摘要
余热排出系统(RHR)是反应堆重要的流体系统。在停堆工况下,余热排出系统接入一回路对堆芯进行冷却时,若余热排出管线出现破口,会无法有效冷却堆芯,严重影响堆芯安全。本文针对华龙一号余热排出系统在接入阶段发生破口的事故进行分析,尤其针对余热排出系统与一回路相连的管线发生不可隔离的破口和余热排出系统在安全壳外的管线发生破口两种典型事故进行分析。通过计算余热排出泵的有效汽蚀余量并分析评估安全壳外破口有效隔离措施,论证了华龙一号余热排出系统设计方案能够应对破口事故,并保证对一回路堆芯的有效冷却。
The residual heat removal system(RHR)is one of the most important fluid systems in the reactor Under shutdown condition,when RHR system is connected to the primary channel to cool the core,if there is a breach in the RHR pipeline,the core cannot be effectively cooled and the safety of the core will be seriously affected.This paper analyzes the accident that the RHR system of HPR1000 breaks during the access stage,especially the two typical accidents of unisolatable breach occurred in the line connecting the RHR system to the primary circuit and breach occurred on the line outside the containment for the RHR system.By calculating net positive suction head available(NPSHa)for the residual heat removal pump and assessing the effective isolation means for the break on the outside of containment,it is demonstrated that the design scheme of HPR1000 RHR system can deal with the rupture accident and ensure the effective cooling of the primary core.
作者
盛美玲
丘锦萌
唐辉
杨志义
Sheng Meiling;Qiu Jinmeng;Tang Hui;Yang Zhiyi(Hualong Pressurized Water Reactor Technology Corporation Ltd.,Beijing 100036,China;Nuclear and Radiation Safety Center,MEE,Beijing 100082,China)
出处
《核安全》
2020年第6期36-43,共8页
Nuclear Safety
关键词
余热排出系统
破口事故
汽蚀余量
安全壳隔离阀
residual heat removal system
break accident
net positive suction head
containment isolation valve
