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ROAAM应用于ACP1000严重事故下实施IVR策略的有效性概率分析

发布时间:2018-06-13 13:22

  本文选题:堆芯熔融物 + 压力容器内滞留 ; 参考:《核动力工程》2015年06期


【摘要】: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。
[Abstract]:Based on the mechanism analysis model of heat transfer between core melt and pressure vessel, Risk-oriented accident analysis (ROAAM) is used to analyze the effectiveness of the IVR strategy of pressurized water reactor (PWR) by cooling the outside of the pressure vessel to implement the retention of core melt in the pressure vessel. Based on the PSA-analysis results of first-order probabilistic safety assessment of nuclear power plants, the typical serious accident sequence of ACP1000 is calculated, and the uncertainty of important parameters affecting the heat transfer of molten matter is analyzed. The results of probabilistic analysis show that the probability of effectiveness of IVR strategy is greater than 99 in the case of serious false accident, and the main position of heat transfer hazard in the lower head occurs in the metal layer due to the heat collecting effect at the top of the melting pool.
【作者单位】: 中国核动力研究设计院核反应堆系统设计技术重点实验室;
【分类号】:TL364.4

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