压水堆严重事故管理入口标准研究

Study on Entry Criteria for Severe Accident Management of Pressure Water Reactor

  • 摘要: 使用严重事故分析程序RELAP/SCDAPSIM,对3种不同尺寸的压水堆热段大破口事故进行了分析。主要研究了15、20、25 cm大破口事故分别在无事故管理和有高压安全注射条件下事故进程。计算结果表明,当堆芯表面峰值温度达1 500 K时,堆芯出口温度不能反映堆芯的损伤状态;当堆芯出口温度达900 K时,进行严重事故管理不能有效阻止堆芯熔化。将堆芯热通道出口温度作为严重事故管理入口标准的计算分析结果表明,在堆芯热通道出口温度达900 K时实施严重事故管理可有效阻止堆芯熔化,此信息可作为进入严重事故管理的入口标准。

     

    Abstract: A systematic study on entry criterion of severe accident management (SAM) for different hot leg break sizes in a 3-loop PWR was carried out using the detailed system thermal-hydraulic and severe accident analysis code package, RELAP/SCDAPSIM. Best estimate calculations of the large break loss of coolant accident (LBLOCA) of 15, 20 and 25 cm without accident management and in the case of high-pressure safety injection as the accident management were performed in this paper. The analysis results show that the core exit temperatures are not reliable indicators of the peak core temperatures and core damage states when peak core temperature reaches 1 500 K, and the proposed entry criteria for SAM is not effective to prevent core melt when the core outlet temperature reaches 900 K. Then other analyses were performed with a parameter of fluid temperature just above the hot channel. The latter analysis results show that earlier water injection is effective to prevent further core melt when the fluid temperature just above the hot channel reaches 900 K. The maximum exit temperature of 900 K above the hot channel can be used as entry criteria to enter into the SAM.

     

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