节点文献
垂直上升圆管与内螺纹管汽液两相流动数值模拟
Numerical Simulation of Vapor-Liquid Two-Phase Flow in Vertical Upward Smooth Tube and Rifled Tube
【作者】 吴宛泽; 孙宝芝; 汪楷; 史建新; 赵智睿; 于祥;
【Author】 Wanze Wu;Baozhi Sun;Kai Wang;Jianxin Shi;Zhirui Zhao;Xiang Yu;College of Power and Energy Engineering, Harbin Engineering University;
【机构】 哈尔滨工程大学动力与能源工程学院;
【摘要】 为了能够高效利用能源,提高换热设备效率,通常在管内加入内螺纹强化换热。工质在流动时由于螺旋上升的内螺纹产生旋转,汽流中的水滴在离心力的作用下不断向管壁靠近,最后到达管壁补充水膜。采用数值模拟方法,对长为2.8m的垂直上升光滑管与内螺纹管内汽液两相流动传热特性进行研究。结果表明:沿圆周方向,内螺纹管流固交界壁面温度分布不均匀,其分布依据近壁面处体积含汽率的分布,迎风侧壁温较高而背风侧较低,肋顶部壁温高于肋根部;流道中心流体流速最高,向壁面方向逐渐降低;而在轴向方向,相同位置处光管体积与质量含汽率略高于螺纹管。
【Abstract】 In order to improve the efficiency of the heat exchanger, internal threads are usually added to the tube to enhance heat transfer. When the working fluid flows in the rifled tube, it rotates under the action of the spiral rising inner threads. Under the action of centrifugal force, the water droplets in the steam flow keep approaching the tube wall and finally reach the tube wall to supplement the water film. The heat transfer characteristics of vapor-liquid two-phase flow in a 2.8 m vertical upward smooth tube and rifled tube are studied by numerical simulation. The results indicate that along the circumferential direction, the wall temperature distribution of the fluid-solid interface of the rifled tube is non-uniform, which is based on the distribution of volume fraction near the interface. The wall temperature on the windward side is higherthan that on the leeward side, and on the crest is higher than that on the root. The flow velocity in the center of the channel is the highest, and gradually decreasing toward the wall. In the axial direction, the volume fraction and quality of the smooth tube is slightly higher than that of the rifled tube at the same position.
【Key words】 vapor-liquid two-phase flow; rifled tube; enhanced heat transfer; numerical simulation;
- 【会议录名称】 第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会论文集
- 【会议名称】第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会
- 【会议时间】2019-11-06
- 【会议地点】中国广东惠州
- 【分类号】TL334;TL353.13
- 【主办单位】中国核学会核能动力分会反应堆热工流体专业委员会、中核核反应堆热工水力技术重点实验室、核反应堆热工流体青年工作委员会