Detailed Information

Cited 0 time in webofscience Cited 0 time in scopus
Metadata Downloads

Fracture simulation of SFR metallic fuel pin using finite element damage analysis method

Full metadata record
DC Field Value Language
dc.contributor.authorJung, Hyun-Woo-
dc.contributor.authorSong, Hyun-Kyu-
dc.contributor.authorKim, Yun-Jae-
dc.contributor.authorJerng, Dong-Wook-
dc.date.accessioned2021-08-30T02:52:44Z-
dc.date.available2021-08-30T02:52:44Z-
dc.date.created2021-06-19-
dc.date.issued2021-03-
dc.identifier.issn1738-5733-
dc.identifier.urihttps://scholar.korea.ac.kr/handle/2021.sw.korea/49505-
dc.description.abstractThis paper suggests a fracture simulation method for SFR metallic fuel pin under accident condition. Two major failure mechanisms - creep damage and eutectic penetration - are implemented in the suggested method. To simulate damaged element, stress-reduction concept to reduce stiffness of the damaged element is applied. Using the proposed method, the failure size of cladding can be predicted in addition to the failure time and failure site. To verify the suggested method, Whole-pin furnace (WPF) test and TREAT-M test conducted at Argonne National Laboratory (ANL) are simulated. In all cases, predicted results and experimental results are overall in good agreement. Based on the simulation result, the effect of eutectic-penetration depth representing failure behavior on failure size is studied. (C) 2020 Korean Nuclear Society, Published by Elsevier Korea LLC.-
dc.languageEnglish-
dc.language.isoen-
dc.publisherKOREAN NUCLEAR SOC-
dc.subjectBEHAVIOR-
dc.subjectIRRADIATION-
dc.subjectFAILURE-
dc.subjectD9-
dc.titleFracture simulation of SFR metallic fuel pin using finite element damage analysis method-
dc.typeArticle-
dc.contributor.affiliatedAuthorKim, Yun-Jae-
dc.identifier.doi10.1016/j.net.2020.08.009-
dc.identifier.scopusid2-s2.0-85089967579-
dc.identifier.wosid000625557100003-
dc.identifier.bibliographicCitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.53, no.3, pp.932 - 941-
dc.relation.isPartOfNUCLEAR ENGINEERING AND TECHNOLOGY-
dc.citation.titleNUCLEAR ENGINEERING AND TECHNOLOGY-
dc.citation.volume53-
dc.citation.number3-
dc.citation.startPage932-
dc.citation.endPage941-
dc.type.rimsART-
dc.type.docTypeArticle-
dc.identifier.kciidART002690804-
dc.description.journalClass1-
dc.description.journalRegisteredClassscie-
dc.description.journalRegisteredClassscopus-
dc.description.journalRegisteredClasskci-
dc.relation.journalResearchAreaNuclear Science & Technology-
dc.relation.journalWebOfScienceCategoryNuclear Science & Technology-
dc.subject.keywordPlusBEHAVIOR-
dc.subject.keywordPlusIRRADIATION-
dc.subject.keywordPlusFAILURE-
dc.subject.keywordPlusD9-
dc.subject.keywordAuthorSodium-cooled fast reactor-
dc.subject.keywordAuthorMetallic fuel-
dc.subject.keywordAuthorFracture simulation-
dc.subject.keywordAuthorFailure prediction-
Files in This Item
There are no files associated with this item.
Appears in
Collections
College of Engineering > Department of Mechanical Engineering > 1. Journal Articles

qrcode

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

Related Researcher

Researcher Kim, Yun Jae photo

Kim, Yun Jae
공과대학 (기계공학부)
Read more

Altmetrics

Total Views & Downloads

BROWSE