摘要
在反应堆运行过程中发生严重的失水事故(LOCA)时,应急堆芯冷却系统启动,冷的安注水从安注接管注入反应堆压力容器(RPV)中,此时压力容器还维持较高压力,这种瞬态就称为承压热冲击,即PTS(Pressurized ThermalShock)。按照10CFR50。61和RCC-M规范,对安注接管、焊缝和堆芯筒体三个区域,进行了PTS工况评估,分析结果表明,在发生PTS时,压力容器的完整性是能够保证的。
The most severe accident condition of a reactor pressure vessel (RPV) in service is the loss of coolant accident (LOCA). The cold safety injection water is pumped into the downcomer of the PRV through inlet nozzles, while the internal pressure may remain at high level. This accident is called as pressurized thermal shock (PTS) transient. In accordance with 10 CFR50.61 and RCC-M code, PTS evaluations were performed for core region, welded region and safety injection nozzle in this paper. As the results the integrity of them for PTS transient was verified.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2002年第A02期99-102,共4页
Nuclear Power Engineering
