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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4期612-616,共5页Atomic Energy Science and Technology
摘 要:为详细研究快堆组件稠密棒束中的冷却剂流动方式,本工作采用Fluent程序对169棒束快堆燃料组件进行了三维数值模拟,并与已公开发表的文献结果进行了对比。由计算结果可知:计算得到的摩擦系数结果在Re为35 885~61 354时与试验结果符合较好;从中心到外围,横向流和轴向流在不同的方向和位置呈现出不同的流动特性。根据模拟结果可更准确地预测棒束通道内的流动情况,可为今后稠密棒束组件水力学设计和子通道内流量测量试验提供参考。In order to study the flow pattern of compact fuel assembly in fast reactor,three-dimensional simulation was performed to the 169-rod bundle fuel assemblies in fast reactor with Fluent code,and the results were compared with those in published papers.The results show that the calculated friction coefficient is in good agreement with experimental result when Re is in the range of 35 885 to 61 354.From central region to peripheral region,the characteristics of axial flow and cross flow in bundle vary with the direction and distance.According to the simulation result,the flow pattern in compact fuel assembly can be more accurately determined,and references for hydraulic design and flow measurement in sub-channels for compact fuel assembly can be provided.
分 类 号:TL331[核科学技术—核技术及应用]
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