先进压水堆主动式和被动式设备对重大事故中热工性能和源项性能的影响

Jishen Li , Bin Zhang
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引用次数: 0

摘要

对普通压水堆的堆芯退化和裂变产物的行为进行了广泛的研究。然而,他们中很少有人研究先进无源PWR中热工水力学和裂变产物行为之间的关系。由于不同事故序列中的热工水力学行为对裂变产物的释放和运输的影响,需要一个具有高度耦合的热工水力学和源项计算的集成严重事故分析(ISAA)代码来同时分析热工水力学和来源项行为。对于先进的无源PWR,应考虑可能影响堆芯和裂变产物行为的重要安全系统。因此,有必要模拟先进无源PWR的热工水力学和裂变产物行为。在本研究中,采用ISAA程序模拟了HPR1000在三种设备故障情况下发生的假想双端冷段LBLOCA。结果表明,高温燃料棒和包壳材料在堆芯较低位置表现出延迟失效,而在再燃过程中,在较高位置表现出早期失效。主动和被动设备影响燃料温度、燃料的氧化条件、裂变产物与结构材料的相互作用以及燃料的状态,从而影响燃料中裂变产物的释放。华龙一号仅依靠无源设备来缓解严重事故中堆芯退化,实现熔体在容器内的滞留,消除裂变产物在容器外释放的可能性。希望研究结果能为华龙一号制定重大事故管理导则(SAMG)提供参考。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Influence of active and passive equipment for advanced pressurized water reactor on thermal hydraulic and source term behavior in severe accidents

Extensive studies have been carried out on the behavior of core degradation and fission products of common pressurized water reactors (PWRs). However, few of them have investigated the relationship between thermal hydraulic and fission product behavior in advanced passive PWRs. Due to the impact of thermal hydraulic behaviors in different accident sequences on the release and transportation of fission products, an integrated severe accident analysis (ISAA) code with highly coupled thermal hydraulic and source term calculations is required to simultaneously analyze thermal hydraulic and source term behavior. For advanced passive PWRs, important safety systems that may affect the behavior of the core and fission products should be considered. It is therefore necessary to simulate the thermal hydraulic and fission product behavior of advanced passive PWRs. In this study, the ISAA code is adopted to simulate the occurrence of a hypothetical double ended cold leg LBLOCA of HPR1000 in three scenarios of equipment failure. The results show that the high-temperature fuel rods and cladding materials exhibit delayed failure at the lower position of the active core, whereas earlier failure at higher position during the reflooding. Active and passive equipment affects fuel temperature, the oxidation conditions of the fuel, the interaction of fission products and structural materials, and the state of the fuel, thereby affecting the release of fission products in the fuel. HPR1000 only relies on passive equipment to relieve the core degradation in severe accidents, realize the in-vessel retention of melt, and eliminate the ex-vessel release possibility of fission product. It is hoped that the results can provide references for HPR1000 to formulate the severe accident management guidelines (SAMG).

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