控制棒导向管外流道旁流特性实验研究

冷却剂流经核反应堆堆芯时，绝大部分通过燃料组件内部流过，带走裂变能量。另外一小部分作为旁流经过燃料组件外侧流道、控制棒导向管外侧及内侧流道流出。为确保反应堆在正常运行工况下的安全性，必须限制堆芯旁流流量。本文通过开展导向管外侧流道阻力特性实验研究，在不同流量工况下获得了分段压差，并进一步拟合了雷诺数与阻力系数的关系式。实验结果表明，导向管外侧流道压力损失主要集中在堆芯下栅格板处，当反应堆额定工况运行时，单组导向管外侧流量仅为0.196 m³/h。

Experimental Investigation of Bypass Flow Characteristic in Flow Path outside Control Rod Guide Tube

When coolant flows through the nuclear reactor core, the vast majority will go into fuel assemblies to take away the fission energy. Another small amount will go into the outer flow path of fuel assemblies as well as inner and outer flow path of control rod guide tube as bypass flow. To ensure the safety of nuclear reactor under normal operation condition, the flow rate of bypass flow must be limited. In this paper, an experiment was carried out to investigate the resistance characteristics of flow path outside guide tube. Pressure loss of different sections was obtained and the relationship between Reynolds number and resistance coefficient was fitted. Experimental results show that the pressure loss of flow path outside guide tube is mainly concentrated in lower plate. The bypass flow rate outside single guide tube is only 0.196 m³/h under normal operation condition.