摘要
分析了中国实验快堆事故停堆后余热的排放过程。对热钠池中的流动与传热采用多孔介质模型的全三维数值模拟，对堆芯支路、事故热交换冷却回路和空冷塔冷却支路采用一维系统分析程序进行数值模拟。通过三维部分和一维部分相互耦合，模拟了余热排放的瞬态过程，得到了堆芯出口温度、燃料元件包壳的最高温度、余热热交换器的余热排放功率等许多重要参数随时间的变化曲线。
This paper analyzes the process of decay heat removal after Chinese Experimental Fast Reactor(CEFR)scram. The 3 D Thermal hydraulic analysis with porous media method is applied in hot plenum, 1 D system analysis is used in three loops of core, decay heat exchanger (DHX)and air cooling tower. In the calculation, 3 D and 1 D are coupled with each other to simulate transient process of decay heat removal. Many important numerical results, such as core outlet temperature variation, the highest temperature of cladding and removal power of DHX etc., are presented and discussed in this paper. They provide valuable reference for the design and safety assessment of CEFR.
出处
《核科学与工程》
CSCD
北大核心
1999年第3期201-201,200,共1页
Nuclear Science and Engineering
基金
国家"863"高科技项目
曹光彪基金
科学与工程计算国家重点实验室的资助
