期刊文献+

小管径超临界流体传热恶化特性研究 被引量:5

Investigation on Heat Transfer Deterioration Characteristics of Supercritical Fluid in Small Diameter Tube
原文传递
导出
摘要 根据IAPWS公布的IF97临界区比容反推方程重新拟合了超临界区域水的拟临界温度计算公式,进一步提高临界区的水和蒸汽物性计算精度。对水平小管径内超临界水的传热恶化特性进行了实验探究,实验结果表明:当平均流体温度小于拟临界温度时,换热系数出现峰值。平均流体与近壁流体的黏度比达到最大值,换热系数达到峰值;密度比达到最大值,传热恶化已经发生,管内进入拟汽相换热区或发生层流化现象。随着热流密度的增大,换热系数峰值越低;换热系数峰值和传热发生恶化的位置都向低焓值区偏移。 Based on backward equations for IF97-Region 3 published by IAPWS, a fitting formula is proposed to calculate pseudo-critical temperature of supercritical water and steam and the calculation accuracy of the physical properties in Region 3 is approved. A experiment was carried out to analyze the heat transfer deterioration characteristic of supercritical water in small horizontal diameter tube.It results that a heat transfer coefficient peak occurs when the average fluid temperature is lower than the pseudo-critical temperature. When the viscosity ratio of the average fluid to the near-wall fluid reaches the maximum, the heat transfer coefficient peak occurs. When the density ratio reaches the maximum, the heat transfer deterioration characteristic occurs and pseudo-steam heat transfer mechanism or laminarization phenomenon happens at the same time. The higher heat load is, the lower heat transfer coefficient peak is and the heat transfer coefficient peak or deterioration occurs at the lower enthalpy region.
作者 范辰浩 王海军 宋子琛 郑宇龙 脱晓冰 FAN Chen-Hao1,2, ANG Hai-Jun1 ,SONG Zi-Chen1, ZHENG Yu-Long1 ,TUO Xiao-Bing1(1. State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an 710049, China; 2. Shanghai Minghua Electric Power Technology Co., Ltd., Shanghai 200090, Chin)
出处 《工程热物理学报》 EI CAS CSCD 北大核心 2018年第9期2032-2039,共8页 Journal of Engineering Thermophysics
基金 国家科学基金资助项目(No.11675128)
关键词 超临界水 拟临界温度 小管径 传热恶化 supercritical water pseudo-critical temperature small horizontal diameter tube heattransfer deterioration
  • 相关文献

参考文献3

二级参考文献14

  • 1Abadzic E, Goldstein, R J. Film Boiling and Free Convection Heat Transfer to Carbon Dioxide near the Critical State[J]. Int. J. Heat Mass Transfer, 1970, 13(7), 1163-1175.
  • 2胡志宏.超临界和近临界压力区垂直上升及倾斜管传热特性研究[D].西安:西安交通大学博士学位论文,2002.
  • 3Carajieseov P, Todreas N E. Experimental and Analytical Study of Axial Turbulent Flows in an Interior Subchannel of a Bare Rod Bundle [J]. J Heat Trans., 1976, 98(2): 262-268.
  • 4Kim, S H, Kim, Y I, Bae Y Y, et al. Numerical Simulation of the Vertical Upward Flow of Water in a Heated Tube at Supercritical Pressure[C]. In: Proe. of ICAPP04, Pittsburgh, PA, USA, June 13-17, 2004.
  • 5Roelof F, Komen Ed. CFD Analysis of Heat Transfer to supercritical Water Flowing Vertically Upward in a Tube[C]. Jahrestagung Kerntechnik, Murnberg, Germany, May 10-12, 2005.
  • 6Yamagata K, Yoshida S, Fujii T, et al. Forced Convective Heat-Transfer to Supercritical Water Flowing in Tubes[J]. International Journal of Heat and Mass Transfer, 1972, 15: 2575-2592.
  • 7Jackson J D, Hall W B. Turbulent Forced Convection in Channels and Bundles[M]. New York: Hemisphere, vol.2, 1979, 563-564.
  • 8The International Association for the Properties of Water and Steam,Release on the IAPWS Industrial Formulation 1997 for the Thermodynamic Properties of water and Steam[M].1999.
  • 9International Formulation Committee of the 6th International Conference on the Property of Steam (1967),The 1967 IFC Formulation for Industrial Use [C].Verein Deutascher Ingenieure,Dusseldorf.
  • 10Huang C H,Mumer Heat Transf,1992年,21卷,Part A期,55页

共引文献23

同被引文献58

引证文献5

二级引证文献9

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部