Fracture simulation of SFR metallic fuel pin using finite element damage analysis method
DC Field | Value | Language |
---|---|---|
dc.contributor.author | Jung, Hyun-Woo | - |
dc.contributor.author | Song, Hyun-Kyu | - |
dc.contributor.author | Kim, Yun-Jae | - |
dc.contributor.author | Jerng, Dong-Wook | - |
dc.date.accessioned | 2021-08-30T02:52:44Z | - |
dc.date.available | 2021-08-30T02:52:44Z | - |
dc.date.created | 2021-06-19 | - |
dc.date.issued | 2021-03 | - |
dc.identifier.issn | 1738-5733 | - |
dc.identifier.uri | https://scholar.korea.ac.kr/handle/2021.sw.korea/49505 | - |
dc.description.abstract | This 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.language | English | - |
dc.language.iso | en | - |
dc.publisher | KOREAN NUCLEAR SOC | - |
dc.subject | BEHAVIOR | - |
dc.subject | IRRADIATION | - |
dc.subject | FAILURE | - |
dc.subject | D9 | - |
dc.title | Fracture simulation of SFR metallic fuel pin using finite element damage analysis method | - |
dc.type | Article | - |
dc.contributor.affiliatedAuthor | Kim, Yun-Jae | - |
dc.identifier.doi | 10.1016/j.net.2020.08.009 | - |
dc.identifier.scopusid | 2-s2.0-85089967579 | - |
dc.identifier.wosid | 000625557100003 | - |
dc.identifier.bibliographicCitation | NUCLEAR ENGINEERING AND TECHNOLOGY, v.53, no.3, pp.932 - 941 | - |
dc.relation.isPartOf | NUCLEAR ENGINEERING AND TECHNOLOGY | - |
dc.citation.title | NUCLEAR ENGINEERING AND TECHNOLOGY | - |
dc.citation.volume | 53 | - |
dc.citation.number | 3 | - |
dc.citation.startPage | 932 | - |
dc.citation.endPage | 941 | - |
dc.type.rims | ART | - |
dc.type.docType | Article | - |
dc.identifier.kciid | ART002690804 | - |
dc.description.journalClass | 1 | - |
dc.description.journalRegisteredClass | scie | - |
dc.description.journalRegisteredClass | scopus | - |
dc.description.journalRegisteredClass | kci | - |
dc.relation.journalResearchArea | Nuclear Science & Technology | - |
dc.relation.journalWebOfScienceCategory | Nuclear Science & Technology | - |
dc.subject.keywordPlus | BEHAVIOR | - |
dc.subject.keywordPlus | IRRADIATION | - |
dc.subject.keywordPlus | FAILURE | - |
dc.subject.keywordPlus | D9 | - |
dc.subject.keywordAuthor | Sodium-cooled fast reactor | - |
dc.subject.keywordAuthor | Metallic fuel | - |
dc.subject.keywordAuthor | Fracture simulation | - |
dc.subject.keywordAuthor | Failure prediction | - |
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