1995 Look-up Table for Calculating Critical Heat Flux in Tubes

Thermal Engineering

Volumn 44, Issue 10, 1997, Pages 823-840

  Bobkov, V P ^a   Vinogradov, V N ^a   Groeneveld, D C ^b   Kirillov, P L ^a   Leung, L K ^b   Royer, E ^c   Smogalev, I P ^a   Huang, H C ^d  

^a State Sci Ctr of the Russ Fed   (Russian Federation)

^b CANADIAN NUCLEAR LABORATORIES   (Canada)

^c EDF R AND D   (France)

^d UNIVERSITY OF OTTAWA   (Canada)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0344907202     PISSN: 00406015     EISSN: None     Source Type: Journal    
DOI: None     Document Type: Article

References (25)

1. Doroshchuk, V.E., Levitan, L.L., and Lantzman, F.P., Investigation into Burnout in Uniformly Heated Tubes, ASME Publication 75-WA/HT-22, 1975.
2. Tabulated Data for Calculating Heat Transfer Crisis under Water Boiling in Uniformly Heated Round Tubes, Teploenergetika (Moscow), 1976, no. 9, pp. 90-92.
3. Recommendations for Calculating Heat Transfer Crisis under Water Boiling in Round Tubes, Preprint of Inst. of High Temperatures, USSR Acad. Sci., no. 1-57, Moscow, 1980.
4. Groeneveld, D.C., Cheng, S.C., and Doan, T., 1986 AECL-U0 Critical Heat Flux Look-up Table, Heat Transfer Engineering, 1986, no. 7, pp. 40-62.
5. Kirillov, P.L., Bobkov, V.P., Boltenko, E.A., et al., A Method for Developing Standard Reference Data on Heat Transfer Crisis in Tubes under Uniform Heat Flux Distribution, Preprint of Energy Physics Inst. FEI-2030, Obninsk, 1989.
6. Kirillov, P.L., Bobkov, V.P., Vinogradov, V.N., et al., On Standard Critical Heat Flux Data for Round Tubes, Proc. of the 4th Int. Topical Meeting on Nuclear Reactor Thermohydraulics, Karlsruhe, FRG, 1989, no. 1, pp. 103-108.
7. Kirillov, P.L., Bobkov, V.P., Boltenko, E.A., et al., New Tables on Critical Heat Flux for Water in Round Tubes, Preprint of Energy Physics Inst. FEI-2225, Obninsk, 1991.
8. Kirillov, P.L., Bobkov, V.P., Boltenko, E.A., et al., Look- up Tables on Heat Transfer Crisis in Tubes, At. Energ., 1991, vol. 71, no. 1, pp. 18-28.
9. Richards, D.J., AECL Internal Mem., 1992.
10. Bestion, D., The Physical Closure Laws in the CATHARE Code, Nucl. Eng. Des., 1990, vol. 124, pp. 229-245.
11. Weaver, W.L., Riemke, R.A., Wagner, R.J., and Johnsen, G.W., The RELAP 5 / Mod. 3 Code for PWR Safety Analysis, Proc. of the 4th Int. Topical Meet. on Nucl. Reactor Thermohydraulics, Karlsruhe, Germany, 1991, vol. 2, pp. 1221-1226.
12. Kiteley, J.C., Carver, M.B., Liner, Y., et al., ASSERT-IV Thermohydraulic Subchannel Analysis Code Simulation of Dryout Power and Pressure Drop in a Horizontal 37-Rod Bundle Fuel Channel Including the Effect of Pressure Tube Creep, Proc. of the 16th Annual CNA Nuclear Simulation Symp., New Brunswick, Aug. 1991, pp. 25-27.
13. Ulrich, G., CHF Table Application in KWU PWR Design, Int. Workshop on CHF Fundamentals-CHF Table Improvements, Braunschweig, Germany, March 3-5, 1993.
14. Smith, R.A., Boiling Inside Tubes: Critical Heat Flux for Upward Flow in Uniformly Heated Tubes, ESDU Data Item no. 86032, London: Eng. Sci. Data Unit Int. Ltd., 1986.
15. Groeneveld, D.C., Kiameh, B.P., and Cheng S.C., Prediction of Critical Heat Flux (CHF) for Non-Aqueous Fluids in Forced Convective Boiling, Proc. of the 8th Int. Heat Trans. Conf., San Francisco, California, 1981.
16. CHF Fluid-to-Fluid Modeling Studies in Three Different Laboratories Using Different Modeling Fluids, Proc. of the 5th Int. Topical Meet. on Nuclear Reactor Thermohydraulics, Salt Lake City, Utah, Sept. 21-25, 1992.
17. Zuber, N., Hydrodynamic Aspects of Boiling Heat Transfer, USAEC Rep. AECU-4439, 1959.
18. Griffith, P., Pearson, J.F., and Lepovski, R.J., Critical Heat Flux during a Loss-of-Coolant Accident, Nuclear Safety, 1977, no. 18, pp. 298-305.
19. Ivey, H.J. and Morris, D.J., On the Relevance of the Vapor-Liquid Exchange Mechanism for Subcooled Boiling Heat Transfer at High Pressure, AEEW-R-137, 1961.
20. Katto, J., A Prediction Model of Subcooled Water Flow Boiling CHF for Pressure in the Range 0.1-20 MPa, Int. J. Heat Transfer, 1991, no. 35, pp. 1115-1123.
21. Huang, X.C., Cheng, S.C., and Groeneveld, D.C., A Simple Method for Smoothing Multidimensional Experimental Data with Application to CHF and Post- CHF Tables, Part J: Applications, Numerical Heat Transfer, 1994.
22. Groeneveld, B.C., Leung, L., Bobkov, V.P., et al., The 1995 Look-up Table for Critical Heat Flux in Tubes, Nucl. Sci. and Des., 1996, vol. 163, pp. 1-23.
23. Becker, K.M., An Analytical and Experimental Study of Burnout Conditions in Vertical Round Ducts, Rep. AE-178, Aktiebolaget Atomenergi, Stockholm, 1965.
24. Biasi, L., Clerici, G.C., Garriba, S., et al., Studies of Burnout. Part 3: A New Correlation for Round Ducts and Uniform Heating and Its Comparison with World Data, Energia Nucleare, 1967, no. 14, pp. 530-536.
25. 2, AEEW-R-789, 1972.