200MW 核供热堆水力稳定性实验数值模拟分析

Numerical Simulating Analysis for the Hydrodynamic StabilityExperiment of the 200MW Heating Reactor

为确定２００ＭＷ核供热堆的安全性并为今后发展奠定研究基础，在改装的俄罗斯ＫＣ实验装置上，完成了该核供热堆主回路系统水力稳定性实验研究。然后应用ＲＥＴＲＡＮ０２程序完成主要实验工况数值模拟计算。理论计算和实验测量的对比结果表明，两者间有较好的符合，获得有益于核供热堆安全设计的一些结论。

In order to determine the safety of the 200MW Nuclear Heating Reactor design and lay a foundation for the future development of the reactor,the hydrodynamic stability experiment has been completed by means of the Russian KC test loop.Numerical simulating analysis of the main experiment results has been accomplished by use of RETRAN 02 code.Comparison analysis shows that there is good coincidence degree between the results of the experimental measurement and the numerical analysis,and some conclusions,which are helpful to the design of NHR 200,are also given in this paper.