核电站非能动辅助给水系统仿真研究

以先进核电站AP1000为研究对象，在其蒸汽发生器二次侧设计了1套耗汽驱动汽动辅助给水泵的非能动辅助给水系统。使用RELAP5程序计算分析全厂断电事故下设计系统的运行特性，研究其应对事故工况的能力。计算结果表明：全厂断电事故下，设计的非能动辅助给水系统可有效地排出堆芯余热，保证反应堆的安全；由于冷却剂体积收缩，170 min时稳压器排空；该系统可连续运行200 min，排出事故后的大部分堆芯余热。非能动辅助给水系统可作为全厂断电事故后的应急缓解方案。

Simulation Research on Passive Auxiliary Feedwater System for NPP

This paper took advanced nuclear power plant (NPP) AP1000 as research object and made a design for passive auxiliary feedwater system (PAFS) on the secondary side of steam generator (SG), of which the auxiliary feedwater pump was driven by steam exhaust. The operation characteristics of PAFS were calculated under station blackout (SBO) accident to analyze the capability of coping with accident by using RELAP5 code. The results indicate that PAFS can remove core residual heat significantly and assure the reactor safety after SBO accident. The pressurizer will be emptied at 170 min later caused by coolant volume shrinkage. The continuous operation time of PAFS is 200 min, which would remove most of core residual heat. PAFS can be used as emergency mitigating scheme for SBO accident.