首页 | 本学科首页   官方微博 | 高级检索  
     

钠冷快堆燃料组件热工水力特性数值模拟与分析
引用本文: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,2014,48(10):1790-1796.
作者姓名:刘洋  喻宏  周志伟
作者单位:中国原子能科学研究院 中国实验快堆工程部,北京102413
摘    要:利用CFD程序CFX,分别对7、19、37、61根棒组成的三角形排列螺旋绕丝定位的钠冷快堆燃料组件棒束通道进行了热工水力特性的分析研究,并将结果与子通道程序SuperEnergy进行了对比验证。重点考察了棒束通道轴向流动分布、横向流交混效应及子通道轴向温升,分析了定位绕丝的影响。结果表明,绕丝对棒束通道的横向流交混效应、轴向流动分布及子通道温升有着重要影响,且随棒束的增多,通道内的流动趋向复杂化,轴向流动不均匀性有升高趋势。

关 键 词:钠冷快堆    燃料组件    CFD    热工水力

Numerical Simulation and Analysis on Thermal-hydraulic Behavior of Fuel Assembly for Sodium-cooled Fast Reactor
LIU Yang,YU Hong,ZHOU Zhi-wei.Numerical Simulation and Analysis on Thermal-hydraulic Behavior of Fuel Assembly for Sodium-cooled Fast Reactor[J].Atomic Energy Science and Technology,2014,48(10):1790-1796.
Authors:LIU Yang  YU Hong  ZHOU Zhi-wei
Affiliation:China Institute of Atomic Energy, P. O. Box 275-34, Beijing 102413, China
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 separately. 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.
Keywords:sodium-cooled fast reactor  fuel assembly  CFD  thermal-hydraulic
本文献已被 CNKI 万方数据 等数据库收录!
点击此处可从《原子能科学技术》浏览原始摘要信息
点击此处可从《原子能科学技术》下载全文
设为首页 | 免责声明 | 关于勤云 | 加入收藏

Copyright©北京勤云科技发展有限公司  京ICP备09084417号