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

Authors
Song, Chang HyunSong, JinhoKim, Sung Joong
Issue Date
Aug-2025
Publisher
한국원자력학회
Keywords
i-SMR; Passive safety system; Coolant recirculation; Design basis accident; MELCOR analysis
Citation
Nuclear Engineering and Technology, v.57, no.8, pp 1 - 19
Pages
19
Indexed
SCIE
SCOPUS
KCI
Journal Title
Nuclear Engineering and Technology
Volume
57
Number
8
Start Page
1
End Page
19
URI
https://scholarworks.bwise.kr/hanyang/handle/2021.sw.hanyang/210105
DOI
10.1016/j.net.2025.103556
ISSN
1738-5733
2234-358X
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.
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COLLEGE OF ENGINEERING (DEPARTMENT OF NUCLEAR ENGINEERING)
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