COMMEN程序热膨胀模型的开发和验证

Development and Validation of Thermal Expansion Model in COMMEN Code

堆芯解体事故已成为钠冷快堆安全分析的主要关注点之一。COMMEN程序是中国原子能科学研究院开发的钠冷快堆堆芯解体事故分析程序。该程序耦合了二维的时空中子动力学模块,主要用于计算堆芯丧失原有几何形状之后的事故进程。为改进COMMEN程序,须在现有的中子学模块中添加热膨胀模型。改进后的COMMEN程序计算严重事故时考虑的反应性反馈更全面。为验证该模型,使用改进后的COMMEN程序对中国实验快堆(CEFR)进行建模计算,并将计算结果和SAS4 A程序进行对比。结果表明:添加了热膨胀模型后,COMMEN程序的计算结果得到了很大改善,其结果与SAS4 A符合的很好。

The consequences of core disruptive accidents(CDAs)have been one of major concerns in the safety of sodium-cooled fast reactor(SFR).COMMEN code was developed by China Institute of Atomic Energy(CIAE)for core disruptive accidents in SFR.It was coupled with a 2-D space and time dependent neutron kinetic module,which was mainly used for simulation of the accident conditions after loss of the original core shape.In order to improve COMMEN code,it was necessary to add a thermal expansion model to its neutronics module.The improved COMMEN code contains more comprehensive reactivity feedback effects when it calculates the severe accidents.In order to verify this model,modeling and analysis for China Experimental Fast Reactor(CEFR)was performed using improved COMMEN code,and calculation results were compared with SAS4A code.It is proved that the results of COMMEN code get great improvement after adding thermal expansion model,and the result is in good agreement with that of SAS4 A code.