200MW 核供热堆燃料组件阻力特性模拟实验  

Simulation Experiment on Fuel Assembly FlowResistance Behavior of NHR 200

作　　者：姜胜耀[1] 张佑杰[1] 马进[1] 博金海[1] 高琅琅[1] 马昌文[1] 

机构地区：[1]清华大学核能技术设计研究院

出　　处：《核动力工程》1998年第4期302-307,共6页Nuclear Power Engineering

基　　金：国家九五科技攻关专题

摘　　要：实验研究在２００ＭＷ核供热堆（ＮＨＲ２００）水力学实验回路（ＨＲＨＴＬ２００）上完成，采用１∶１的实验本体，模拟条件为几何形状和雷诺数相同。研究了燃料组件入口节流孔板不同开孔直径（５０～１１０）条件下，燃料组件，节流孔板，进、出口格板，棒束及出口段的流动阻力特性，研究结果可直接用于ＮＨＲ２００的热工水力学设计。The Experiment was carried out on the NHR 200 hydraulic test loop(HRHTL 200). The test section is a 1:1 model, which has the same geometry and can be with the same Reynolds number as the fuel assembly. The flow resistance of the whole fuel assembly, the orifice,the inlet and outlet grids, the fuel bundle and the exit section were studied under different diameter of orifice(50～110)at the inlet of the assembly.The results can be directly used in the thermohydraulic design for the NHR 200.

关 键 词：核供热堆 燃料组件 流动特性 模拟实验 阻力 

分 类 号：TL413.203[核科学技术—核技术及应用]