摘要
应用RETRAN 0 2程序 ,结合一堆芯流道阻塞典型模型 ,计算了板状燃料堆芯发生流道阻塞事故时诸热工水力参数的瞬态变化 ,分析了事故工况下的物理过程 。
On the basis of a typical model of the flow blockage at a reactor core, transient variations of thermohydraulics parameters at a flow blockage incident are analyzed and the relevant measure of protection and its effects are discussed. It is shown that the flow blockage accident will cause the parameters of coolant and associated plate type fuel to change dramatically. The hydraulic oscillation will form in the blockage area, which will mechanically damage the reactor core and circulating system.
出处
《原子能科学技术》
EI
CAS
CSCD
2002年第1期76-79,共4页
Atomic Energy Science and Technology