Development of an on-demand flooding safety system achieving long-term inexhaustible cooling of small modular reactors employing metal containment vessel

  • Park, Jae Hyung
  • Im, Jihun
  • An, Hyo Jun
  • Kim, Yonghee
  • Lee, Jeong Ik
  • ... Kim, Sung Joong
Citations

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6
Citations

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6

초록

This paper proposes a flooding safety system (FSS) and its operation strategy that can provide long-term safety and effective maintenance for modules of small modular reactor (SMR) and metal containment maintained at dried environment during normal operation. During hypothesized accidents, the FSS re-collects the evaporated steam into the common pool by the condenser installed above the common water pool and provides an emergency coolant for the cavities and auxiliary pools. This study suggested that the condensate re-collection strategy using the FSS can effectively delay the depletion of available water in response to the accidents. Without re-collection, the achievable grace periods ranged from 44 to 1507 days for six-module and one-module accidents, respectively. However, with a full re-collection (ratio = 1.0), the time to total depletion of emergency coolant was estimated indefinite. Even with a partial re-collection ratio of 0.3, a grace period of 83.5 days could be ensured for a six-module transient. This study reported the effectiveness of condensate re-collection and the FSS as an innovative safety management strategy and system. Employing a condensate re-collection strategy with a high re-collection ratio can enhance the long-term safety and effective convenience of SMR operations and maintenance.

키워드

Small modular reactorPassive safety systemDry separate cavityEmergency coolant supply in an accidentCondensate re-collectionFlooding safety systemNATURAL CIRCULATIONDESIGNPLANTCOGENERATIONFEATURESSMR
제목
Development of an on-demand flooding safety system achieving long-term inexhaustible cooling of small modular reactors employing metal containment vessel
저자
Park, Jae HyungIm, JihunAn, Hyo JunKim, YongheeLee, Jeong IkKim, Sung Joong
DOI
10.1016/j.net.2024.02.012
발행일
2024-07
유형
Article
저널명
Nuclear Engineering and Technology
56
7
페이지
2534 ~ 2544