一体化先进堆全厂断电事故下非能动余热排出系统能力分析  

Performance Analysis of Passive Residual Heat Removal System under Blackout Accident of Chinese Integral Advanced Reactor

作　　者：沈瑾[1] 江光明[1] 唐钢[1] 余红星[1] 

机构地区：[1]中国核动力研究设计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6期80-83,共4页Nuclear Power Engineering

摘　　要：中国核动力研究设计院(NPIC)设计的中国一体化先进堆(CIP)余热排出系统是非能动系统。采用RELAP5/MOD程序分析计算该堆全厂断电事故后堆芯核功率、堆芯平均温度、一回路和二回路压力,以及非能动余热排出系统功率随时间的变化,论证了非能动余热排出系统对事故的缓解能力。分析结果表明,CIP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。The residual heat removal system of Chinese Integral Advanced Reactor （CIP） designed by Nuclear Power Institute of China is of passive. In this paper, RELAP5/MOD is used to analyze and compute the core nuclear power, core average temperature, pressures of first and second loop and the PRHR power variation with time, and verifies the accident mitigation capability of the PRHR. The analysis results show that PRHR of CIP can successfully build the natural circulation and remove the core residual heat after the blackout accident.

关 键 词：一体化先进堆 非能动余热排出系统 全厂断电事故 

分 类 号：TL364[核科学技术—核技术及应用]