The natural circulation 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。
They are the natural circulation flow analysis code (MC-FLOW), the core thermal hydraulic analysis code (MC-THAS) and the pulsed reactor transient analysis code (MC-TRAN).
它包括脉冲堆自然循环分析程序（MC-FLOW）、堆芯热工水力分析程序（MC-THAS）和脉冲堆瞬态分析程序（MC-TRAN）。
The purpose of this experiment was to determine the themohydraulic parameters in pool-type nuclear heating reactor with natural circulation.
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。
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 natural circulation two phase flow system is studied experimentally.
通过实验研究了一体化自然循环反应堆压力壳上部自稳压气空间对于自然循环两相流系统启动过程中流动稳定性的影响。
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 natural circulation two phase flow system is studied experimentally.
通过实验研究了一体化自然循环反应堆压力壳上部自稳压气空间对于自然循环两相流系统启动过程中流动稳定性的影响。
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