摘要
利用LOFTRAN2程序研究了某核电厂蒸汽发生器主给水管道断裂事故工况下非能动余热排出换热器(PRHR HX)的冷却能力。分析结果表明,在极端事故工况下,反应堆冷却剂系统(RCS)的长期冷却能够持续进行,PRHR HX能够在36h内将RCS冷却到215.6℃,符合先进轻水堆用户要求文件(URD)的规定。敏感性分析表明,PRHR HX污垢系数和安全壳内置换料水箱初始温度对长期冷却能力有重要影响,在实际运行中需引起注意。
The cooling performance of PRHR HX in main feedwater line break accident was analyzed with LOFTRAN2 code.The analysis results show that the long term cooling is sustaining and PRHR HX is able to cool the RCS to 215.6 ℃in 36 h even under extreme situation,which conforms to the requirement of advanced light water reactor utility requirements document（URD）.The sensitivity analysis results show that the fouling factor of PRHR HX and the initial temperature of in-containment refueling water storage tank（IRWST）may affect the long term cooling performance significantly,so it must be paid attention in plant operation.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2016年第3期454-458,共5页
Atomic Energy Science and Technology
