基于MELCOR的HE-FUS3实验模拟及氦气冷却系统安全初步分析

Modeling of HE-FUS3 Experimental Loop and Preliminary Safety Analysis of Helium-cooled Systems with MELCOR Program

MELCOR程序是由美国Sandia国立实验室为美国核管会开发,用于模拟轻水堆严重事故进程主要现象的一体化系统软件。针对HE-FUS3氦气实验回路进行了建模和计算分析,取得了良好的结果。该成果可为氦气冷却系统安全分析提供初步的参考;并将继续扩展使用于ITER氦冷包层系统安全分析。首先利用MELCOR对HE-FUS3氦气实验回路进行建模,对LOFA30失流事故进行了稳态及瞬态分析;并将MELCOR程序计算值与实验值进行了对比。结果显示:通过MELCOR对实验回路建模得到的LOFA30失流事故稳态计算值与CATHARE 2参考值大体一致;在失流事故的瞬态进程中,大部分热工水力参数计算值均与实验值符合较好。结果证明利用MELCOR程序对HE-FUS3实验回路整体建模的可靠性很高,通过MELCOR程序计算,用于分析氦气冷却系统安全性的数据准确,可靠,可以继续使用MELCOR对该领域进行更为深入,系统的研究和分析。

MELCOR is being developed at Sandia National Laboratories for the U. S. Nuclear Regulatory Commission. MELCOR is a fully integrated,engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. In this paper,the HE-FUS3 experimental loop is modeled and analyzed with a good calculated result. The results can provide a preliminary reference for the safety analysis of helium-cooled systems and furthermore be used in the safety analysis of ITER helium-cooled blanket system. The steady and transient behaviors of LOFA30 loss of flow accident are modeled and analyzed using the MELCOR code,then the MELCOR calculated values are compared with the experimental values. The results indicate that the steady calculated values of LOFA30 loss of flow accidents obtained by modeling of the experimental loop through MELCOR comply well with the CATHARE 2 reference values. In the transient process of the loss of flow accident,most of the calculated thermal-hydraulic parameters are greatly consistent with the experimental values. This shows that it＇s of high reliability to use MELCOR program to model HE-FUS3 experimental loop. Accoding to the calculation of MELCOR,data which are used in the safety analysis of helium-cooled systems are accurate and reliable,and we can use MELCOR in this field for further research and analysis.