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Boiling, flow critical heat flux

C. Pan and T. N. Lin, Marangoni Flow Effect in Nucleate Boiling Near Critical Heat Flux, in Int. Comm. Heat Mass Transfer (16) 475-486,1989. [Pg.1149]

H. Zhang, 1. Mudawar, M. M. Hasan, Photographic study of high-flux subcooled flow boiling and critical heat flux, Int. Com. Heat Mass Transfer, 2008, 35, 793-799. [Pg.93]

The code determines the onset of nucleate boiling and critical heat flux corresponding to flow instability in each individual channel and burnout of fuel plate. Heat flux for the onset of nucleate boiling and critical heat flux are calculated using actual power distribution, coolant velocity, local pressure and saturation temperature at each individtial code. Margins to nucleate boiling, flow instability and burnout are also calculated. [Pg.8]

The static limit is the non-linear limit of conditionally instability, where departure from nucleate boiling or critical heat flux will occur at low and high qualities, respectively. There are sufficient data in the literature which show that instability in multiple channels precedes the limit of classic single channel (mass-flow controlled) dryout (Mathison, 1967) (D Arcy, 1967). This differs from the result for the zero frequency condition, which can only be written as a cubic in, (Ns / Np), and does not give a critical subcooling number. The condition of static instability in parallel channels is the Ledinegg condition (Saha et al, 1976) (Duffey and Hughes, 1991),... [Pg.54]

T2. Tippets, F. E., Analysis of the critical heat flux condition in high pressure boiling water flow, ASME Paper No. 62-WA-161 (1962). [Pg.293]

The subject of Chap. 6 is boiling in micro-channels. Several aspects of boiling are also considered for conventional size channels and comparison with micro-channels was carried out. Significant differences of ONB in micro-channels have been discussed compared to conventional channels. Effect of dissolved gases on boiling in water and surfactant solution was revealed. Attention was paid on pressure drop and heat transfer, critical heat flux and instabilities during flow boiling in microchannels. [Pg.259]

Available data sets for flow boiling critical heat flux (CHF) of water in small-diameter tubes are shown in Table 6.9. There are 13 collected data sets in all. Only taking data for tube diameters less than 6.22 mm, and then eliminating duplicate data and those not meeting the heat balance calculation, the collected database included a total of 3,837 data points (2,539 points for saturated CHF, and 1,298 points for subcooled CHF), covering a wide range of parameters, such as outlet pressures from 0.101 to 19.0 MPa, mass fluxes from 5.33 to 1.34 x lO kg/m s, critical heat fluxes from 0.094 to 276 MW/m, hydraulic diameters of channels from 0.330 to 6.22 mm, length-to-diameter ratios from 1.00 to 975, inlet qualities from —2.35 to 0, and outlet thermal equilibrium qualities from -1.75 to 1.00. [Pg.305]

Inasaka F (1993) Critical heat flux of subcooled flow boiling in water under uniform heating conditions. Papers Ship Res Inst 30(4) 1-69... [Pg.321]

Kandlikar SG (2006) Nucleation characteristics and stability considerations during flow boiling in micro-channels. Exp. Thermal and Fluid Science 30 441 47 Katto Y, Ohno H (1984) An improved version of the generalized correlation of critical heat flux for the forced convective boiling in uniformly heated vertical tubes. Int J Heat Mass Transfer 27 1641-1648... [Pg.321]

Kureta M (1997) Critical heat flux for flow boiling of water in small diameter tubes under atmospheric pressure. Dissertation, Kyoto University (in Japanese)... [Pg.322]

Mudawar I, Bowers MB (1999) Ultra-high critical heat flux (CHF) for subcooled water flow boiling. I CHF data and parametric effects for small diameter tubes. Int J Heat Mass Transfer 42 1405-1428... [Pg.323]

Qu W, Mudawar I (2002) Prediction and measurement of incipient boiling heat flux in micro-channel heat sinks. Int J Heat Mass Transfer 45 3933-3945 Qu W, Mudawar I (2004) Measurement and correlation of critical heat flux in two-phase micro-channel heat sinks. Int J Heat Mass Transfer 47 2045-2059 Quiben JM, Thome JR (2007a) Flow pattern based two-phase pressure drop model for horizontal tubes. Part I. Diabatic and adiabatic experimental study. Int. J. Heat and Fluid Flow. 28(5) 1049-1059... [Pg.323]

Yen T-H, Kasagi N, Suzuki Y (2003) Forced convective boiling heat transfer in micro-tubes at low mass and heat fluxes. Int J Multiphase Flow 29 1771-1792 Yu W, France DM, Wambsganss MW, Hull JR (2002) Two-phase pressure drop, boiling heat transfer, and critical heat flux to water in a small-diameter horizontal tube. Int J Multiphase Flow 28 927-941... [Pg.325]

Bergles, A. E., J. P. Ross, and J. G. Bourne, 1968, Investigation of Boiling Flow Regimes and Critical Heat Flux, NYO-3304-13, Dynatech Corp., Cambridge, MA. (3)... [Pg.523]

Chang, S. H., and K. W. Lee, 1988, A Derivation of Critical Heat Flux Model in Flow Boiling at Low Qualities Based on Mass, Energy, and Momentum Balance, Korea Advanced Institute of Science and Technology, Taejeon, Korea. [Pg.526]

Dean, R A., R. S. Dougall, and L. S. Tong, 1971, Effect of Vapor Injection on Critical Heat Flux in a Subcooled R-l 13 (Freon) Flow, Proc. Int. Symp. on Two-Phase Flow Systems, Haifa, Israel. (6) Deane, C. W., and W. M. Rohsenow, 1969, Mechanism and Behavior of Nucleate Boiling Heat Transfer to the Alkali Liquid Metals, USAEC Rep. DSR 76303-65, Massachusetts Institute of Technology, Cambridge, MA Also in 1970, Liquid Metal Heat Transfer and Fluid Dynamics J. C. Chen and A. A. Bishop, Eds., ASME Winter Annual Meeting, New York. (4)... [Pg.529]

Pei, B. S., 1981, Prediction of Critical Heat Flux in Flow Boiling at Low Qualities, Ph.D. thesis, University of Cincinnati, Cincinnati, OH. (5)... [Pg.548]

Tippets, F. E., 1962, Critical Heat Fluxes and Flow Patterns in High Pressure Boiling Water Flows, ASME Paper 62-WA-162, Winter Annual Meeting, ASME, New York. (5)... [Pg.555]

Weisman, J., 1992, The Current Status of Theoretically Based Approaches to the Prediction of the Critical Heat Flux in Flow Boiling, Nuclear Techno . 99.1-21. (1)... [Pg.558]


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