中国工程试验堆堆芯入口流量分配特性实验研究

堆芯入口流量分配研究是新型反应堆设计过程中一项重要的工程验证实验，其结果能为反应堆的热工水力及安全分析提供数据支撑。本文针对中国工程试验堆（CENTER），采用缩比模型开展了堆芯入口流量分配特性实验研究，在不同工况下获得了模拟燃料组件、铍/铝组件、钴靶组件及控制棒导向管内的流量分配因子。实验结果表明：在本文研究的工况范围中，堆芯中大部分冷却剂流过模拟燃料组件，同类型模拟组件间的流量分配较均匀，最大流量相对偏差在±4%以内。实验入口总流量对流量分配特性几乎没有影响。

Experimental Investigation of Flow Distribution Characteristic at Core Inlet in CENTER

Flow distribution investigation at core inlet is an important engineering validation experiment during the design process of a new type nuclear reactor. It can provide experimental data for thermal-hydraulics and safety analysis of nuclear reactor. A flow distribution characteristic experimental investigation at core inlet in China Engineering Test Reactor (CENTER) was carried out based on a scaled-down model. Flow distribution factors under different working conditions among simulating fuel assembly, beryllium/aluminum assembly, and cobalt target assembly and control rod guide tube simulators were obtained. Experiment results show that under the working conditions in this paper, large amount of coolant flows through simulating fuel assembly and the flow distribution factors among the same kind assemblies are homogeneous, and the max relative deviation is within ±4%. The total inlet flow in the experiment has little influence on flow distribution characteristic.