原子能科学技术Issue(1)：61-66,6.DOI:10.7538/yzk.2014.48.01.0061
快堆燃料组件棒束通道内流动和传热现象分析与研究
Analysis and Investigation on Flow and Convective Heat Transfer Phenomena of Fast Reactor Fuel Bundle
摘要
Abstract
Commercial CFD code CFX 12.0 was used as an approach to investigate the flow and convective heat transfer phenomena of a typical 7-pin fuel bundle with wrapped-wire .The pressure drop coefficient and Nusselt number under different Re were obtained , and the simulation results are in good agreement with empirical correlations .The transverse flow effects in three kinds of typical subchannels were investigated ,and its features were analyzed .The results show that the corner channel’s transverse flow intensity varies heavily along the axial direction ,and the transverse flow intensities in three typical subchannels show periodic feature .The local Nusselt number distribution on three cross sections of the central rod surface was also analyzed .The results show that the minimum local Nusselt number occurs close to the contact location of wire and rod ,which means that the convective heat transfer condition is the worst in such area ,and the special attention in accident analysis is deserved .关键词
计算流体力学/棒束通道/压降系数/对流换热/横向流Key words
CFD/fuel bundle/pressure drop coefficient/convective heat transfer/transverse flow分类
能源科技引用本文复制引用
刘洋,喻宏,刘一哲..快堆燃料组件棒束通道内流动和传热现象分析与研究[J].原子能科学技术,2014,(1):61-66,6.基金项目
863计划资助项目 （）
