钠冷快堆乏燃料组件热工水力分析程序开发  

Development of Thermal-hydraulic Analysis Code for Spent Fuel Assembly of Sodium Cooled Fast Reactor

作　　者：马晓[1] 林超[1] 李淞[1] 周志伟[1] 冯预恒[1] 张东辉[1] MA Xiao;LIN Chao;LI Song;ZHOU Zhiwei;FENG Yuheng;ZHANG Donghui(Division of Reactor Engineering Technology Research,China Institute of Atomic Energy,Beijing 102413,China)

机构地区：[1]中国原子能科学研究院反应堆工程技术研究部,北京102413

出　　处：《原子能科学技术》2020年第4期606-614,共9页Atomic Energy Science and Technology

摘　　要：为了对示范快堆乏燃料组件的热工水力特性进行分析,自主研发了钠冷快堆乏燃料组件热工水力分析程序SPATANS。该程序基于子通道分析方法,采用适用于低流量下的流动换热和交混关系式。针对乏燃料组件棒束区进行计算,得到组件不同高度处各子通道的温度、压力等热工参数,并将计算结果与三维计算流体力学FLUENT程序的结果进行对比分析。结果表明:自主研发程序的计算结果与FLUENT程序的计算结果较为吻合,偏差在工程可接受范围内,且其计算效率明显高于FLUENT程序。初步表明SPATANS程序可用于钠冷快堆乏燃料组件热工水力分析,并具有良好的应用前景。In order to analyze the thermal-hydraulic characteristics for spent fuel assembly of sodium cooled fast reactor,thermal-hydraulic code SPATANS for spent fuel assembly of sodium cooled fast reactor was independently developed.SPATANS code was based on sub-channel analysis method,and flow heat exchange and mixing correlations fitted for lower flow were used in the code.Computation was performed for bundle region of spent fuel assembly,and thermal parameters such as temperatures and pressures for various sub-channels at different heights of assembly were got.Computation results were compared with those of three-dimensional computational fluid dynamics FLUENT code.The results show that the computation results of the independently developed code are consistent with those of the FLUENT code,and the deviation is within the acceptable range in engineering.However,the computation efficiency of the code is significantly higher than that of the FLUENT code.It’s preliminarily indicated that SPATANS code can be used in the thermal-hydraulic analysis for spent fuel assembly of sodium cooled fast reactor,and there is a good prospect of application.

关 键 词：钠冷快堆 乏燃料组件 棒束区 热工水力分析 

分 类 号：TL333[核科学技术—核技术及应用]