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Toward the multiscale nature of stress corrosion cracking

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dc.contributor.authorLiu, Xiaolong-
dc.contributor.authorHwang, Woonggi-
dc.contributor.authorPark, Jaewoong-
dc.contributor.authorVan, Donghyun-
dc.contributor.authorChang, Yunlong-
dc.contributor.authorLee, Seung Hwan-
dc.contributor.authorKim, Sung-Yup-
dc.contributor.authorHan, Sangsoo-
dc.contributor.authorLee, Boyoung-
dc.date.accessioned2021-07-30T05:01:12Z-
dc.date.available2021-07-30T05:01:12Z-
dc.date.created2021-05-14-
dc.date.issued2018-02-
dc.identifier.issn1738-5733-
dc.identifier.urihttps://scholarworks.bwise.kr/hanyang/handle/2021.sw.hanyang/2725-
dc.description.abstractThis article reviews the multiscale nature of stress corrosion cracking (SCC) observed by high-resolution characterizations in austenite stainless steels and Ni-base superalloys in light water reactors (including boiling water reactors, pressurized water reactors, and supercritical water reactors) with related opinions. A new statistical summary and comparison of observed degradation phenomena at different length scales is included. The intrinsic causes of this multiscale nature of SCC are discussed based on existing evidence and related opinions, ranging from materials theory to practical processing technologies. Questions of interest are then discussed to improve bottom-up understanding of the intrinsic causes. Last, a multiscale modeling and simulation methodology is proposed as a promising interdisciplinary solution to understand the intrinsic causes of the multiscale nature of SCC in light water reactors, based on a review of related supporting application evidence.-
dc.language영어-
dc.language.isoen-
dc.publisherKOREAN NUCLEAR SOC-
dc.titleToward the multiscale nature of stress corrosion cracking-
dc.typeArticle-
dc.contributor.affiliatedAuthorLee, Seung Hwan-
dc.identifier.doi10.1016/j.net.2017.10.014-
dc.identifier.scopusid2-s2.0-85040115287-
dc.identifier.wosid000425255700001-
dc.identifier.bibliographicCitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.50, no.1, pp.1 - 17-
dc.relation.isPartOfNUCLEAR ENGINEERING AND TECHNOLOGY-
dc.citation.titleNUCLEAR ENGINEERING AND TECHNOLOGY-
dc.citation.volume50-
dc.citation.number1-
dc.citation.startPage1-
dc.citation.endPage17-
dc.type.rimsART-
dc.type.docType정기학술지(Article(Perspective Article포함))-
dc.description.journalClass1-
dc.description.isOpenAccessY-
dc.description.journalRegisteredClassscie-
dc.description.journalRegisteredClassscopus-
dc.description.journalRegisteredClasskci-
dc.relation.journalResearchAreaNuclear Science & Technology-
dc.relation.journalWebOfScienceCategoryNuclear Science & Technology-
dc.subject.keywordPlusPWR PRIMARY WATER-
dc.subject.keywordPlusAUSTENITIC STAINLESS-STEEL-
dc.subject.keywordPlusGRAIN-BOUNDARY MIGRATION-
dc.subject.keywordPlusREACTIVE FORCE-FIELD-
dc.subject.keywordPlusOXIDE-FILM FORMATION-
dc.subject.keywordPlusNICKEL-BASE ALLOYS-
dc.subject.keywordPlusHIGH-TEMPERATURE-
dc.subject.keywordPlusMOLECULAR-DYNAMICS-
dc.subject.keywordPlusINTERGRANULAR OXIDATION-
dc.subject.keywordPlusSELF-DIFFUSION-
dc.subject.keywordAuthorCharacterization-
dc.subject.keywordAuthorIntergranular Corrosion-
dc.subject.keywordAuthorLight Water Reactors-
dc.subject.keywordAuthorMultiscale Simulation-
dc.subject.keywordAuthorStress Corrosion Cracking-
dc.identifier.urlhttps://www.sciencedirect.com/science/article/pii/S1738573317304552?via%3Dihub-
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