快堆组件数值模拟研究  

Numerical Simulation of Fast Reactor Fuel Assembly

作　　者：李淞[1] 杨红义[1] 周志伟[1] 冯预恒[1] LI Song;YANG Hongyi;ZHOU Zhiwei;FENG Yuheng(China Institute of Atomic Energy, P. O. Box 275 95, 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》2018年第5期937-941,共5页Atomic Energy Science and Technology

摘　　要：为详细研究快堆组件棒束中的流动换热特性,本工作采用Fluent程序对169棒束快堆燃料组件进行三维数值模拟。结果表明,在流量为10.92~18.67kg/s时,计算得到的压降与已公开发表文献结果的相对偏差小于3.41%。内子通道的相对温度升高,呈现出周期为1/3螺距的波动,内子通道的局部温度比子通道程序SUPERENERGY计算的结果更高。根据模拟计算结果可更为准确地预测棒束通道内的流动换热情况,为今后组件棒束热工水力学设计提供参考。In order to study the thermal and flow pattern of fuel assemblies in fast reactor,3 Dsimulation was performed for the 169 bundle wire-wrapped fast reactor fuel assemblies using CFD code Fluent.The result shows that when the flow rate is in the range of 10.92 to 18.67 kg/s,the relative deviation of calculated pressure drop compared with experimental results from the reference is less than 3.41%.The relative temperature of inner sub-channels rises with a fluctuation period of 1/3 of rod pitch.Local temperature of inner sub-channels can be higher than the result of sub-channel code SUPERENERGY.Based on simulation results the flow distribution and heat exchange in fuel assemblies can be more accurately determined,and it can provide reference for future thermal-hydraulic design of sub-channels.

关 键 词：快堆 棒束 数值模拟 

分 类 号：TL331[核科学技术—核技术及应用]