Abstract
A new system, which is named advanced secondary passive residual heat removal system (ASP), is designed to remove decay heat passively through the steam generator (SG). It is done by condensing steam from steam generator inside a heat exchanger submerged in a water tank. Current investigations and code adaptations have demonstrated that the RELAP5 code can be applied for thermal hydraulic analysis of test facility with good prediction. In this paper, numerical investigation of the secondary-side passive residual heat removal system is performed using RELAP5 code. Steady and transient conditions under postulated Station Black-Out (SBO) accident are analyzed. Results show that 0.41 % of decay heat can be totally removed by natural circulation. Transient test results show that, in the event of station black-out accident, decay heat of reactor core can be sufficiently removed during 18000 s after shutdown.
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Li, L., Wen, Q., Wu, X., Lu, D. (2017). Numerical Investigation of Passively Cooled Steam Generator Natural Circulation Using RELAP5 Code. In: Jiang, H. (eds) Proceedings of The 20th Pacific Basin Nuclear Conference. PBNC 2016. Springer, Singapore. https://doi.org/10.1007/978-981-10-2311-8_41
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DOI: https://doi.org/10.1007/978-981-10-2311-8_41
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