用RELAP5程序分析非能动堆芯应急冷却系统实验结果  

RELAP5 Analysis of Passive Emergency Core Cooling System Tests

作　　者：彭云康[1] 郑华[1] 

机构地区：[1]中国核动力研究设计院,成都610041

出　　处：《核动力工程》2003年第1期15-17,共3页Nuclear Power Engineering

摘　　要：先进压水堆的一个显著特点是非能动系统的高可靠性,评价这些系统的运行特性以及系统分析程序(如RELAP5等)的计算能力是非常重要的。中国核动力研究设计院设计建造了原理性的非能动堆芯应急冷却系统实验装置,并完成了相关实验研究,取得一批有价值的数据。本文用RELAP5/MOD3.2程序对实验过程进行了模拟分析,通过计算结果与实验结果的比较,初步评价了RELAP5/MOD3.2程序的计算能力。One of the apparent characteristics of advanced PWR is the high reliability of passive safety system. It is important to assess the operation behavior of such system and the capability of system analysis code such as RELAP5.One principal test facility, passive emergency core cooling system, has constructed by Nuclear Power Institute of China and the related experiments had been carried out. The RELAP5/Mod3.2 was used to simulate the experiments in this paper. The simulation capability of RELAP5/Mod3.2 in passive emergency core cooling system was assessed by the comparison between the experimental results and calculation results.

关 键 词：RELAP5 非能动 堆芯应急冷却系统 

分 类 号：TL353.1[核科学技术—核技术及应用]