Fracture simulation of SFR metallic fuel pin using finite element damage analysis method
DC Field | Value | Language |
---|---|---|
dc.contributor.author | Jung, H.-W. | - |
dc.contributor.author | Song, H.-K. | - |
dc.contributor.author | Kim, Y.-J. | - |
dc.contributor.author | Jerng, D.-W. | - |
dc.date.accessioned | 2022-01-17T02:40:56Z | - |
dc.date.available | 2022-01-17T02:40:56Z | - |
dc.date.issued | 2021-03 | - |
dc.identifier.issn | 1738-5733 | - |
dc.identifier.uri | https://scholarworks.bwise.kr/cau/handle/2019.sw.cau/53605 | - |
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. © 2020 | - |
dc.format.extent | 10 | - |
dc.language | 영어 | - |
dc.language.iso | ENG | - |
dc.publisher | Korean Nuclear Society | - |
dc.title | Fracture simulation of SFR metallic fuel pin using finite element damage analysis method | - |
dc.title.alternative | Fracture simulation of SFR metallic fuel pin using fi nite element damage analysis method | - |
dc.type | Article | - |
dc.identifier.doi | 10.1016/j.net.2020.08.009 | - |
dc.identifier.bibliographicCitation | Nuclear Engineering and Technology, v.53, no.3, pp 932 - 941 | - |
dc.identifier.kciid | ART002690804 | - |
dc.description.isOpenAccess | Y | - |
dc.identifier.wosid | 000625557100003 | - |
dc.identifier.scopusid | 2-s2.0-85089967579 | - |
dc.citation.endPage | 941 | - |
dc.citation.number | 3 | - |
dc.citation.startPage | 932 | - |
dc.citation.title | Nuclear Engineering and Technology | - |
dc.citation.volume | 53 | - |
dc.type.docType | Article | - |
dc.publisher.location | 대한민국 | - |
dc.subject.keywordAuthor | Failure prediction | - |
dc.subject.keywordAuthor | Fracture simulation | - |
dc.subject.keywordAuthor | Metallic fuel | - |
dc.subject.keywordAuthor | Sodium-cooled fast reactor | - |
dc.subject.keywordPlus | BEHAVIOR | - |
dc.subject.keywordPlus | IRRADIATION | - |
dc.subject.keywordPlus | FAILURE | - |
dc.subject.keywordPlus | D9 | - |
dc.relation.journalResearchArea | Nuclear Science & Technology | - |
dc.relation.journalWebOfScienceCategory | Nuclear Science & Technology | - |
dc.description.journalRegisteredClass | scie | - |
dc.description.journalRegisteredClass | scopus | - |
dc.description.journalRegisteredClass | kci | - |
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