• Title/Summary/Keyword: Nuclear valve

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Study on the Real-Time Leak Monitoring Technique for Power Plant Valves (발전용 밸브누설 실시간 감시기술 연구)

  • Lee, S.G.
    • Journal of Power System Engineering
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    • v.11 no.1
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    • pp.39-44
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    • 2007

  • The purpose of this study is to verify availability of the acoustic emission in-situ monitoring method to the internal leak and operating conditions of the major valves at nuclear power plants. In this study, acoustic emission tests are performed when the pressurized temperature water and steam flowed through glove valve(main steam dump valve) and check valve(main steam outlet pump check valve) on the normal size of 12 and 18". The valve internal leak monitoring system for practical field was designed. The acoustic emission method was applied to the valves at the site, and the background noise was measured for the abnormal plant condition. To improve the reliability, a judgment of leak on the system was used various factors which are AE parameters, trend analysis, frequency analysis, voltage analysis and amplitude analysis of acoustic signal emitted from the valve operating condition internal leak.

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Strategic analysis on sizing of flooding valve for successful accident management of small modular reactor

  • Hyo Jun An;Jae Hyung Park;Chang Hyun Song;Jeong Ik Lee;Yonghee Kim;Sung Joong Kim
    • Nuclear Engineering and Technology
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    • v.56 no.3
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    • pp.949-958
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    • 2024

  • 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.

  • https://doi.org/10.1016/j.net.2023.11.025 인용 PDF