[ICAPP 2023] strategic analysis on sizing of flooding valve for successful accident management of small modular reactor

Strategic analysis on sizing of flooding valve for successful accident management of small modular reactor
  • An, Hyo Jun
  • Park, Jae Hyung
  • Song, Chang Hyun
  • Lee, Jeong Ik
  • Kim, Yonghee
  • ... Kim, Sung Joong
Citations

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9
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초록

In contrast to all-time flooded small modular reactor (SMR) systems, an in-kind flooding safety system (FSS) has been proposed as a passive safety system applicable to small modular reactors (SMRs) that adopt a metal containment vessel (MCV). Under transient conditions, the FSS can provide emergency cooling to dry reactor cavities and sustain long-term coolability using re-acquired evaporated steam in the reactor building on demand. When designing an FSS, the effect of the flooding flow area is vital as it affects the overall accident sequence and safety. Therefore, in this study, a MELCOR model of a reference SMR is developed and numerical analysis is performed under postulated accident scenarios. Without flooding, the MCV pressure of the reactor module exceeds the design pressure before core damage. To prevent core damage, an emergency flooding strategy is devised using various flow path parameters and requirements to ensure an adequate emergency coolant supply before the core damage is investigated. The results indicate that a flow area exceeding 0.02 m2 is required in the FSS to prevent MCV overpressure and core damage. This study is the first to report a strategic analysis for appropriately sizing an FSS flooding valve applicable to innovative SMRs.

키워드

Accident managementFlooding safety systemMELCOR codePassive safety systemSmall modular reactorSAFETYMODELSMRHYDROGEN
제목
[ICAPP 2023] strategic analysis on sizing of flooding valve for successful accident management of small modular reactor
제목 (타언어)
Strategic analysis on sizing of flooding valve for successful accident management of small modular reactor
저자
An, Hyo JunPark, Jae HyungSong, Chang HyunLee, Jeong IkKim, YongheeKim, Sung Joong
DOI
10.1016/j.net.2023.11.025
발행일
2024-03
유형
Article
저널명
Nuclear Engineering and Technology
56
3
페이지
949 ~ 958