Two-Phase Flow and Heat Transfer

Preview

Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.

References

  1. Berenson, P. J., “Experiments of Pool Boiling Heat Transfer,” Int. Journal of Heat Mass Transfer, 5, 1962.Google Scholar
  2. Bernath, L., Transactions of A.I.Ch.E., 1955.Google Scholar
  3. Biasi, L., et. al., “Studies on burnout, Part 3. Enrgy Nucl. 14:530, 1967.Google Scholar
  4. Bjornard, T. A. and P. Griffith, “PWR Blowdown Heat Transfer,” Symposium on Thermal and Hydraulic Aspects of Nuclear Reactor Safety (Vol. 1). New York, ASME 1977.Google Scholar
  5. Bowring, R. W., “Simple but Accurate Round Tube, Uniform Heat Flux Dryout Correlation over the Pressure Range 0.7 to 17 MPa,” AEEW-R-789, U.K. Atomic Energy Authority, 1972.Google Scholar
  6. Bromley, L. A., “Heat Transfer in Stable Film Boiling,” Chem. Eng. Prog., 46, 221, 1950.Google Scholar
  7. Chen, John C., “A Correlation for Boiling Heat Transfer to Saturated Fluids in Convection Fow,” ASME paper 63-HT-34, 1963.Google Scholar
  8. Cheng, S. C, W. Ng, and K. T. Heng, “Measurements of Boiling Curves of Subcooled Water Under Forced Convection Conditions,“ Int. Journal of Heat Mass Transfer 21:1385, 1978.CrossRefGoogle Scholar
  9. Cichitti, A., et. al., “Two-Phase Cooling Experiments — Pressure Drop, Heat Transfer, and Burnout Measurements,” Energia Nucl. 7:407, 1960.Google Scholar
  10. Collier, John G. and Thome, John R., “Convective Boiling and Condensation,” Third Edition, Oxford University Press, 1996.Google Scholar
  11. Delhaye, J. M., M. Giot, and M. L. Riethmuller, “Thermohydraulics of Two-Phase Systems for Industrial Design and Nuclear Engineering,” McGraw Hill/Hemisphere, 1981.Google Scholar
  12. Dergarabedian, P., “The Rate of Growth of Bubbles in Superheated Liquid,” Journal of Appl. Mech. Trans. ASME, vol. 75, 1953.Google Scholar
  13. Dhir, V. K. and J. H. Lienhard, “Laminar Film Condensation on Planes and Axisymmetric Bodies in Non-uniform Gravity,” Journal of Heat Transfer, 93, 97–100, 1971Google Scholar
  14. Duckler, A. E., et. al., “Pressure Drop and Hold-up in Two-Phase Flow: Part A — A Comparison of Existing Correlations. Part B — An Approach Through Similarity Analysis,” AIChE Journal, 10:38, 1964.CrossRefGoogle Scholar
  15. Fauske, H. F., “The Discharge of Saturated Water Through Tubes,” Chem. Eng. Sym. Series 61:210, 1965.Google Scholar
  16. Friedel, L., “Improved Friction Pressure Drop Correlations for Horizontal and Vertical Two-Phase Pipe Flow, European Two-Phase Flow Group Meeting, Ispra, Italy, 1979.Google Scholar
  17. Forster, H. K. and N. Zuber, “Dynamics of Vapor Bubbles and Boiling Heat Transfer,” AIChE Journal, 1(4), 531–535, 1955.CrossRefGoogle Scholar
  18. Gaspari, G. P., et. al., “A Rod-Centered Subchannel Analysis with Turbulent Mixing for Critical Heat Flux Prediction in Rod Clusters Cooled by Boiling Water,” Proceedings of 5th Int. Heat Transfer Conference, Tokyo, Japan, 3–7, September 1974, CONF-740925, 1975.Google Scholar
  19. George, Thomas L., et. al., “GOTHIC Containment Analysis Package, Technical Manual,” Numerical Applications, Inc., Richland, Washington, NAI 8907-06, Rev. 12, July 2001.Google Scholar
  20. Ginoux, J. N., “Two-Phase Flow and Heat Transfer,” McGraw Hill/Hemisphere, 1978.Google Scholar
  21. Groeneveld, D. C., “Post Dryout Heat Transfer at Reactor Operating Conditions, AECL-4513, 1973.Google Scholar
  22. Henry, R. E., “The Two-Phase Critical Discharge of Initially Saturated or Subcooled Liquid,” Nuclear Science and Engineering, 41, 1970, pp 336.Google Scholar
  23. Henry, R.E., and H. F. Fauske, “The Two-Phase Critical Flow of One-Component Mixtures in Nozzles, Orifices, and Short Tubes,” Transactions of ASME, Journal of Heat Transfer 93, 179–187, May 1971.Google Scholar
  24. Hewitt, G. F. and D. N. Roberts, “Studies of Two-Phase Flow Patterns by Simultaneous X-Ray and Flash Photography,” AERE-M2159, 1969.Google Scholar
  25. Hsu, Yih-Yun, “On the Size Range of Active Nucleation Cavities in Nucleate Boiling,” Journal of Heat Transfer, 84C(3), 207–216, 1962.Google Scholar
  26. Hsu, Yih-Yun and Robert W. Graham, “Transport Processes in Boiling and Two-Phase Systems, McGraw Hill Publishing Company, 1976.Google Scholar
  27. Janssen, E. and Levy, S., “General Electric Company Report APED-3892, 1962.Google Scholar
  28. Jens, W. H. and P. A. Lottes, “Analysis of Heat Transfer, Burnout, Pressure Drop, and Density Data for High Pressure Water,” ANL-4627, 1951.Google Scholar
  29. Kandlikar, S. G., “A General Correlation for Saturated Two-Phase Flow Boiling Heat Transfer Inside Horizontal and Vertical Tubes,” J. Heat Transfer, 112(1):219–228, 1990.Google Scholar
  30. Katto, Y. and Haramura, Y., “Critical Heat Flux on a uniformly heated horizontal cylinder in an upward cross flow of saturated liquid,” Int. Journal Heat Mass Transfer, 26, pp 1199–1205, 1983.Google Scholar
  31. Mandhane, J. M. et. al., “A Flow Pattern Map for Gas-Liquid Flow in Horizontal Pipes,” International Journal of Multiphase flow, 1:537, 1974.CrossRefGoogle Scholar
  32. —, RELAP-5, MOD1 Code Technical ManualCrossRefGoogle Scholar
  33. Labuntsov, D. A., “Heat Transfer in Film Condensation of Pure Steam on Vertical Surfaces and Horizontal Tubes,” Teploenergetika, 4, 72, 1957.Google Scholar
  34. McAdams, W. H., et. al., “Vaporization Inside Horizontal Tubes. II. Benzene-Oil Mixture, Trans. ASME 64:193, 1942.Google Scholar
  35. MacBeth, R. V., “Burn-out Analysis, Part 4. Application of a local condition hypothesis to world data for uniformly heated round tubes and rectangular channels,” AEEW-R 267, 1963.Google Scholar
  36. McDonough, J.B., W. Milich, W., and E.C. King, “An Experimental Study of Partial Film Boiling Region with Water at Elevated Pressures in a Round Vertical Tube. Chem. Eng. Prog. Sym. Series 57:197, 1961.Google Scholar
  37. Martinelli, R. C. and D. B. Nelson, “Prediction of Pressure Drop During Forced Circulation Boiling of Water,” Trans. ASME 70:695, 1948.Google Scholar
  38. Moody, F. J., “Maximum Flow Rate of a Single-Component, Two-Phase Mixture,” Journal of Heat Transfer, Vol. 87, 134–142, February 1965.Google Scholar
  39. Moore, K. V. and W. H. Rettig, “RELAP4 — A Computer Program for Transient Thermal-Hydraulic Analysis,” ANCR-1127, Idaho National Laboratory, Idaho Falls, Idaho, 1975.Google Scholar
  40. Myer, John E., “Conservation Laws in One-Dimensional Hydrodynamics,” WAPD-BT-20, Sept. 1960.Google Scholar
  41. Nahavandi, Amir N and Michael P. Rashevsky, “A Digital Computer Program for Critical Flow Discharge of Two-Phase Steam-Water Mixtures,” CVNA-128, February 1962.Google Scholar
  42. Nukiyama, S., “The Maximum and Minimum Values of Heat Transmitted from Metal to Boiling Water Under Atmospheric Pressure,” Int. J. Heat Mass Transfer, 9, 1966.Google Scholar
  43. Pei, B. S. et. al., “Evaluations and Modifications of the EPRI-1 Correlation of PWR Critical Heat FluxGoogle Scholar
  44. Predictions Under Normal & Abnormal Fuel Conditions,” Nuclear Tech., Vol. 75, NO. 2, November 1986.Google Scholar
  45. Reddy, D. G., R. S. Sreepada, and Amir. N. Nahavandi, “Two-Phase Friction Multiplier Correlation for High — Pressure Steam Water Flow,” EPRI, NP-2522, July 1982.Google Scholar
  46. Scriven, L. E., “On the Dynamics of Bubbles in Superheated Water,” Chem. Eng. Sci., vol. 10, 1959.Google Scholar
  47. Stephen, Karl, “Heat Transfer in Condensation and Boiling,” Springer-Verlag, 1992.Google Scholar
  48. Tong, L. S., “Boiling Crisis and Critical Heat Flux, TID-25887 NTIS, 1972.Google Scholar
  49. Thom, J. R. S., et. al., “Boiling in Subcooled Water During Flow in Tubes and Annuli,” Proc. Int. Mech. Eng. 180:226, 1966.Google Scholar
  50. Thom, J. R. S., “Prediction of Pressure Drop During Forced Circulation Boiling of Water,” Int. Journal of Heat Mass Transfer 7:709, 1964.CrossRefGoogle Scholar
  51. Wallis, G. B., “One Dimensional Two-Phase Flow,” McGraw Hill, New York. 1969.Google Scholar
  52. Whalley, P. B., “Boiling, Condensation, and Gas-Liquid Flow,” Oxford University Press, 1990.Google Scholar
  53. Winterton, R. H. S., “Thermal Design of Nuclear Reactors,” Pergamon Press, 1981.Google Scholar
  54. Zivi, S. M., “Estimation of Steady-State Steam Void Fraction By Means of The Principle of Minimum Entropy Production,” Trans. ASME (J. Heat Transfer), 86, 247–52.Google Scholar
  55. Zuber, N, and J. A. Findlay, “Average Volumetric Concentration in Two-Phase Flow Systems,” J. Heat Transfer, 87:453, 1965.Google Scholar
  56. Zuber, N., “On the Stability of Boiling Heat Transfer,” Trans. ASME, 80, 1958.Google Scholar
  57. Zuber, N. and M. Tribus, “Further Remarks on the Stability of Boiling Heat Transfer,” UCLA, Report No. 58-5, January 1958.Google Scholar

Copyright information

© Springer-Verlag Berlin Heidelberg 2005

Personalised recommendations