基于MELCOR的HE-FUS3实验模拟及氦气冷却系统安全初步分析

发布时间：2018-06-14 16:38

本文选题：MELCOR + 失流事故　；参考：《科学技术与工程》2015年30期

【摘要】：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。
[Abstract]:The MELCOR program is an integrated system software developed by the Sandia National Laboratory for the American Nuclear Regulatory Commission to simulate the main phenomena in the LWR serious accident process. The HE-FUS3 helium experimental circuit is modeled and calculated, and good results are obtained. The results can provide a preliminary reference for the safety analysis of helium cooling system and will continue to be applied to the safety analysis of ITER helium cooled blanket system. Firstly, the HE-FUS3 helium experimental loop is modeled by MELCOR, and the steady and transient analysis of LOFA30 is carried out, and the calculated value of MELCOR is compared with the experimental value. The results show that the steady-state calculation values of LOFA30 off-flow accident obtained by MELCOR are in good agreement with the reference values of CATHARE2, and that most of the calculated values of thermal hydraulic parameters are in good agreement with the experimental values during the transient process of the off-flow accident. The results show that the overall modeling of HE-FUS3 experimental circuit is highly reliable by using MELCOR program. The data used to analyze the safety of helium cooling system are accurate and reliable, and the MELCOR can be used in this field more deeply. Systematic research and analysis.
【作者单位】：西安交通大学动力工程多相流国家重点实验室核科学与技术系;中国核动力研究设计院核反应堆系统设计技术重点实验室;
【基金】：中国聚变工程实验堆(CFETR)包层热工水力设计与安全分析评价研究(2014GB114001)资助
【分类号】：TL364.4

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