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Safety implications of multiple passive safety valve failures in an i-SMR design

Authors
Song, Chang HyunKim, Sung Joong
Issue Date
Jan-2026
Publisher
Elsevier BV
Keywords
i-SMR; Passive safety system; Multiple failure; Severe accident; MELCOR
Citation
Progress in Nuclear Energy, v.191, pp 1 - 12
Pages
12
Indexed
SCIE
SCOPUS
Journal Title
Progress in Nuclear Energy
Volume
191
Start Page
1
End Page
12
URI
https://scholarworks.bwise.kr/hanyang/handle/2021.sw.hanyang/209158
DOI
10.1016/j.pnucene.2025.106065
ISSN
0149-1970
1878-4224
Abstract
Small Modular Reactors (SMRs) are being developed as next-generation nuclear options in response to increasing global power demand driven by data centers, artificial intelligence, and industrial electrification. Korea's innovative SMR (i-SMR) is designed as an integral pressurized water reactor with a thermal output of 520 MWth, aiming to achieve a core damage frequency below 1.0E-09 per year. To meet these goals, the i-SMR adopts multiple Passive Safety Systems (PSSs), including the Passive Emergency Core Cooling System (PECCS), which ensures core cooling through depressurization and natural recirculation. While previous studies have validated the effectiveness of PSSs under nominal conditions, their performance under multiple passive valve failures remains underexplored. In particular, the emergency depressurization valves, and emergency recirculation valves are critical components that enable passive cooling. If one or more of these valves fail to function as designed, coolant may be lost rapidly or recirculation hindered, accelerating fuel exposure. In this study, a detailed MELCOR input model of the i-SMR was developed to analyze accident progression behavior under multiple passive valve failures, particularly focusing on PECCS-related valves. MELCOR simulation results revealed that partial valve failures can lead to faster core degradation than complete system failure scenarios. These findings highlight the critical need to incorporate design redundancy and diversity in passive valve components to ensure reliable accident mitigation capabilities in the i-SMR.
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COLLEGE OF ENGINEERING (DEPARTMENT OF NUCLEAR ENGINEERING)
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