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基于堆芯熔融物与压力容器传热的机理分析模型,采用风险导向事故分析方法(ROAAM)分析压水堆在严重事故情况下通过冷却压力容器外部的手段来实施堆芯熔融物滞留在压力容器内(IVR)策略的有效性。以核电厂一级概率安全评价(PSA)分析结果为参考,计算ACP1000典型严重事故序列,分析影响熔融物传热的重要参数不确定性。概率分析结果表明:ACP1000发生假象的严重事故情况下,IVR策略有效性概率大于99%;由于熔融池顶部的金属层出现集热效应,下封头发生传热危险的主要位置出现在金属层。
Based on the mechanism analysis model of the heat transfer between the core melt and the pressure vessel, ROAAM is used to analyze the pressured water reactor in the case of a serious accident by cooling the outside of the pressure vessel to implement the core melt retained in the pressure vessel Validity of internal (IVR) strategies. Based on the results of first-level probability-based safety assessment (PSA) analysis of nuclear power plant, the ACP1000 typical serious accident sequence is calculated and the uncertainty of important parameters that affect the heat transfer of the melt is analyzed. The probability analysis shows that the probability of validity of IVR strategy is more than 99% in the case of severe accident with ACP1000. The main location of the heat risk of lower head occurs in the metal layer due to the heat collecting effect of the metal layer on the top of the molten pool.