Detailed Information

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

Evaluation of accident mitigation capability of passive core and containment cooling systems of i-SMR under representative LOCA and non-LOCA conditions

Full metadata record
DC Field Value Language
dc.contributor.authorSong, Chang Hyun-
dc.contributor.authorSong, Jinho-
dc.contributor.authorKim, Sung Joong-
dc.date.accessioned2025-12-26T05:30:17Z-
dc.date.available2025-12-26T05:30:17Z-
dc.date.issued2025-08-
dc.identifier.issn1738-5733-
dc.identifier.issn2234-358X-
dc.identifier.urihttps://scholarworks.bwise.kr/hanyang/handle/2021.sw.hanyang/210105-
dc.description.abstractThe global climate crisis has accelerated efforts to cut greenhouse gas emissions in the energy sector. While renewable energy faces limits in capacity and high costs, nuclear power offers a low-carbon, reliable baseload alternative and has been included in the EU Green Taxonomy since 2023 as a top option for achieving net-zero targets. Meeting heightened safety standards in nuclear power plants (NPPs) and rising electricity demand driven by AI has spurred strong interest in small modular reactors (SMRs) equipped with advanced passive safety systems. A standout example is Korea's innovative SMR (i-SMR), which delivers 170 MWe and is engineered to enhance safety by over 1000 times compared to traditional NPPs, with core damage frequency and early release frequency below 1.0E-09 and 1.0E-10 per module-year, respectively. Using the MELCOR code, this study evaluates the i-SMR's passive cooling systems under LOCA and non-LOCA conditions. The results confirm these systems can maintain reactor core and fuel integrity for 72 h post-accident without operator intervention, showcasing the high efficacy of the i-SMR's passive safety systems.-
dc.format.extent19-
dc.language영어-
dc.language.isoENG-
dc.publisher한국원자력학회-
dc.titleEvaluation of accident mitigation capability of passive core and containment cooling systems of i-SMR under representative LOCA and non-LOCA conditions-
dc.typeArticle-
dc.publisher.location대한민국-
dc.identifier.doi10.1016/j.net.2025.103556-
dc.identifier.scopusid2-s2.0-85219663652-
dc.identifier.wosid001453993700001-
dc.identifier.bibliographicCitationNuclear Engineering and Technology, v.57, no.8, pp 1 - 19-
dc.citation.titleNuclear Engineering and Technology-
dc.citation.volume57-
dc.citation.number8-
dc.citation.startPage1-
dc.citation.endPage19-
dc.type.docTypeArticle in press-
dc.identifier.kciidART003210287-
dc.description.isOpenAccessY-
dc.description.journalRegisteredClassscie-
dc.description.journalRegisteredClassscopus-
dc.description.journalRegisteredClasskci-
dc.relation.journalResearchAreaNuclear Science & Technology-
dc.relation.journalWebOfScienceCategoryNuclear Science & Technology-
dc.subject.keywordPlusMALL MODULAR REACTOR-
dc.subject.keywordPlusELECTRICITY-
dc.subject.keywordAuthori-SMR-
dc.subject.keywordAuthorPassive safety system-
dc.subject.keywordAuthorCoolant recirculation-
dc.subject.keywordAuthorDesign basis accident-
dc.subject.keywordAuthorMELCOR analysis-
dc.identifier.urlhttps://www.sciencedirect.com/science/article/pii/S173857332500124X?via%3Dihub-
Files in This Item
Go to Link
Appears in
Collections
서울 공과대학 > 서울 원자력공학과 > 1. Journal Articles

qrcode

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

Related Researcher

Researcher Kim, Sung Joong photo

Kim, Sung Joong
COLLEGE OF ENGINEERING (DEPARTMENT OF NUCLEAR ENGINEERING)
Read more

Altmetrics

Total Views & Downloads

BROWSE