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作 者:李明刚[1] 聂常华[1] 王均[1] 杨祖毛[1] 谢峰[1] 湛力[1] 吴小飞[1] 黄彦平[1]
机构地区:[1]中国核动力研究设计院反应堆工程研究所,成都610041
出 处:《核动力工程》2015年第3期15-19,共5页Nuclear Power Engineering
摘 要:选取在通道形状、热工水力特性等方面接近原型组件的典型栅元,是反应堆的研究设计中重要的一环。通过适用于紧密排列螺旋绕肋组件的数值模拟方法,分析棒束规模对热工水力特性的影响。数值计算结果表明:与原型组件217棒束相比,19棒束组件的"冷壁效应"、"边壁效应"已经较弱,当量直径、阻力压降、中心通道无量纲质量流速、热通道的传热系数等关键参数的偏差小于13%,确定反映原型组件热工水力特性的典型栅元为19棒束组件。It is important in the reactor research and design to choose the typical lattice, which could represent the channel shape and thermal-hydraulic performance of the prototype assembly. In this study, the effect of bundle scale on thermal-hydraulic performance has been analyzed by numerical simulation method which applies to the tight arrangement spiral-fin fuel assembly. Simulation results show that compared with prototype assembly 217 rod bundle, cold wall effect and side wall effect of 19 rod bundle could be neglected. The deviations of equivalent diameter, pressure drop, center channel dimensionless mass flux and hot channel heat transfer coefficient are less than 13%. Therefore, 19 rod bundle are chosen to be the typical lattice for tight arrangement spiral-fin fuel assembly.
分 类 号:TL352[核科学技术—核技术及应用]
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