期刊文献+

亚临界及近临界压力区倾斜上升管传热特性研究 被引量:6

Investigation on the Heat Transfer Characteristics of the Steam-Water Two-Phase Flow in the Inclined Upward Smooth Tube in Sub-Critical and Near Critical Pressure Regions
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摘要 在亚临界及近临界压力下,对倾角α=20的Φ323mm不锈钢倾斜上升光管内汽水两相流体的传热特性进行了试验研究。试验参数范围:p=13~21.5MPa;质量流速G=600~1200kg/(m2·s);内壁热负荷q=200~600kW/m2。试验结果表明:倾斜管壁温及内壁热负荷沿管壁周向不均匀分布;提高质量流速可以减弱甚至消除这种不均匀性;在不同工况下,压力对传热的影响规律是不同的。还提出了倾斜管最小传热系数的计算关联式。 Under sub-critical and near critical pressures, the heat transfer characteristics of the steam-water two-phase flow in the inclined upward smooth tube with the diameter of φ32×3 mm and the inclined angle of α=20 were investigated experimentally. The tests were performed at p=13-21.5 MPa, G=600-1200 kg/(m2&middots) and q=200-600 kW/m2. The results show that the wall temperatures and the internal wall heat fluxes non-uniformly distribute along the circumference of the inclined upward tube, and that the non-uniform distribution can be decreased and even eliminated by increasing the mass velocity. At different working conditions, the influence laws of the pressures on the heat transfer are different. The correlation of the minimum heat transfer coefficient of the inclined tube has been provided and can be used as a reference in the design of engineering practices.
出处 《核动力工程》 EI CAS CSCD 北大核心 2004年第6期494-498,513,共6页 Nuclear Power Engineering
基金 国家自然科学基金重大资助项目(No. 50323001)
关键词 传热 亚临界 近临界 倾斜管 Tubes (components) Two phase flow
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  • 1陈听宽,西安交通大学学报,1990年,增刊,43页
  • 2陶文铨,数值传热学,1989年
  • 3黄承懋,锅炉水动力学及锅内传热,1982年
  • 4陈学俊,大型电站锅炉锅内传热和水动力特性,1978年
  • 5林宗虎,锅内过程,1990年

共引文献19

同被引文献37

  • 1杨传勇,徐进良,王晓东,张伟.超临界参数CO2在倾斜管内对流换热数值模拟[J].热力发电,2013,42(1):26-35. 被引量:9
  • 2徐峰,郭烈锦,白博峰.管内超临界压力水的混和对流换热[J].工程热物理学报,2005,26(1):76-79. 被引量:11
  • 3王为术,陈听宽,罗毓珊,李会雄,顾红芳,尹飞,朱晓静.超临界压力区倾斜上升光管壁温分布与传热特性的试验研究[J].动力工程,2005,25(5):623-627. 被引量:14
  • 4Tian Y S,Chen T K,Luo Y S,et al.Heat transfer characteristics of supercritical water flowing in inclined tubes[J].Journal of Chemical Industry and Engineering,1993,44(1):34-40.
  • 5Yang Jue,Oka Yoshiaki,Ishiwatari Yuki,et al.Numerical investigation of heat transfer in upward flows of supercritical water in circular tubes and tight fuel rod bundles[J].Nucl Eng Des,2007,237(4):420 -430.
  • 6Yamagata K,Nishikawa K,Hasegawa S,et al.Forced convection heat transfer to supercritical water flowing in tubes[J].Int J Heat Mass Transfer,1972,15 (12):2575-2593.
  • 7Cheng X,Kuang B.Numerical analysis of heat transfer in supercritical water cooled flow channels[J].Nucl Eng Des,2007,237 (3):240-252.
  • 8Gessner F B.The origin of secondary flow in turbulent flow along a corner[J].J Fluid Mech.1973,58(1):1 -25.
  • 9Vonka V.Measurement of secondary flow vortices in a rod bundle[J].Nucl Eng Des,1988,106(2):191 -207.
  • 10Flunt Inc[CP].Fluent,Lebanon,NH.2008.

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