压力容器水位参数在堆芯损伤评价方法中的应用

Application of Reactor Pressure Vessel Water Lever During Core Damage Assessment

  • 摘要: 事故工况下,堆芯会随着冷却能力的下降而逐步升温,长时间的裸露会导致堆芯损伤,而堆芯出口温度和压力容器水位可直观反映堆芯的冷却能力。以西屋公司堆芯损伤评价导则为基础的堆芯损伤评价方法将堆芯出口温度和安全壳剂量率作为主要参数评价堆芯损伤状态,压力容器水位作为辅助参数之一来验证评价结果的合理性,但一些核电厂堆芯出口热电偶量程并不能满足严重事故条件下的要求,需要其他替代参数。本工作以压水堆核电厂严重事故分析数据为基础,探讨将压力容器水位作为主要参数应用于堆芯损伤评价方法的可行性。

     

    Abstract: The core continued to heat up due to the loss of cooling under accident conditions. The core would damage as it is uncovered for a long time. The reactor core exit temperature (CET) and the reactor vessel level (RVL) can provide an indirect indication of inadequate core cooling. CET and the containment dose rate are the master criteria in the method of core damage assessment, which is based on Westinghouse Owners Group Core Damage Assessment Guidance (CDAG). RVL, as one of the assistant parameters, can be used to validate the assessment result. In some nuclear power plant, CET, which is unused under sever accident condition, must be replaced by some other parameters. Based on the analysis of sever accident sequence, RVL would be discussed to be used in the current method of core damage assessment as a master criterion.

     

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