螺旋管内流动和传热特性实验研究及经验公式评价  

Experimental Study of Flow and Heat Transfer Characteristics in Helically-coiled Tube and Evaluation of Empirical Formulas

作　　者：程林海 谷海峰 汤维 陈斌[1] 石依妍 CHENG Linhai;GU Haifeng;TANG Wei;CHEN Bin;SHI Yiyan(Fundamental Science on Nuclear Safety and Simulation Technology Laboratory,Harbin Engineering University,Harbin 150001,China;Guangdong Key Laboratory of Nuclear Power Safety,China Nuclear Power Technology Research Institute,Shenzhen 518026,China)

机构地区：[1]哈尔滨工程大学核安全与仿真技术国防重点科学实验室,黑龙江哈尔滨150001 [2]中广核研究院有限公司广东省核电安全重点实验室,广东深圳518026

出　　处：《原子能科学技术》2025年第1期100-109,共10页Atomic Energy Science and Technology

摘　　要：螺旋管内流动和传热特性对螺旋管蒸汽发生器的设计具有重要意义。本文在较宽的压力范围:0.2~14.1 MPa,对内径为8.8 mm、螺旋直径为568 mm的立式螺旋管开展了流动和传热特性实验研究。获得了不同工况下单相段和两相段的摩擦系数以及单相水区、过冷沸腾区、饱和沸腾区和干涸区的换热系数。将实验结果与近年经验关系式进行对比分析发现,Akagawa等、Hart等、Ito学者经验公式对单相水摩擦系数预测的精度较高,在±5%以内。当前经验公式对本实验两相段摩擦系数与不同区域的换热系数的预测,相对平均偏差在10%~20%左右。分析结果可为螺旋管蒸汽发生器的设计提供参考。The flow and heat transfer characteristics of helically-coiled tubes are crucial for the design of spiral tube steam generators.In this paper,the flow and heat transfer characteristics of a vertical helically-coiled tube with an inner diameter of 8.8 mm and a helical diameter of 568 mm were experimentally investigated in a wide pressure range:0.2-14.1 MPa.The mass flow rate is 49-1902 kg/(m2·s).The heat flux of the experimental section is 14.5-580 kW/m2.In this experiment,the flow rate of the main loop is adjusted by the valve opening,the system pressure is adjusted by the highpressure nitrogen cylinder,the metering pump and the pressure relief valve,the inlet fluid parameters of the experimental section is adjusted by the input power of the preheater and the direct-current(DC)voltage loaded in the preheating section,and the heating heat flux is adjusted by the DC voltage loaded in the experimental section.Finally,the friction coefficients of single-phase and two-phase,as well as heat transfer coefficients of single-phase,subcooled boiling,saturated boiling and dry out under different working conditions were obtained.Comparison and analysis of the experimental results with the empirical relational formulas of recent years revealed that the empirical formulas of Akagawa's,Hart's,and Ito's predicted the single-phase friction coefficients with high accuracy within±5%.The secondary flow increases the critical Reynolds number,which is about 10000 in this experiment.In the range of straight tube laminar flow(Re<2300),the influence of secondary flow is greater.When the Reynolds number increases,the energy dissipation of secondary flow to the turbulent region is much smaller than that of laminar flow region.The current empirical formula has at least 10%-20%deviation in predicting the two-phase friction coefficient and the heat transfer coefficient in different regions.The relative average deviation between the friction coefficient of the two phases and the calculation formulas of Chen,Guo,Ferraris and M-N is about±20%

关 键 词：螺旋管 两相流 摩擦阻力 传热系数 

分 类 号：TL123[核科学技术—核能科学]