基于MAAP5程序的秦山核电站严重事故分析

应用MAAP5程序建立了秦山核电站一、二回路，安全系统以及安全壳的模型，并以冷段双端断裂叠加高高、高、低压安注失效，安全壳喷淋系统失效为例，对该严重事故序列进行了模拟计算，给出了瞬态过程一些重要参数随时间的变化规律。结果表明：在72 h内无能动干预手段的条件下，安全壳的完整性可得到保证，相关数据可为秦山核电站严重事故预防和事故缓解措施的制定提供重要参考。

Severe Accident Analysis of Qinshan Nuclear Power Plant Based on MAAP5 Code

The MAAP5 code was applied for modeling of primary and secondary circuits, safety system and containment for Qinshan Nuclear Power Plant in this paper. And by applying the code, a severe accident scenario of large break loss of coolant accident (LBLOCA) at cold leg with failure of high-high, high, and low pressure injections and containment spray was selected for simulation and calculation, and some important transient process parameter change laws with time were given. The analysis results show that under the condition of no active intervention within 72 h, the integrity of the containment can be guaranteed and the relevant data of which can provide important reference for the establishment of accident prevention and mitigation measures of Qinshan Nuclear Power Plant.