions of 4.5 x 10(19) neutron/cm(2) at 290 A degrees C and 9.0 x 10(19) neutron/cm(2) at 290 A degrees C, respectively, increased the hardness and ductile-to-brittle transition temperature (DBTT). However, the increases of the hardness and DBTT resulting from the neutron irradiation were primarily affected by the irradiation dose that is closely related to the generation of irradiation defects, but not by the nickel content. In addition, a linear relationship between the changes in the hardness and DBTT subjected to the irradiation was confirmed. These results demonstrate that increasing the nickel content up to 3.5 wt% does not have a harmful effect on the irradiation embrittlement of Ni-Mo-Cr reactor pressure vessel (RPV) steels.-
dc.description.statementofresponsibilityX-
dc.languageEnglish-
dc.publisherKIM-
dc.relation.isPartOfMETALS AND MATERIALS INTERNATIONAL-
dc.subjectalloys-
dc.subjectmicrostructure-
dc.subjectfracture-
dc.subjectneutron-
dc.subjectductile-to-brittle transition temperature (DBTT)-
dc.subjectCHARPY IMPACT PROPERTIES-
dc.subjectPRESSURE-VESSEL STEELS-
dc.subjectMARTENSITIC STEEL-
dc.subjectBAINITIC STEELS-
dc.subjectMICROSTRUCTURE-
dc.subjectMECHANISM-
dc.subjectEVOLUTION-
dc.subjectSTRENGTH-
dc.titleEffect of nickel content on the neutron irradiation embrittlement of Ni-Mo-Cr steels-
dc.typeArticle-
dc.contributor.college철강대학원-
dc.identifier.doi10.1007/S12540-013-6007-X-
dc.author.googleLee, CH-
dc.author.googleKasada, R-
dc.author.googleKimura, A-
dc.author.googleLee, BS-
dc.author.googleSuh, DW-
dc.author.googleLee, HC-
dc.relation.volume19-
dc.relation.issue6-
dc.relation.startpage1203-
dc.relation.lastpage1208-
dc.contributor.id10126321-
dc.relation.journalMETALS AND MATERIALS INTERNATIONAL-
dc.relation.indexSCI급, SCOPUS 등재논문-
dc.relation.sciSCI-
dc.collections.nameJournal Papers-
dc.type.rimsART-
dc.identifier.bibliographicCitationMETALS AND MATERIALS INTERNATIONAL, v.19, no.6, pp.1203 - 1208-
dc.identifier.wosid000327080600006-
dc.date.tcdate2019-01-01-
dc.citation.endPage1208-
dc.citation.number6-
dc.citation.startPage1203-
dc.citation.titleMETALS AND MATERIALS INTERNATIONAL-
dc.citation.volume19-
dc.contributor.affiliatedAuthorSuh, DW-
dc.identifier.scopusid2-s2.0-84888412846-
dc.description.journalClass1-
dc.description.journalClass1-
dc.description.wostc1-
dc.description.scptc0*
dc.date.scptcdate2018-05-121*
dc.type.docTypeArticle-
dc.subject.keywordPlusCHARPY IMPACT PROPERTIES-
dc.subject.keywordPlusMARTENSITIC STEEL-
dc.subject.keywordPlusVESSEL-
dc.subject.keywordPlusMICROSTRUCTURE-
dc.subject.keywordPlusMECHANISM-
dc.subject.keywordPlusEVOLUTION-
dc.subject.keywordPlusSTRENGTH-
dc.subject.keywordAuthoralloys-
dc.subject.keywordAuthormicrostructure-
dc.subject.keywordAuthorfracture-
dc.subject.keywordAuthorneutron-
dc.subject.keywordAuthorductile-to-brittle transition temperature (DBTT)-
dc.relation.journalWebOfScienceCategoryMaterials Science, Multidisciplinary-
dc.relation.journalWebOfScienceCategoryMetallurgy & Metallurgical Engineering-
dc.description.journalRegisteredClassscie-
dc.description.journalRegisteredClassscopus-
dc.description.journalRegisteredClasskci-
dc.relation.journalResearchAreaMaterials Science-
dc.relation.journalResearchAreaMetallurgy & Metallurgical Engineering-

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