Based on an exact mathematic model, a measurement method regarding core thermal power of nuclear power pressurized water reactor and its error analysis were presented in this paper.
通过建立精确的数学模型，提出了一种测量核电站压水反应堆堆芯热功率的方法，并对该方法进行了误差分析。
2
The improved transient sealing analysis program for reactor pressure vessel is applied to analyze the 1/4 structure of the model under the cool and the thermal work conditions.
应用改进后的反应堆压力容器瞬态密封分析程序对压力容器模拟体1/4模型进行了冷态和热态密封分析。
3
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).