AP1000 containment accident transient analysis using MELCOR
XIAO Hong1, CAO Zhiwei2, FENG Yingjie2, YANG Zhiyi1, ZHU Jianmin2
1. Nuclear and Radiation Safety Center, Ministry of Environmental protection, Beijing 100082, China; 2. China Nuclear Power Institute Co., Ltd., Shenzhen 518026, China
Abstract：The AP1000 containment and passive containment cooling system (PCS) were modeled using MELCOR 2.1 and SNAP with detailed 3D modeling to analyze the convective heat transfer, condensation and film evaporation for containment cooling. The film tracking model was used to simulate the PCS characteristics. The containment thermal hydraulic transients during a LOCA were analyzed to predict the main parameters at each stage after the accident. The effects of the film coverage fraction and the film coverage time were also studied. The results show that the MELCOR program can accurately simulate the thermal hydraulics of the AP1000 passive containment cooling system. The results provide a reference for analyzing the characteristics of the nuclear power plant containment system. This study also independently verifies the safety of this reactor design by using an analysis code that is totally different from the design codes.
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2018, Vol. 58 
