Evaluation of subcooled critical heat flux correlations using the PU-BTPFL CHF database for vertical upflow of water in a uniformly heated round tube

Nuclear Technology

Volumn 117, Issue 2, 1997, Pages 234-246

  Hall, David D ^a   Mudawar, Issam ^a  

^a PURDUE UNIVERSITY   (United States)

Author keywords

Correlation; Critical heat flux; Subcooled boiling

Indexed keywords

CORRELATION METHODS; DATABASE SYSTEMS; HEAT FLUX; INFORMATION USE; WATER;

VERTICAL UPFLOW;

WATER COOLED REACTORS;

EID: 0031079359     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/nt97-a35328     Document Type: Review

References (63)

1. J. LONGO, Jr., "A Statistical Investigation of Subcooled Burnout with Uniform and Locally Peaked Heat Fluxes," KAPL-1744, Knolls Atomic Power Laboratory (1957).
2. R. A. DeBORTOLI, S. J. GREEN, B. W. LeTOUR-NEAU, 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 Corp. (1958).
3. W. R. GAMBILL and N. D. GREENE, "Boiling Burnout with Water in Vortex Flow," Chem. Eng. Prog., 54, 10, 68 (1958).
4. B. A. ZENKEVICH, "The Correlation of the Experimental Data on Critical Heat Loads in Forced Flow of Water Heated Below the Boiling Temperature," At. Energ., 6, 169 (1959); see also Sov. J. At. Energy, 6, 95 (1959); J. Nucl. Energy, Part B, 1, 130 (1959).
5. B. A. ZENKEVICH, "The Correlation of the Experimental Data on Critical Heat Loads in Forced Flow of Water Heated Below the Boiling Temperature," At. Energ., 6, 169 (1959); see also Sov. J. At. Energy, 6, 95 (1959); J. Nucl. Energy, Part B, 1, 130 (1959).
6. B. A. ZENKEVICH, "The Correlation of the Experimental Data on Critical Heat Loads in Forced Flow of Water Heated Below the Boiling Temperature," At. Energ., 6, 169 (1959); see also Sov. J. At. Energy, 6, 95 (1959); J. Nucl. Energy, Part B, 1, 130 (1959).
7. L. BERNATH, "A Theory of Local-Boiling Burnout and Its Application to Existing Data," Chem. Eng. Prog. Symp. Ser. No. 30, 56, 95 (1960).
8. R. T. JACOBS and J. A. MERRILL, "The Application of Statistical Methods of Analysis for Predicting Burnout Heat Flux," Nucl. Sci. Eng., 8, 480 (1960).
9. A. P. ORNATSKII and A. M. KICHIGIN, "Critical Heat Loads in High-Pressure Boiling of Underheated Water in Small Diameter Tubes," Teploenergetika, 9, 6, 44 (1962); see also ORNL-tr-107, Oak Ridge National Laboratory.
10. W. R. GAMBILL, "Generalized Prediction of Burnout Heat Flux for Flowing, Subcooled, Wetting Liquids," Chem. Eng. Prog. Symp. Ser. No. 41, 59, 71 (1963).
11. L. S. TONG, H. B. CURRIN, and A. G. THORP II, "New Correlations Predict DNB Conditions," Nucleonics, 21, 5, 43 (1963).
12. R. H. WILSON and J. K. FERRELL, "Correlation of Critical Heat Flux for Boiling Water in Forced Circulation at Elevated Pressures," Chem. Eng. Prog. Symp. Ser. No. 47, 60, 118 (1964).
13. J. GRIFFEL and C. F. BONILLA, "Forced-Convection Boiling Burnout for Water in Uniformly Heated Tubular Test Sections," Nucl. Struct. Eng., 2, 1 (1965).
14. A. P. ORNATSKII and L. S. VINYARSKII, "Heat Transfer Crisis in a Forced Flow of Underheated Water in Small-Bore Tubes," Teptofiz. Vys. Temp., 3, 444 (1965); see also High Temp. (USSR), 3, 400 (1965).
15. A. P. ORNATSKII and L. S. VINYARSKII, "Heat Transfer Crisis in a Forced Flow of Underheated Water in Small-Bore Tubes," Teptofiz. Vys. Temp., 3, 444 (1965); see also High Temp. (USSR), 3, 400 (1965).
16. B. C. SKINNER and C. S. LOOSMORE, "Subcooled Critical Heat Flux for Water in Round Tube," MS Thesis, Massachusetts Institute of Technology (1965).
17. L. S. TONG, "Prediction of Departure from Nucleate Boiling for an Axially Non-Uniform Heat Flux Distribution," J. Nucl. Energy, 21, 241 (1967).
18. L. S. TONG, "Boundary-Layer Analysis of the Flow Boiling Crisis," Int. J. Heat Mass Transfer, 11, 1208 (1968).
19. L. F. GLUSHCHENKO, "Correlation of Experimental Data on Critical Heat Fluxes in Subcooled Boiling," Teplofiz. Teplotekh., 15, 125 (1969); see also Heat Transfer Sov. Res., 2, 1, 139 (1970); Int. Chem. Eng., 10, 219 (1970).
20. L. F. GLUSHCHENKO, "Correlation of Experimental Data on Critical Heat Fluxes in Subcooled Boiling," Teplofiz. Teplotekh., 15, 125 (1969); see also Heat Transfer Sov. Res., 2, 1, 139 (1970); Int. Chem. Eng., 10, 219 (1970).
21. L. F. GLUSHCHENKO, "Correlation of Experimental Data on Critical Heat Fluxes in Subcooled Boiling," Teplofiz. Teplotekh., 15, 125 (1969); see also Heat Transfer Sov. Res., 2, 1, 139 (1970); Int. Chem. Eng., 10, 219 (1970).
22. 2 (100-2500 psia)," AEEW-R 789, United Kingdom Atomic Energy Authority (1972).
23. F. INASAKA and H. NARIAI, "Critical Heat Flux and Flow Characteristics of Subcooled Flow Boiling in Narrow Tubes," JSME Int. J., 30, 1595 (1987).
24. M. M. SHAH, "Improved General Correlation for Critical Heat Flux During Upflow in Uniformly Heated Vertical Tubes," Int. J. Heat Fluid Flow, 8, 326 (1987).
25. R. D. BOYD, "Subcooled Water Flow Boiling Experiments Under Uniform High Heat Flux Conditions," Fusion Technol., 13, 131 (1988).
26. M. CAIRA, G. CARUSO, and A. NAVIGLIO, "Requirements of High Heat Flux for Fusion Reactor Components: Revised Models and Correlations Predict Critical Heat Flux in Subcooled Flow Boiling," Proc. 1993 National Heat Transfer Conf., Atlanta, Georgia, August 8-11, 1993, p. 383, American Nuclear Society (1993).
27. G. P. CELATA, M. CUMO, and A. MARIANI, "Assessment of Correlations and Models for the Prediction of CHF in Water Subcooled Flow Boiling," Int. J. Heat Mass Transfer, 37, 237 (1994).
28. C. L. VANDERVORT, A. E. BERGLES, and M. K. JENSEN, "An Experimental Study of Critical Heat Flux in Very High Heat Flux Subcooled Boiling," Int. J. Heat Mass Transfer, 37, Suppl. 1, 161 (1994).
29. M. CAIRA, G. CARUSO, and A. NAVIGLIO, "A Correlation to Predict CHF in Subcooled Flow Boiling," Int. Comm. Heat Mass Transfer, 22, 35 (1995).
30. 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-R 356, United Kingdom Atomic Energy Authority (1964).
31. H. FIRSTENBERG, K. GOLDMANN, L. LOBIANCO, S. PREISER, and G. RABINOWITZ, "Compilation of Experimental Forced-Convection, Quality Burnout Data with Calculated Reynolds Numbers," NDA-2131-16, Nuclear Development Corporation of America (1960).
32. H. L. McGILL and W. L. SIBBITT, "Heat Transfer and Pressure Drop of Water Flowing in a Small Tube," ANL-4603 (Part I), Argonne National Laboratory (1951).
33. T. W. HUNT, H. S. JACKET, J. D. ROARTY, and J. E. ZERBE, "An Investigation of Subcooled and Quality Burnout in Circular Channels," WAPD-LSR(IM)-1, Westinghouse Electric Corp. (1955).
34. W. H. LOWDERMILK, C. D. LANZO, and B. L. SIEGEL, "Investigation of Boiling Burnout and Flow Stability for Water Flowing in Tubes," NACA TN 4382, National Advisory Committee for Aeronautics (1958).
35. W. H. LOWDERMILK and W. F. WEILAND, "Some Measurements of Boiling Burn-Out," NACA RM E54K10, National Advisory Committee for Aeronautics (1955).
36. R. A. DeBORTOLI and R. MASNOVI, "Effect of Dissolved Hydrogen on Burnout for Water Flowing Vertically Upward in Round Tubes at 2000 psia," WAPD-TH-318, Westinghouse Electric Corp. (1957).
37. M. A. STYRIKOVICH and L. E. FAKTOROVICH, "Effect of Tube Length on the Magnitude of Critical Heat Flow with Forced Convection of Steam-Water Mixtures," Dokl. Akad. Nauk SSSR, 120, 1018 (1958); see also Sov. Phys. Dokl., 3, 518 (1958); and USAEC Report NP-tr-180, U.S. Atomic Energy Commission.
38. M. A. STYRIKOVICH and L. E. FAKTOROVICH, "Effect of Tube Length on the Magnitude of Critical Heat Flow with Forced Convection of Steam-Water Mixtures," Dokl. Akad. Nauk SSSR, 120, 1018 (1958); see also Sov. Phys. Dokl., 3, 518 (1958); and USAEC Report NP-tr-180, U.S. Atomic Energy Commission.
39. D. H. LEE and J. D. OBERTELLI, "An Experimental Investigation of Forced Convection Burnout in High Pressure Water. Part I, Round Tubes with Uniform Flux Distribution," AEEW-R 213, United Kingdom Atomic Energy Authority (1963).
40. R. J. WEATHERHEAD, "Heat Transfer, Flow Instability, and Critical Heat Flux for Water in a Small Tube at 200 psia," ANL-6715, Argonne National Laboratory (1963).
41. K. M. BECKER, G. HERNBORG, M. BODE, and O. ERIKSSON, "Burnout Data for Flow of Boiling Water in Vertical Round Ducts, Annuli and Rod Clusters," AE-177, Aktiebolaget Atomenergi (1965).
42. G. P. CELATA and A. MARIANI, "A Data Set of Critical Heat Flux in Water Subcooled Flow Boiling," Proc. Specialists' Workshop Thermal-Hydraulics of High Heat Flux Components in Fusion Reactors, G.P. CELATA and A. MARIANI, Eds., ENEA Casaccia, Rome, Italy (1993).
43. W. R. GAMBILL, R. D. BUNDY, and R. W. WANSBROUGH, "Heat Transfer, Burnout, and Pressure Drop for Water in Swirl Flow through Tubes with Internal Twisted Tapes," Chem. Eng. Prog. Symp. Ser. No. 32, 57, 127 (1961).
44. J. MAYERSAK, S. D. RAEZER, and E. A. BUNT, "Confirmation of Gambill-Green Straight-Flow Burnout Heat Flux Equation at Higher Flow Velocity," ASME J. Heat Transfer, 86, 297 (1964).
45. R. R. HOOD, "Heavy Water Moderated Power Reactors. Progress Report: March 1962," DP-725, E.I. du Pont de Nemours and Company (1962).
46. J. W. SCHAEFER and J. R. JACK, "Investigation of Forced-Convection Nucleate Boiling of Water for Nozzle Cooling at Very High Heat Fluxes," NASA TN D-1214, National Aeronautics and Space Administration (1962).
47. 2O Coolant with Aluminum and Stainless Steel Heaters," DP-1306, E.I. du Pont de Nemours and Company (1973).
48. A. P. ORNATSKII and A. M. KICHIGIN, "An Investigation of the Dependence of Critical Thermal Loading on Weight Velocity, Underheating and Pressure," Teploenergetika, 8, 2, 75 (1961).
49. T. F. IRVINE, Jr., and P. E. LILEY, Steam and Gas Tables with Computer Equations, Academic Press, Orlando, Florida (1984).
50. A. P. ORNATSKII, "Critical Heat Loads and Heat Transfer for a Forced Flow of Water in Tubes in the Region of Superhigh Pressures (175-220atm)," Teploenergetika, 10, 3, 66 (1963); see also AEC-tr-6401, U.S. Atomic Energy Commission.
51. G. P. CELATA, M. CUMO, and A. MARIANI, "CHF in Highly Subcooled Flow Boiling with and Without Turbulence Promoters," presented at European Two-Phase Flow Group Mtg., Stockholm, Sweden, June 1-3, 1992.
52. G. P. CELATA, M. CUMO, and A. MARIANI, "Subcooled Water Flow Boiling CHF with Very High Heat Fluxes," Rev. Gen. Therm., 31, 106 (1992).
53. G. P. CELATA, M. CUMO, and A. MARIANI, "Burnout in Highly Subcooled Water Flow Boiling in Small Diameter Tubes," Int. J. Heat Mass Transfer, 36, 1269 (1993).
54. G. P. CELATA, ENEA Casaccia, Personal Communication (Feb. 26, 1996).
55. F. INASAKA and H. NARIAI, "Evaluation of Subcooled Critical Heat Flux Correlations for Tubes With and Without Internal Twisted Tapes," Proc. 5th Int. Topl. Mtg. Reactor Thermal Hydraulics, NURETH-5, Salt Lake City, Utah, September 21-24, 1992, Vol. 4, p. 919, American Nuclear Society (1992).
56. J. GRIFFEL, "Forced-Convection Boiling Burnout for Water in Uniformly Heated Tubular Test Sections," EngScD Thesis, Columbia University, New York (1965); see also NYO-187-7, New York Operations Office, U.S. Atomic Energy Commission.
57. J. G. COLLIER and J. R. THOME, Convective Boiling and Condensation, 3rd ed., Clarendon Press, Oxford, United Kingdom (1994).
58. P. BRICARD and A. SOUYRI, "Understanding and Modeling DNB in Forced Convective Boiling: A Critical Review, "Proc. Int. Symp. Two-Phase Flow Modeling and Experimentation, Rome, Italy, October 9-11, 1995, p. 843, G. P. CELATA and R. K. SHAH, Eds. (1995).
59. R. D. BOYD, "Subcooled Flow Boiling Critical Heat Flux (CHF) and Its Application to Fusion Energy Components. Part I. A Review of Fundamentals of CHF and Related Data Base," Fusion Technol., 7, 7 (1985).
60. R. D. BOYD, "Subcooled Flow Boiling Critical Heat Flux (CHF) and Its Application to Fusion Energy Components. Part II. A Review of Microconvective, Experimental, and Correlational Aspects,"Fusion Technol., 7, 31 (1985).
61. L. HAAR, J. S. GALLAGHER, and G. S. KELL, NBS/NRC Steam Tables, Hemisphere Publishing, Washington, D.C. (1984).
62. U. GRIGULL, J. STRAUB, and P. SCHIEBENER, Steam Tables in Si-Units, 3rd ed., Springer-Verlag, Berlin, Germany (1990).
63. G. CARUSO, University of Rome "La Sapienza," Personal Communication (Feb. 26, 1996).