摘要
非能动余热排出系统能在反应堆事故停堆期间,不依靠外部能量驱动导出堆芯余热.采用RELAP5/MOD3.2程序,以AP1000主冷却剂系统为原型进行建模,对非能动余热排出系统在全厂断电事故下的瞬态响应过程和工作能力进行了计算和评估.分析结果表明,合理设计非能动余热排出系统可保证其余热导出能力,使系统依靠自然循环有效地导出堆芯余热.此外,根据计算结果分析了系统冷热源中心高度差对自然循环能力的影响.
Passive residual heat removal (PRHR) system is capable of removing the core residual heat without the driving of external energy during the period of emergency shutdown. RELAP5/MOD3.2 is used to simulate and analyze the transient proceeding of AP1000 nuclear power plant with PRHR system under blackout accident. The resuits show that the core residual heat is able to be removed effectively using natural circulation and the capacity of system can be assured by PRHR system which is rationally designed. In addition, the influence of the height between cold and hot sources for PRHR system on the capacity of natural circulation is analyzed according to the resuits.
出处
《应用科技》
CAS
2009年第10期61-64,共4页
Applied Science and Technology