基于ATHLET软件与仿真机系统对压水堆热管段小破口失水事故的分析

Small Break Loss of Coolant Accident Analysis in PWR Hot Leg Based on ATHLET and SIMIS

为避免反应堆在一回路小破口失水事故下,堆芯因不充分冷却而发生融化事故和放射性的外泄,利用大亚湾1 000 MW核电站仿真机系统对压水堆主冷却剂系统热管段小破口失水事故进行计算分析。通过实验数据分析不同破口尺寸情况下出入口温度变化趋势,并将分析结果与ATHLET软件模拟情况的参数变化相比较,以此来验证仿真机系统能否精确地对热管段小破口事故进行仿真机模拟,同时为分析不同破口尺寸情况下出入口温度变化趋势提供数据参考。

The small break loss of coolant accident in hot leg of PWR primary coolant system was analyzed with the Daya Bay 1000 MW nuclear power plant simulation system in order to avoid the reactor core melt and the radioactive leakage due to the inadequate cooling of the reactor core led by the small break loss of coolant accident in primary circuit. The temperature variation trend of inlet and outlet under different break sizes were analyzed on the basis of the simulation data and the results were compared with the results which were calculated by the ATHLET software to verify the accuracy of the simulation system and provide data references for the analysis of the inlet and outlet temperature variation under different break sizes.