先进堆非能动余热排出系统应对全厂断电事故的能力分析  

Application of Passive Residual Heat Removal System under Blackout Accident of Chinese Advanced Nuclear Power Plant

作　　者：沈瑾[1] 江光明[1] 唐钢[1] 余红星[1] 

机构地区：[1]中国核动力院核反应堆系统设计技术国家重点实验室,成都610041

出　　处：《核动力工程》2007年第2期87-90,共4页Nuclear Power Engineering

摘　　要：采用RELAP5/MOD程序对先进堆全厂断电事故进行分析计算,论证非能动余热排出系统对事故的缓解能力。分析表明,先进堆在发生全厂断电事故后,完全能够依靠非能动余热排出系统导出堆芯余热,保证反应堆的安全;先进堆非能动余热排出系统的设计总体上是成功的。The passive residual heat removal （PRHR） system provides emergency core decay heat removal during the transient accidents such as blackout or loss of forced reactor coolant flow. Referenced to the design of AP1000, Chinese advanced nuclear power plant applied PRHR to mitigate the accident consequence only by the natural circulation. The blackout accident was calculated to identify the capacity of PRHR of Chinese advanced nuclear power plant by using RELAP5/MOD3 code. The analysis results show that PRHR of HLS can build the natural circulation and remove the core residual heat after the blackout accident successfully.

关 键 词：先进堆 非能动余热排出系统 全厂断电事故 自然循环 

分 类 号：TL364.4[核科学技术—核技术及应用]