The naturalcirculation ability of PWR (pressurized water reactor) coolant system is one of inherent safeties of this kind NPP (nuclear power plant).
压水堆核电厂反应堆冷却剂系统自然循环能力是这种类型核电厂固有的安全性之一。
2
The purpose of this experiment was to determine the themohydraulic parameters in pool-type nuclear heating reactor with naturalcirculation.
试验是为确定自然循环池式核供热堆的热工水力学参数而进行的。
3
The influence of the gas space on the top of an integral reactor vessel on the flow stability in the start up process of a naturalcirculation two phase flow system is studied experimentally.