摘要
以AP1000主冷却剂系统为原型,提出了一种二次侧非能动余热排出(PRHR)系统设计方案,并采用RELAP5/MOD3.2程序分析计算了全厂断电事故下该系统的瞬态响应过程,对其余热排出能力进行了评估。此外,根据计算结果分析了影响系统自然循环能力和密度锁内冷热界面稳定性的因素。分析结果表明,合理设计二次侧PRHR系统,可以保证依靠自然循环有效地导出堆芯余热;PRHR系统冷热源中心高度差和密度锁内局部阻力是影响系统工作能力的主要因素。
One design scheme for secondary-side passive residual heat removal system is presented based on the prototype of AP1000 primary system. The RELAP5/MOD3.2 is used to simulate and analyze the transient process of the PRHR system during blackout accident. In addition, the factors having effects on the capacity of natural circulation and the stability of interface between cold and hot fluid in density lock are analyzed based on the calculation results. The results show that the core residual heat is able to be removed effectively using natural circulation, and the capacity of system can be assured by the PRHR system which is rationally designed, and the height difference between steam generator and PRHR heat exchanger and the local resistance in density lock are the principal factors having effects on the operating capacity of system.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2010年第4期25-30,共6页
Nuclear Power Engineering
基金
国家自然科学基金资助(50776022)
关键词
RELAP5
菲能动余热排出系统
自然循环
瞬态分析
RELAP5, Passive residual heat removal system, Natural circulation, Transient analysis