NHR-200燃料组件定位格架水力学模拟实验研究  

Experimental simulation study on hydraulic behavior of fuel assembly grid of NHR 200

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

机构地区：[1]清华大学核能技术设计研究院

出　　处：《清华大学学报（自然科学版）》1998年第12期1-3,8,共4页Journal of Tsinghua University(Science and Technology)

基　　金：国家"九五"科技攻关项目

摘　　要：为了掌握２００ＭＷ核供热堆定位格架对燃料组件阻力系数的影响，采用１１的实验本体，模拟条件为几何形状，雷诺数相同，在ＨＲＨＴＬ－２００水力实验回路上完成本实验研究。描述了实验本体的设计及制作方法，研究了燃料组件进口节流孔板在开孔直径分别为７０ｍｍ，９０ｍｍ和１１０ｍｍ条件下，燃料组件及模拟定位格架的流动阻力特性。分析了定位格架对燃料组件阻力系数的影响。实验还研究了有、无定位格架时棒束机械振动对燃料组件阻力系数的影响。实验结果表明棒束机械振动对燃料组件阻力系数的影响可以忽略。研究结果可直接用于２００ＭＷ核供热堆的热工水力学设计。The experiment was carried out on the 200MW nuclear heating reactor's (NHR 200) hydraulic test loop (HRHTL 200). The test section is an 1∶1 model, which has the same geometry and can be with the same Reynolds number as that in the fuel assembly. The principles for the design and manufacture of the test section were described. Flow resistance of the whole fuel assembly was studied under different diameter orifices (70mm, 80mm, 110mm) at the inlet of the assembly. The hydraulic behavior of grid and its effect, and the effect of mechanical vibration of the fuel bundle, on the flow resistance of the whole fuel assembly were also researched. The effect mentioned above can be neglected. The results can be directly used in the thermohydraulic design for the 200MW nuclear heating reactor.

关 键 词：核供热堆 燃料组件 定位格架 水力学模拟实验 

分 类 号：TL413.203[核科学技术—核技术及应用]