29
Views
6
CrossRef citations to date
0
Altmetric
Technical Paper

An Improved Theoretical Critical Heat Flux Model for Low-Quality Flow

, &
Pages 294-306 | Published online: 13 May 2017

References

  • C.H. LEE and I. A. MUDAWWAR, “A Mechanistic Critical Heat Flux Model for Subcooled Flow Boiling Based on Local Bulk Flow Conditions,” Int. J. Multiphase Flow, 14, 711 (1988).
  • R. MESLER, “A Mechanism Supported by Extensive Experimental Evidence to Explain High Heat Flux Observed During Nucleate Boiling,” AIChE J., 22, 246 (1976).
  • A. M. BHAT, R. PRAKASH, and J. S. SAINI, “Heat Transfer in Nucleate Pool Boiling at High Heat Flux,” Int. J. Heat Mass Transfer, 26, 833 (1983).
  • R. HINO and T. UEDA, “Studies on Heat Transfer and Flow Characteristics in Subcooled Flow Boiling – Part 2, Flow Characteristics,” Int. J. Multiphase Flow, 11, 283 (1986).
  • S. B. V. MOLEN and F. W. B. M. GALJEE, “The Boiling Mechanism During Burnout Phenomena in Subcooled Two Phase Water Flow,” Proc. 6th Int. Heat Transfer Conf., Toronto, Canada, August 7-11, 1978, Vol. 1, p. 381 (1978).
  • A. SERIZAWA, “Theoretical Prediction of Maximum Heat Flux in Power Transients,” Int. J. Heat Mass Transfer, 26, 921 (1983).
  • J. WEISMAN and B. S. PEI, “Prediction of Critical Heat Flux in Flow Boiling at Low Qualities,” Int. J. Heat Mass Transfer, 26, 1463 (1983).
  • W. S. LIN, B. S. PEI, C. H. LEE, and L. A. MUDAWWAR, “A Theoretical Critical Heat Flux Model for Rod Bundles Under PWR Conditions,” Nucl. Technol., 85, 213 (1989).
  • B. K. C. CHAN and R. G. H. PRINCE, “Viscous Drag on a Gas Bubble Rise in a Liquid,” AIChE J., 11, 188 (1965).
  • R. COLE and W. R. ROHSENOW, “Correlation of Bubble Departure Diameters for Boiling of Saturated Liquids,” Chem. Eng. Progr. Symp., 92, 211 (1969).
  • V. S. ARPACI and P. S. LARSEN, Convection Heat Transfer, Prentice-Hall, Inc., Edgewood Cliffs, New Jersey (1984).
  • A. E. DUKLER, M. WICKS III, and R. G. CLEVELAND, “Frictional Pressure Drop in Two-Phase Flow: B. An Approach Through Similarity Analysis,” AIChE J., 10, 44 (1964).
  • S. LEVY, “Forced Convection Subcooled Boiling Prediction of Vapor Volumetric Fraction,” Int. J. Heat Mass Transfer, 10, 951 (1967).
  • R. C. MARTINELLI, “Heat Transfer to Molten Metals,” Trans. ASME, 69, 947 (1947).
  • M. M. SHAH, “A General Correlation for Heat Transfer During Subcooled Boiling in Pipes and Annuli,” ASHRAE Trans., 83, 202 (1977).
  • S. W. BEYERLEIN, R. K. COSSMANN, and H. J. RICHTER, “Prediction of Bubble Concentration Profiles in Vertical Turbulent Two-Phase Flow,” Int. J. Multiphase Flow, 11, 629 (1985).
  • D. BUTTERWORTH and G. F. HEWITT, Two-Phase Flow and Heat Transfer, Oxford University Press, Oxford (1980).
  • W. J. GREEN, “A Flow Boiling Critical Heat Flux Correlation for Water and Freon-12 at Low Mass Fluxes,” Nucl. Eng. Des., 72, 381 (1982).
  • R. A. DEBORTOLI, S. J. GREEN, B. W. LETOURNEAU, M. TROY, and A. WEISS, “Forced Convection Heat Transfer Burnout Studies for Water in Rectangular Channels and Round Tubes at Pressures Above 500 psia,” WAPD-188, Westinghouse Electric Corporation (1958).
  • K. M. BECKER, P. PERSSON, L. NILSSON, and O. ERIKSSON, “Measurements of Burnout Conditions for Flow of Boiling Water in Vertical Round Ducts,” Parts 1 and 2, AE-87(1962) and AE-114(1963), Aktiebolaget Atomenergie.
  • D. H. LEE and J. D. OBERTELLI, “An Experimental Investigation of Forced Convection Burnout in High Pressure Water, Part 1. Round Tubes with Uniform Flux Distribution,” AEEW-R213, United Kingdom Atomic Energy Authority (1963).
  • B. THOMPSON and R. V. MACBETH, “Boiling Water Heat Transfer Burnout in Uniformly Heated Round Tubes-A Compilation of World Data with Accurate Correlations,” AEEW-R356, United Kingdom Atomic Energy Authority (1964).
  • D. H. LEE and D. J. MORRIS, “Burnout and Two-Phase Pressure Drop for Water at 1000 psia in Round Tubes with Uniform and Non-Uniform Heat Flux Distribution,” AEEW-355, United Kingdom Atomic Energy Authority (1964).
  • R. R. HOOD and L. ISAKOFF, “Heavy Water Moderated Power Reactors Progress Report for June 1962,” D.P. 755, U.S. Atomic Energy Commission (1962).
  • R. J. WEATHERHEAD, “Nucleate Boiling Characteristics and the Critical Heat Flux Occurrence in Subcooled Axial Flow Water Systems,” ANL-6675, Argonne National Laboratory (1963).
  • B. MATZNER, “Basic Experimental Studies of Boiling Fluid Flow and Heat Transfer at Elevated Pressures,” TID-18978, U.S. Atomic Energy Commission (1962).
  • D. H. LEE and J. D. OBERTELLI, “An Experimental Investigation of Forced Convection Boiling in High Pressure Water,” Part III, AEEW-R355, United Kingdom Atomic Energy Authority (1965).
  • V. Y. DOROSHCHUK and F. P. FRIED, “Critical Heat Flux for Water Flowing in Tubes,” Problems of Heat Transfer and Hydraulics of Two-Phase Media, S. S. KUTADELADZE, Ed., Pergamon Press, Oxford (1969).
  • L. S. TONG, “Prediction of Departure from Nucleate Boiling for an Axially Non-Uniform Heat Flux Distribution,” J. Nucl. Energy, 21, 241 (1967).
  • R. W. BOWRING, “A Simple but Accurate Round Tube Uniform Heat Flux, Dryout Correlation over the Pressure Range 0.7-17 MN/M2 (100-2500 psia),” AEEW-R789, United Kingdom Atomic Energy Authority (1972).
  • Y. KATTO and H. OHNO, “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 (1984).
  • R. BOWRING and P. MORENO, “COBRA IIIC/MIT Computer Code Manual,” Massachusetts Institute of Technology, Department of Nuclear Engineering (Mar. 1976).
  • C. F. FIGHETTI and D. G. REDDY, “Parametric Study of CHF Data, Vol. 3: Critical Heat Flux Data,” NP-2609, Electric Power Research Institute (1983).
  • D. G. REDDY and C. F. FIGHETTI, “Parametric Study of CHF Data, Vol. 2: A Generalized Subchannel CHF Correlation for PWR and BWR Fuel Assemblies,” NP-2609, Electric Power Research Institute (1983).
  • “Tabular Data for Calculating Burnout When Boiling Water in Uniformly Heated Round Tubes,” Thermal Eng., 23, 77 (1977).

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.