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。
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。
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）。
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