Cited 0 time in
Evaluation of accident mitigation capability of passive core and containment cooling systems of i-SMR under representative LOCA and non-LOCA conditions
| DC Field | Value | Language |
|---|---|---|
| dc.contributor.author | Song, Chang Hyun | - |
| dc.contributor.author | Song, Jinho | - |
| dc.contributor.author | Kim, Sung Joong | - |
| dc.date.accessioned | 2025-12-26T05:30:17Z | - |
| dc.date.available | 2025-12-26T05:30:17Z | - |
| dc.date.issued | 2025-08 | - |
| dc.identifier.issn | 1738-5733 | - |
| dc.identifier.issn | 2234-358X | - |
| dc.identifier.uri | https://scholarworks.bwise.kr/hanyang/handle/2021.sw.hanyang/210105 | - |
| dc.description.abstract | The 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.extent | 19 | - |
| dc.language | 영어 | - |
| dc.language.iso | ENG | - |
| dc.publisher | 한국원자력학회 | - |
| dc.title | Evaluation of accident mitigation capability of passive core and containment cooling systems of i-SMR under representative LOCA and non-LOCA conditions | - |
| dc.type | Article | - |
| dc.publisher.location | 대한민국 | - |
| dc.identifier.doi | 10.1016/j.net.2025.103556 | - |
| dc.identifier.scopusid | 2-s2.0-85219663652 | - |
| dc.identifier.wosid | 001453993700001 | - |
| dc.identifier.bibliographicCitation | Nuclear Engineering and Technology, v.57, no.8, pp 1 - 19 | - |
| dc.citation.title | Nuclear Engineering and Technology | - |
| dc.citation.volume | 57 | - |
| dc.citation.number | 8 | - |
| dc.citation.startPage | 1 | - |
| dc.citation.endPage | 19 | - |
| dc.type.docType | Article in press | - |
| dc.identifier.kciid | ART003210287 | - |
| dc.description.isOpenAccess | Y | - |
| 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 | MALL MODULAR REACTOR | - |
| dc.subject.keywordPlus | ELECTRICITY | - |
| dc.subject.keywordAuthor | i-SMR | - |
| dc.subject.keywordAuthor | Passive safety system | - |
| dc.subject.keywordAuthor | Coolant recirculation | - |
| dc.subject.keywordAuthor | Design basis accident | - |
| dc.subject.keywordAuthor | MELCOR analysis | - |
| dc.identifier.url | https://www.sciencedirect.com/science/article/pii/S173857332500124X?via%3Dihub | - |
Items in ScholarWorks are protected by copyright, with all rights reserved, unless otherwise indicated.
222, Wangsimni-ro, Seongdong-gu, Seoul, 04763, Korea+82-2-2220-1366
COPYRIGHT © 2024 HANYANG UNIVERSITY.
Certain data included herein are derived from the © Web of Science of Clarivate Analytics. All rights reserved.
You may not copy or re-distribute this material in whole or in part without the prior written consent of Clarivate Analytics.
