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Effect of strain rate and stress triaxiality on fracture strain of 304 stainless steels for canister impact simulation

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dc.contributor.authorSeo, Jun-Min-
dc.contributor.authorKim, Hune-Tae-
dc.contributor.authorKim, Yun-Jae-
dc.contributor.authorYamada, Hiroyuki-
dc.contributor.authorKumagai, Tomohisa-
dc.contributor.authorTokunaga, Hayato-
dc.contributor.authorMiura, Naoki-
dc.date.accessioned2022-08-10T19:40:31Z-
dc.date.available2022-08-10T19:40:31Z-
dc.date.created2022-08-10-
dc.date.issued2022-07-
dc.identifier.issn1738-5733-
dc.identifier.urihttps://scholar.korea.ac.kr/handle/2021.sw.korea/142771-
dc.description.abstractIn this paper, smooth and notched bar tensile tests of austenitic stainless steel 304 are performed, covering four different multi-axial stress states and six different strain rate conditions, to investigate the effect of the stress triaxiality and strain rate on fracture strain. Test data show that the measured true fracture strain tends to decrease with increasing stress triaxiality and strain rate. The test data are then quantified using the Johnson-Cook (J-C) fracture strain model incorporating combined effects of the stress triaxiality and strain rate. The determined J-C model can predict true fracture strain overall conservatively with the difference less than 20%. The conservatism in the strain-based acceptance criteria in ASME B&PV Code, Section III, Appendix FF is also discussed. (c) 2022 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).-
dc.languageEnglish-
dc.language.isoen-
dc.publisherKOREAN NUCLEAR SOC-
dc.subjectMETALS-
dc.titleEffect of strain rate and stress triaxiality on fracture strain of 304 stainless steels for canister impact simulation-
dc.typeArticle-
dc.contributor.affiliatedAuthorKim, Yun-Jae-
dc.identifier.doi10.1016/j.net.2022.02.002-
dc.identifier.scopusid2-s2.0-85124713609-
dc.identifier.wosid000826778300005-
dc.identifier.bibliographicCitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.54, no.7, pp.2386 - 2394-
dc.relation.isPartOfNUCLEAR ENGINEERING AND TECHNOLOGY-
dc.citation.titleNUCLEAR ENGINEERING AND TECHNOLOGY-
dc.citation.volume54-
dc.citation.number7-
dc.citation.startPage2386-
dc.citation.endPage2394-
dc.type.rimsART-
dc.type.docTypeArticle-
dc.identifier.kciidART002858392-
dc.description.journalClass1-
dc.description.isOpenAccessY-
dc.description.journalRegisteredClassscie-
dc.description.journalRegisteredClassscopus-
dc.relation.journalResearchAreaNuclear Science & Technology-
dc.relation.journalWebOfScienceCategoryNuclear Science & Technology-
dc.subject.keywordPlusMETALS-
dc.subject.keywordAuthorAustenitic stainless steel-
dc.subject.keywordAuthorStrain rate-
dc.subject.keywordAuthorStress triaxiality-
dc.subject.keywordAuthorFracture strain-
dc.subject.keywordAuthorStrain -based acceptance criteria-
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