【作者】 王汉； 毕勤成； 吕海财； 陆道纲；

【Author】 Wang Han;Bi Qincheng;Lv Haicai;Lu Daogang;School of Nuclear Science and Technology, North China Electric Power University;State Key Laboratory of Multiphase Flow in Power Engineering, Xi’an Jiaotong University;

【机构】 华北电力大学核科学与工程学院； 西安交通大学动力工程多相流国家重点实验室；

【摘要】 超临界水冷堆(SCWR)燃料棒束间隙小、表面热负荷高,加之超临界水在拟临界区剧烈的物性变化,使得SCWR堆芯热工-水力特性的研究成为一个重要问题。本文对间隙为2 mm的环形窄缝通道内超临界水的传热特性进行了试验研究和数值模拟,分析了流动方向对加热管壁温和换热系数的影响。研究结果表明,垂直流动中传热特性的差异与系统参数有关,浮升力和超临界水剧烈的物性变化是导致低质量流速下传热恶化发生的主要原因。更多还原

【Abstract】 Tight rod bundles were designed in the core of the Supercritical Water-cooled Reactor. Because of the small gap size, large heat load and the drastic thermophysical variations of the supercritical water in the pseudo-critical enthalpy region, the thermal-hydraulic behaviors in SCWR fuel bundle becomes an important issue. This paper investigates the heat transfer characteristics of supercritical water in a narrow annulus with experimental and numerical methods. The effects of flow direction on wall temperature and heat transfer coefficient were analyzed. Results showed that the heat transfer difference with different flow directions relates to the system parameters. Deteriorated heat transfer is attributed to buoyancy and the strong thermophysical variations of supercritical water.更多还原