AP1000安全壳子隔间压力响应分析

Analysis on Pressure Response of Containment Subcompartments for AP1000

用TMD程序建立了AP1000核电厂安全壳子隔间73节点模型,选取3种典型的破口尺寸和类型,计算了不同位置破口导致的子隔间压力响应。同时分析了程序模型和输入参数对结果的影响,得到极限工况计算结果,并识别出安全壳隔间薄弱环节。结果表明,增大薄弱节点的流通面积可明显降低隔间最大压差,提高安全裕量。

The 73-node model of containment subcompartments for AP1000 nuclear power plant was set up using TMD code. Then 3 kinds of breaks with representative sizes and types were selected in order to calculate the pressure response of subcompartments due to breaks at different locations. Besides, the influence of model and input parameters was evaluated to get the results of limiting cases, and the weak nodes of containment subcompatments were identified. The results show that the maximum differential pressure can be reduced so as to increase the safety margin by enlarging the flow area of weak nodes.