They are the natural circulation flow analysis code (MC-FLOW), the core thermal hydraulic analysis code (MC-THAS) and the pulsed reactortransient analysis code (MC-TRAN).
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
In order to carry out power transient tests for PWR fuel element in China Advanced research Reactor (carr), the research and conceptual design of 3he pressure control loop were completed.