167 196

Full metadata record

DC FieldValueLanguage
dc.contributor.author장재일-
dc.date.accessioned2022-04-26T05:13:38Z-
dc.date.available2022-04-26T05:13:38Z-
dc.date.issued2020-08-
dc.identifier.citationKOREAN JOURNAL OF METALS AND MATERIALS, v. 58, no. 8, page. 522-532en_US
dc.identifier.issn1738-8228-
dc.identifier.issn2288-8241-
dc.identifier.urihttp://kjmm.org/journal/view.php?doi=10.3365/KJMM.2020.58.8.522-
dc.identifier.urihttps://repository.hanyang.ac.kr/handle/20.500.11754/170289-
dc.description.abstractThe small punch (SP) test is one of the small specimen test techniques, and standardization of the SP test method for evaluating the mechanical properties of metallic materials is in progress. In this study, the impact transition temperature of reactor pressure vessel steels (RPV) in nuclear power plants was estimated using the draft standard SP test method. The SP fracture energy (E-SP) and normalized SP fracture energy (E-NSP) of the RPV steels were evaluated at various temperatures, and their transition curves were derived and compared to the transition curve in the Charpy V notch (CVN) test. The SP transition region appeared at a much lower temperature range than that of the CVN owing to the size and notch effect. Ductile brittle transition temperature (DBTT) in the SP transition curve showed a linear relationship with DBTT and T-41J in the CVN transition curve. The ductile to brittle transition behaviors of SP specimens were analyzed using fractographs and compared with the transition curves in E-SP and E-NSP. E-NSP started to decrease at the temperature at which the SP ductile to brittle transition behavior occurred, and this means that the E-NSP transition curves were in good agreement with transition behavior in the SP test. However, the E-SP transition curves did not match transition behavior Using DBTT in the E-NSP transition curve is appropriate to estimate the CVNDBTT and T-41J.en_US
dc.description.sponsorship이 성과는 정부(과학기술정보통신부)의 재원으로 한국연 구재단의 지원을 받아 수행된 연구임(2017M2A8A4015156).en_US
dc.language.isoko_KRen_US
dc.publisherKOREAN INST METALS MATERIALSen_US
dc.subjectreactor pressure vesselen_US
dc.subjectsmall punch testen_US
dc.subjectASTM WK61832en_US
dc.subjectcharpy impact testen_US
dc.subjecttransition temperatureen_US
dc.title소형펀치 파단에너지 천이곡선을 활용한 원자로용기강의 천이온도 평가en_US
dc.title.alternativeEvaluation of Transition Temperature in Reactor Pressure Vessel Steels using the Fracture Energy Transition Curve from a Small Punch Testen_US
dc.typeArticleen_US
dc.relation.no8-
dc.relation.volume58-
dc.identifier.doi10.3365/KJMM.2020.58.8.522-
dc.relation.page522-532-
dc.relation.journalKOREAN JOURNAL OF METALS AND MATERIALS-
dc.contributor.googleauthor이태경-
dc.contributor.googleauthor홍석민-
dc.contributor.googleauthor김종민-
dc.contributor.googleauthor김민철-
dc.contributor.googleauthor장재일-
dc.contributor.googleauthorLee, Tae-kyung-
dc.contributor.googleauthorHong, Seokmin-
dc.contributor.googleauthorKim, Jongmin-
dc.contributor.googleauthorKim, Min-Chul-
dc.contributor.googleauthorJang, Jae-il-
dc.relation.code2020047427-
dc.sector.campusS-
dc.sector.daehakCOLLEGE OF ENGINEERING[S]-
dc.sector.departmentSCHOOL OF MATERIALS SCIENCE AND ENGINEERING-
dc.identifier.pidjijang-
dc.identifier.researcherIDA-3486-2011-
dc.identifier.orcidhttps://orcid.org/0000-0003-4526-5355-


qrcode

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

BROWSE