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R134a卧式螺旋管内流动沸腾CHF特性研究 被引量:7

Study on Dry-out CHF Characteristics of R134a Flow Boiling in Horizontal Helically-coiled Tubes
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摘要 为探索低潜热工质在卧式螺旋管内流动沸腾的临界热流密度(CHF)特性,采取大电流直接对实验段通电,利用不锈钢电阻加热的方式,在出口压力p=0.40~1.05 MPa,质量流速G=51~257 kg/m2s,入口热平衡干度Xi=-0.18~0.43的条件下开展了R134a在卧式螺旋管内流动沸腾的CHF特性研究。实验用螺旋管内径7.6 mm,螺旋径300 mm,节距40 mm,有效加热长度7.07 m。重点分析了实验段壁温沿管长和管截面周向的变化规律,以及压力、流量、干度等参数对CHF值的影响,并把实验数据与Bowring和Shah关联式的计算值进行了验证比较,结果发现这2种关联式在该实验条件下均不适用。 An experimental study of critical heat flux(CHF) using R134a as work fluid in horizontal helically-coiled tubes was performed to investigate the CHF characteristics.The stainless steel test section was directly heated uniformly by high-power source.The experiment parameters were: a.outlet pressures of 0.40~1.05 MPa,b.mass fluxes of 51~257 kg/m2s,and c.inlet qualities of-0.18~0.43.And the structure parameters of the test section were: inner diameter of 7.6mm,helix diameter of 300 mm,helix pitch of 40 mm and heated length of 7.07 m.The characteristics of wall temperature and the effects of pressure,mass flux and vapor qualities on CHF were investigated and discussed in this paper.Experiment data were compared with the calculated results by Bowring correlation and Shah correlation,respectively.It was found that the two correlations were not suitable for predicting CHF under the present experiment conditions.
出处 《核动力工程》 EI CAS CSCD 北大核心 2010年第5期76-80,共5页 Nuclear Power Engineering
基金 国家自然科学基金资助项目(50776055) 山东自然科学基金资助项目(Y2007F10)
关键词 临界热流密度(CHF) 卧式螺旋管 沸腾传热 R134A CHF Horizontal helically-coiled tubes Boiling heat transfer R134a
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  • 1Bowring R W. A Simple But Accurate Round Tube Uniform Heat Flux, Dry-out Correlation Over the Pressure Range, 0.7-12 MN/mZ(100-2500 psia)[R]. 1972, AEEW-R789.
  • 2Katto Y, Ohno H. An Improved Version of the Generalized Correlation of Critical Heat Flux for the Forced Convective Boiling in Uniformly Heated Vertical Tubes[J]. Int. J. Heat Mass Transfer, 1984, 27: 1641-1648.
  • 3Shah M M. Improved General Correlation for Critical Heat Flux During Up Flow in Uniformly Heated Vertical Tubes[J]. Int J Heat Fluid Flow, 1987, 08 : 325-335.
  • 4Groeneveld D C, Shah J Q, Vasic A Z, et al. The 2006 CHF Look-up Table[J]. Nuclear Engineering and Design, 2007,237: 1909-1922.
  • 5郭烈锦,陈学俊,张鸣远.卧式螺旋管内汽水两相流沸腾传热特性研究[J].西安交通大学学报,1994,28(5):120-124. 被引量:9
  • 6Cheng X, Erbacher F J, Muller U. Critical Heat Flux in Uniformly Heated Vertical Tubes[J]. Int. J. Heat Mass Transfer, 1997, 40: 2929-2939.
  • 7马卫民,张鸣远,陈学俊,孙科霞.卧式螺旋管内的沸腾临界后传热[J].工程热物理学报,1998,19(5):633-636. 被引量:3
  • 8毕勤成,陈听宽,田永生,陈学俊.螺旋管内高压汽水两相流传热恶化规律的研究[J].西安交通大学学报,1996,30(5):30-35. 被引量:10
  • 9冯自平,郭烈锦,陈学俊,孙巨峰.卧式螺旋管内烧干特性[J].化工学报,1997,48(2):180-185. 被引量:3
  • 10Grocheveld D C, Delorme G G J. Prediction of Thermal Non-Equilibrium in the Post Dry-out Regime[J]. Nuclear Engineering and Design, 1976, 36: 17-26.

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