Zusammenfassung
Dies ist ein Kapitel der 12. Auflage des VDI-Wärmeatlas.
Access this chapter
Tax calculation will be finalised at checkout
Purchases are for personal use only
Literatur
Cumo, M., Palazzi, G., Urbani, G.C.: On the Limiting Critical Quality and the „Deposition Controlled“ Burnout. CNEN-RT/ING, Bd. 4(79), Rome, Italy, (1979)
Drescher, G., Köhler, W.: Die Ermittlung kritischer Siedezustände im gesamten Dampfgehaltsbereich für innendurchströmte Rohre. BWK. 33(10), 416–422 (1981)
Doroshchuk, V.E., Levitan, L.L., Lantsmann, F.P.: Recommendations for calculating burnout in a round tube with uniform heat release. Teploenergetika 22(12), 66–70 (1975)
Academy of Sciences, USSR: Tabular data for calculating burnout when boiling water in uniformly heated round tubes. Therm. Eng. 23(9), 77–79 (1977)
Kon’kov, A.S.: Experimental study of the conditions under which heat exchange deteriorates when a steam water mixture flows in heated tubes. Teploenergetika 13(12), 77 (1965)
Groeneveld, D.C., Shan, J.Q., et al.: The 2005 CHF LOOK-UP TABLE. NURETH-11, paper 166, October 2–6, 2005. Avignon (2005)
Groeneveld, D.C., Cheng, S.C., Doan, T.: AECL-UO critical heat flux look-up table. Heat Transf. Eng. 7(1–2), 46–62 (1986)
Köhler, W., Herbst, O., Kastner, W.: Thermal-Hydraulic behavior of a safety condenser. In: Proceedings of the International Conference on New Trends in Nuclear System Thermo-Hydraulics, Vol. I, 30 May–2 June. Pisa (1994)
Cumo, M., Fabrizi, F., Palazzi, G.: The Influence of Inclination on CHF in Steam Generators Channels. CNEN-RT/ING, Bd. 11(78), Rome, Italy, (1978)
Merilo, M.: Critical heat flux experiments in a vertical and horizontal tube with both Freon-12 and Water as coolant. Nucl. Eng. Des. 44, 1–16 (1977)
Chojnowski, B., Wilson, P.W., Whitcutt, R.D.B.: Critical heat flux in inclined steam generating tubes. Symposium Multiphase Flow Systems, University Strathelyde Paper E 3. Institution of Chemical Engineers Symposium Series 38 (1974)
Watson, G., Lee, R.A., Wiener, M.: Critical heat flux in inclined and vertical smooth and ribbed tubes. Paper B 6.8. 5th International Heat Transfer Conference, Tokyo (1974)
Kefer, V.: Strömungsformen und Wärmeübergang in Verdampferrohren unterschiedlicher Neigung. Dissertation, Technical University of München (1989)
Ünal, H.C.: Some aspects of two-phase flow heat transfer and dynamic instabilities in medium and high pressure steam generators. Dissertation, Technische Hochschule Delft (1981)
Roumy, R: Dryout in Helically Coiled Tubes with Boiling Freon 12. European Two-Phase Flow Group Meeting, Copenhagen (1971)
Campolunghi, F., Cumo, M., Ferrari, G., Palazzi, G.: Full Scale Tests and Thermal Design Correlations for Coiled Once-Through Steam Generators. CNEN-RT/ING, Bd. (75):11, Rome, Italy, (1975)
Cumo, M., Farello, G.E., Ferrari, G.: The influence of curvature in post dryout heat transfer. Int. J. Heat Mass Transf. 15, 2045–2062 (1972)
Naitoh, M., Nakamura, A., Ogasawara, H.: Dryout in helically coiled tube of sodium heated steam generator. ASME 74-WA/HT-48 (1974)
Duchatelle, L., De Nucheze, L., Robin, M.G.: Departure from nucleate boiling in helical tubes of liquid metal heated steam generators. ASME 73-HT-57 (1973)
Ünal, H.C., van Gasselt, M.L.G., van T'Verlaat, P.M.: Dyrout and two-phase flow pressure drop in sodium heated helically coiled steam generators tubes at elevated pressures. Int. J. Heat Mass Transf. 24, 285–298 (1981)
Miropol’skiy, Z.L., Pikus, V.Y.: Critical boiling heat fluxes in curved channels. Heat Tran. Sov. Res. 1(1), 74–79 (1969)
Babarin, V.P., Sevat’yanov, R.I., Alad’yev, I.T., Khudyakow, V.F., Tzachev, V.A.: Critical heat flux in tubular coils. Heat Transf. Sov. Res. 3(4), 85–90 (1971)
Alad’yev, I.T., Petrov, C.I., Rzayev, A.I., Khudyakov, V.F.: Heat transfer in a sodium-potassium heat exchanger (potassium boiler) made of helically-coiled tubes. Heat Tran. Soviet Res. 8(3), 1–16 (1976)
Butterworth, D.: A Model for Predicting Dryout in a Tube with a Circumferential Variation in Heat Flux. AERE-M 2436, Harwell (1971)
Cumo, M., Palazzi, G., Urbani, G., Frazolli, F.V.: Full Scale Tests on Axial Profile Heat Flux. Influence on the Critical Quality in PWR Steam Generators. CNEN-RT/ING, Bd. 5(80), Rome, Italy, (1980)
Cocilovo, M., Cumo, M., Palazzi, G.: On DNB Location with Axially Disuniform Heat Flux. CNEN-RT/ING, Bd. 21(79), Rome, Italy, (1979)
Doroshchuk, C.E., Levitan, L.L. et al.: Investigations into Burnout mechanism in steam-generating tubes. Paper FB-21. In: 6th International Heat Transfer Conference, Toronto, 7–11 Aug 1978
Peskov, O.L., Remizoo, O.V., Sudnitsyn, O.A.: Some features of heat transfer burnout in tubes with non-uniform axial heat flux distribution. Paper NR-10. 6th International Heat Transfer Conference, Toronto, 7–11 Aug 1978
Keeys, R.K.F., Ralph, I.C., Roberts, D.N.: Post-burnout heat transfer in high pressure steam-water mixtures in an tube with cosine heat flux distribution. Progr. Heat Mass Transf. 6, 99–118 (1972)
Becker, K.M., Letzter, A.: Burnout measurements for flow of water in an annulus with two-sided heating. KTH-NEL-23. European Two-Phase Flow Group Meeting, Haifa (1975)
Cheng, X., Müller, U.: Review on Critical Heat Flux in Water Cooled Reactors. Forschungszentrum Karlsruhe GmbH, FZKA 6825, Institut für Kern- und Energietechnik, Karlsruhe (2003)
Zernick, W., Currin, H.B., Elyash, E., Previti, G.: THINC, A Thermal Hydrodynamic Interaction Code for a Semi-Open or Closed Channel Core. WCAP-3704, Atomic Power Div., Pittsburgh, USA, (1962)
Chelemer, H., Weismann, J., Tong, L.S.: Subchannel Thermal Analysis of Rod Bundle Core. WCAP-7014, Atomic Power Div., Pittsburgh, USA, (1967)
Bowring, R.W.: HAMBO – A Computer Program for the Subchannel Analysis of the Hydraulic and Burnout Characteristics of Rod Clusters. AEEW R 524 (1967)
Rowe, D.S.: Crossflow Mixing Between Parallel Flow Channels During Boiling. Part 1: COBRA – Computer Program for Coolant Boiling. BNWL-371 Part 1 (1967)
Rowe, D.S.: COBRA IIIC: A Digital Computer Program for Steady State and Transient Thermal-Hydraulic Analysis of Rod Bundle Nuclear Fuel Elements. BNWL-1965 (1973)
Hochreiter, L.E., Chelemer, H.: Application of the THINC-IV Program to PWR Design. WCAP-8195 (1973)
Ulrych, G.: Strömungsvorgänge mit unterkühltem Sieden in Brennstabbündeln wassergekühlter Kernreaktoren. Dissertation, TU Braunschweig (1976)
Burtak, F., Heinecke, J., Glück, M., Kronenberg, J., Kollmann, T.: Advanced Thermal Hydraulic Core and Fuel Assembly Design with State-of-the-Art Subchannel Codes. TOPFUEL, Salamanca, 22–26 Oct 2006
Glück, M.: Sub-channel analysis with F-COBRA-TF – code validation and approaches to CHF prediction. Nucl. Eng. Des. 237, 655–667 (2007)
Suchy, P., Ulrych, G., Kemner, H., Kurz, E.: Application of tables of critical heat fluxes to rod bundles. Transactions of the ENC ’79 Conference of the European Nuclear Society. Hamburg, Germany, May (1979)
Lahey, R.T., Drew, D.A.: An asssessment of the literature related to LWR instability modes. NUREG/CR-1414 (1980)
Katto, Y., Ohno, H.: 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 Transf. 27(9), 1641–1648 (1984)
Katto, Y.: A generalized correlation of critical heat flux for the forced convection boiling in vertical uniformly heated round tubes – a supplementary report. Int. J. Heat Mass Transf. 22, 783–794 (1979)
Katto, Y., Yokoya, S.: CHF of forced convection boiling in uniformly heated vertical tubes: experimental study of HP-Regime by the use of refrigerant 12. Int. J. Multiphase Flow 8, 165–181 (1982)
Groeneveld, D.C.: The occurrence of upstream dryout in uniformly heated channels. Proc. 5th Int. Heat Transf. Conf. 4, 265–269 (1974)
Katto, Y.: A generalized correlation of ritical heat flux for the forced convection boiling in vertical uUniformly heated round tubes. Heat Mass Transf. 21, 1527–1542 (1978)
Katto, Y.: An analysis of the effect of inlet subcooling on critical heat flux of forced convection boiling in vertical uniformly heated tubes. Int. J. Heat Mass Transf. 22, 1567–1575 (1979)
Katto, Y.: General features of CHF of forced convection boiling in uniformly heated vertical tubes with zero inlet subcooling. Int. J. Heat Mass Transf. 23, 493–504 (1980)
Katto, Y.: Critical heat flux of forced convection boiling in uniformly heated vertical tubes (Correlation of CHF in HP-regime and determination of CHF-Regime map). Int. J. Heat Mass Transf. 23, 1573–1580 (1980)
Katto, Y.: A study of limiting exit quality of CHF of forced convection boiling in uniformly heated vertical channels. Transaction of American Society of Mechanical. Engineera, Series C. J. Heat Transf. 104, 40–47 (1982)
Katto, Y.: On the heat-flux/exit-quality type correlation of CHF of forced convection boiling in uniformly heated vertical tubes. Int. J. Heat Mass Transf. 24, 533–539 (1981)
Katto, Y., Ashida, S.: CHF in high-pressure regime for forced convection boiling in uniformly heated vertical tube of low length-to-diameter ratio. Proc. 7th Int. Heat Tranf. Conf. 4, 291–296 (1982)
Nishikawa, K., Yoshida, S., Yamada, A., Ohno, M.: Experimental investigation of critical heat flux in forced convection boiling of Freon in a tube at high subcritical pressure. Proc. 7th Int. Heat Transf. Conf. 4, 321–326 (1982)
Katto, Y.: An analytical investigation on CHF of flow boiling in uniformly heated vertical tubes with special reference to governing dimensionsless groups. Int. J. Heat Mass Transf. 25, 1353–1361 (1982)
Groeneveld, D.C.: Freon Dryout Correlations and their Applicability to Water. AECL 3418 (1969)
Ilic, V.: The Effect of Pressure on Burnout in a Round Tube Cooled by Freon 12. AAEC/E 325 (1974)
Barnett, P.G., Wood, R.W.: An Experimental Investigation to Determine the Scaling Laws of Forced Convection Boiling Heat Transfer, Part 2: An Examination of Burnout Data for Water, Freon 12 and Freon 21 in Uniformly Heated Round Tubes. AEEW-R443 (1965)
Staub, F.W.: Two phase fluid modelling – the critical heat flux. Nucl. Sci. Eng. 35, 190–199 (1969)
Purcupile, J.C., Gouse, S.W.: Reynolds Flux Model of Critical Heat Flux in Subcooled Forced Convection Boiling. ASME-72-HT-4 (1972)
Dix, G.E.: Freon-Water Modelling of the CHF in Round Tubes. ASME 70-HT-26, ASME, New York (1970)
Katto, Y., Yokoya, S.: Critical heat flux of liquid helium (I) in forced convective boiling. Int. J. Multiphase Flow 10(4), 401–413 (1984)
Lewis, J.P., Goodykoontz, J.H., Kline, J.F.: Boiling Heat Transfer to Liquid Hydrogen and Nitrogen in Forced Flow. NASA, Techn. Note D-1314. National Aeronautics and Space Administration, Washington, DC (1962)
Alad’yev, T., Gorlov, I.G., Dodonov, L.D., Fedynskiy, O.S.: Heat transfer to boiling potassium in uniformly heated tubes. Heat Transf. Sov. Res. 1(4), 14–26 (1969)
Hoffman, H.W., Krakoviak, A.I.: Convective Boiling with Liquid Potassium. In: Proceedings of the Heat Transfer and Fluid Mechanics Institute, S. 19–37. Oak Ridge National Laboratory, Oak Ridge (1964)
Noel, M.B.: Experimental Investigation of the Forced-Convection and Nucleate-Boiling Heat-Transfer Characteristics of Liquid Ammonia. JPL-Tech. Notes Report No. 32–125, California Inst. of Tech., Pasadena, CA, USA, (1966)
Cumo, M., Bertoni, R., Cipriani, R., Palazzi, G.: Up-flow and down-flow burnout. Inst. Mech. Eng. Conf. Publ. 1977–1978, 183–192 (1977)
Wojtan, L., Revellin, R., Thome, J.R.: Investigation of saturated critical heat flux in a single, uniformly heated microchannel. Exp. Thermal Fluid Sci. 30, 765–774 (2006)
Park, J.E., Thome, J.R.: Critical heat flux in multi-microchannel copper elements with low pressure refrigerants. Int J. Heat Mass Transf. 53, 110–122 (2010)
Jensen, M.K., Bergles, A.: Critical heat flux in helically coiled tubes. J. Heat Transf. 103, 660–666 (1981)
Ahmad, S.Y.: Fluid-to-fluid modelling of CHF: a compensated distortion model. Int. J. Heat Mass Transf. 16, 641–662 (1973)
Katsaounis, A.: Literaturbewertung zur Fluidähnlichkeit für die kritische Heizflächenbelastung. GKSS 81/E/10, Geesthacht-Tesperhude, Germany
Katsaounis, A.: Verification of Ahmad’s Fluid-to-Fluid Scaling Law by Bundle Experiments. Winter Annual Meeting of ASME, Chicago, HDT-Vol. 14 (1980)
Katsaounis, A.: Comparison of Various CHF-Data Performed in Different Fluids and Test Sections with Various CHF-Correlations. Europ. Two-Phase Flow Group Meeting, Eindhoven, 1981 und GKSS 81/E/35, GKSS-Forschungszentrum Geesthacht GmbH, Geesthacht-Tesperhude, Germany (1981)
Stephan, K., Körner, M.: Berechnung des Wärmeübergangs verdampfender binärer Flüssigkeitsgemische. Chem.-Ing. Techn. 41, 409–434 (1969)
Marroquin Nisch, A.: Kritische Wärmestromdichte und minimale Wärmestromdichte des Filmsiedens binärer Gemische im zwangsdurchströmten senkrechten Rohr. Fortschr.-Ber. VDI, Reihe 3, Nr. 541. VDI Verlag, Düsseldorf (1998)
Sterman, L., Abramov, A., Checheta, G.: Investigation of Boiling Crisis at Forced Motion of High Temperature Organic Heat Carriers and Mixtures. International Symposium on Research into Co-current Gas-Liquid Flow, University of Waterloo, Canada, paper E 2 (1968)
Tolubinskiy, V.I., Matorin, A.S.: Forced convection boiling heat transfer crisis with binary mixture. Heat Transf. Sov. Res. 5(2), 98–101 (1973)
Celata, G.P., Cumo, M., Setaro, T.: Critical heat flux in upflow-convective boiling of refrigerant binary mixtures. Int. J. Heat Mass Transf. 37, 1143–1153 (1994)
Wallis, G.B.: One-dimensional Two-Phase-Flow. Mc-Graw-Hill, New York (1969)
Author information
Authors and Affiliations
Corresponding author
Editor information
Editors and Affiliations
Section Editor information
Rights and permissions
Copyright information
© 2019 Springer-Verlag GmbH Deutschland, ein Teil von Springer Nature
About this chapter
Cite this chapter
Herbst, O. (2019). H3.6 Strömungssieden – Kritische Siedezustände. In: Stephan, P., Kabelac, S., Kind, M., Mewes, D., Schaber, K., Wetzel, T. (eds) VDI-Wärmeatlas. Springer Reference Technik(). Springer Vieweg, Berlin, Heidelberg. https://doi.org/10.1007/978-3-662-52989-8_59
Download citation
DOI: https://doi.org/10.1007/978-3-662-52989-8_59
Published:
Publisher Name: Springer Vieweg, Berlin, Heidelberg
Print ISBN: 978-3-662-52988-1
Online ISBN: 978-3-662-52989-8
eBook Packages: Computer Science and Engineering (German Language)