水力驱动控制棒热态极限落棒能力分析  

Scram ability of hydraulic control rod drives in severe accidents at high temperatures

作　　者：王金华[1] 薄涵亮[1] 郑文祥[1] 

机构地区：[1]清华大学核能技术设计研究院,北京100084

出　　处：《清华大学学报（自然科学版）》2002年第12期1628-1631,共4页Journal of Tsinghua University(Science and Technology)

基　　金：清华大学"九八五"基金资助项目(985-01-04-014)

摘　　要：控制棒驱动机构是核反应堆的关键设备,其是否正常运行直接关系到核反应堆的安全性。该文对水力驱动控制棒系统在摩擦力卡棒和倒置等极限工况下的停堆问题,提出了步进缸内腔卸压的解决方法,并在热态实验研究的基础上,建立了正置落棒和倒置插棒的理论模型。分析了极限落棒过程参数(位移、速度和棒内外差压)的变化规律,得到了摩擦力卡棒和倒置等极限工况下控制棒插入堆芯的能力。结果表明:在极限工况下水力驱动控制棒有足够能力插入堆芯。The control rod drives are a very important nuclear safety component in nuclear reactors. This paper describes a method for pressure discharge from the stepping cylinder's inner tube to enable scramming of the hydraulic control rod drives in the event of control rod hang up and inversion conditions. The scram and pressure discharge models were derived from high temperature experiments with either normal or inversion conditions. The displacement, the velocity, and the pressure drop between inside and outside of rod in the scram process were analyzed so that the control rods can scram in the most severe accidents. The results show that the hydraulic control rods will enter the reactor core in the most severe accidents.

关 键 词：落棒能力 低温核供热堆 水力驱动控制棒系统 极限落棒 热态实验研究 安全运行 

分 类 号：TL413.2[核科学技术—核技术及应用] TL36