Full metadata record

DC Field Value Language
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.accessioned2024-01-19T23:32:31Z-
dc.date.available2024-01-19T23:32:31Z-
dc.date.created2021-09-03-
dc.date.issued2018-02-
dc.identifier.issn1738-5733-
dc.identifier.urihttps://pubs.kist.re.kr/handle/201004/121777-
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. (c) 2018 Korean Nuclear Society, Published by Elsevier Korea LLC.-
dc.languageEnglish-
dc.publisherKOREAN NUCLEAR SOC-
dc.subjectPWR PRIMARY WATER-
dc.subjectAUSTENITIC STAINLESS-STEEL-
dc.subjectGRAIN-BOUNDARY MIGRATION-
dc.subjectREACTIVE FORCE-FIELD-
dc.subjectOXIDE-FILM FORMATION-
dc.subjectNICKEL-BASE ALLOYS-
dc.subjectHIGH-TEMPERATURE-
dc.subjectMOLECULAR-DYNAMICS-
dc.subjectINTERGRANULAR OXIDATION-
dc.subjectSELF-DIFFUSION-
dc.titleToward the multiscale nature of stress corrosion cracking-
dc.typeArticle-
dc.identifier.doi10.1016/j.net.2017.10.014-
dc.description.journalClass1-
dc.identifier.bibliographicCitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.50, no.1, pp.1 - 17-
dc.citation.titleNUCLEAR ENGINEERING AND TECHNOLOGY-
dc.citation.volume50-
dc.citation.number1-
dc.citation.startPage1-
dc.citation.endPage17-
dc.description.journalRegisteredClassscie-
dc.description.journalRegisteredClassscopus-
dc.description.journalRegisteredClasskci-
dc.identifier.kciidART002315415-
dc.identifier.wosid000425255700001-
dc.identifier.scopusid2-s2.0-85040115287-
dc.relation.journalWebOfScienceCategoryNuclear Science & Technology-
dc.relation.journalResearchAreaNuclear Science & Technology-
dc.type.docTypeReview-
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-
Appears in Collections:
KIST Article > 2018
Files in This Item:
There are no files associated with this item.
Export
RIS (EndNote)
XLS (Excel)
XML

qrcode

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

BROWSE