摘要
在非失水事故(LOCA)事故工况下,AP1000核电厂应在36 h内将反应堆冷却剂系统(RCS)平均温度冷却至215.6℃,但因冷凝水回流率远低于预期目标而无法实现。经分析并通过穹顶冷凝水滴落等试验进行验证,确定了冷凝水损失途径。因此,执行了一系列包括修改环吊梁、内部加强肋、冷凝水回流槽结构在内的设计优化。安全停堆评价证明在丧失正常给水叠加丧失厂外电源事故后,AP1000核电厂可在34.6 h内将RCS平均温度降至215.6℃。
During any non-LOCA event,the average temperature of the reactor cooling system(RCS)should be decreased to 215.6℃ within 36 hours in AP1000 nuclear power plant.However,this goal cannot be achieved because the rate of condensate return was far lower than that expected.Through the analysis and verification of the dome condensation drop test,the path of condensation loss was determined.Therefore,a series of the design modifications to the polar crane girder,the internal stiffener and the condensation return gutter were carried out.Lastly,the safety shutdown temperature evaluation showed that the AP1000 plant could reduce the RCS average temperature to 215.6℃ within 34.6 hours after the loss of normal feedwater and the loss of off-site power concurrently.
作者
马柏松
庄亚平
郄卫青
Ma Baisong;Zhuang Yaping;Qie Weiqing(Shandong Nuclear Power Co.,Ltd.,Yantai,Shandong,265116,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2020年第5期79-83,共5页
Nuclear Power Engineering
