原子能科学技术Issue(10)：1790-1796,7.DOI:10.7538/yzk.2014.48.10.1790
钠冷快堆燃料组件热工水力特性数值模拟与分析
Numerical Simulation and Analysis on Thermal-hydraulic Behavior of Fuel Assembly for Sodium-cooled Fast Reactor
摘要
Abstract
The thermal-hydraulic behavior of triangular arranged fuel bundle with wrapped wire spacer of fuel assembly for sodium-cooled fast reactor was investigated by employing CFD code CFX ,and the results were compared with subchannel analysis code SuperEnergy .Fuel bundles composed of 7,19 ,37 and 61 fuel rods were analyzed sepa-rately .The axial velocity ,cross flow mixing effect ,and temperature rise along axial direction for different subchannels of the fuel bundle were discussed ,and the effect of wrapped wire spacer was carefully investigated .The results show that the wrapped wire spacer plays an important role on the cross flow effect and axial velocity distribution as well as the temperature rise in different subchannels .Moreover ,with the increase of fuel rods ,the flow in fuel bundle becomes more complicated ,and the non-uniformity of the axial flow also shows a tendency to enhance .关键词
钠冷快堆/燃料组件/CFD/热工水力Key words
sodium-cooled fast reactor/fuel assembly/CFD/thermal-hydraulic分类
能源科技引用本文复制引用
刘洋,喻宏,周志伟..钠冷快堆燃料组件热工水力特性数值模拟与分析[J].原子能科学技术,2014,(10):1790-1796,7.基金项目
863计划资助项目 （）
