基于Fluent程序的AP1000堆芯组件热工水力计算与分析  

Thermohydrodynamic calculation and analysis for AP1000 Reactor Core Assembly based on the code of Fluent

作　　者：乔雪冬 毕金生 贾斌 李远山 靖剑平 张春明 QIAO Xue-dong BI Jin-sheng JIA Bin LI Yuan-shan JING Jian-ping ZHANG Chun-ming(Nuclear and Radiation Safety Center, Beijing 100145)

机构地区：[1]环境保护部核与辐射安全中心,北京100145

出　　处：《核科学与工程》2016年第4期476-481,共6页Nuclear Science and Engineering

基　　金：大型先进压水堆及高温气冷堆电站国家科技重大专项:CAP1400安全审评关键技术研究(2013ZX06002001)

摘　　要：本文利用计算流体力学程序Fluent对AP1000反应堆组件稳态运行时的内部温度场和速度场的分布情况进行模拟计算,研究格架对流动的影响及计算在不同模型下格架的阻力系数,并将Fluent与VIPRE-W的计算结果进行对比,以验证Fluent程序在计算堆芯组件时的准确性。The temperature and velocity distribution of AP1000 reactor core assembly was modeled and calculated by the CFD code of Fluent in this paper.The influence of grid to flow was studied and the flow resistance coefficient was calculated.The veracity for the code of Fluent applying on the fuel assembly was testified by comparing with the code of VIPRE-W.

关 键 词：AP1000 堆芯组件 热工 格架 

分 类 号：TL33[核科学技术—核技术及应用]