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Abstrakty
Detailed experimental data obtained at the TOPFLOW facility for steam-water vertical pipe flow were used to test the complex interaction of local bubble distributions, bubble size distributions and local heat and mass transfer. Steam is injected into subcooled water and condenses during the upward flow. The model considers a large number of bubble classes (50). This allows the investigation of the influence of the bubble size distribution. The results of the simulations show a good agreement with experimental data. The condensation process is clearly slower, if large bubbles are injected (4 mm holes). Also the bubble break-up has a strong influence on the condensation process because of the change of the interfacial area. Some unsureness arises from the unknown interfacial area for large bubbles and possible uncertainties of the heat transfer coefficient.
Czasopismo
Rocznik
Tom
Strony
49--59
Opis fizyczny
Bibliogr. 14 poz., tab., rys.
Twórcy
autor
- Forschungszentrum Rossendorf e. V., Institute of Safety Research,. p.o. Box 510 119, D-01314 Dresden, Germany
autor
- Forschungszentrum Rossendorf e. V., Institute of Safety Research,. p.o. Box 510 119, D-01314 Dresden, Germany
Bibliografia
- [1] LUCAS D., SHI J.-M., KREPPER E. AND PRASSER H.-M.: Models for the forces acting on bubbles in comparison with experimental data for vertical pipe flow, 3rd Int. Symposium on Two-Phase Flow Modelling and Experimentation, Pisa, Italy, 2004, Paper ha04.
- [2] LUCAS D. AND PRASSER H.-M.: Scaling effects in vertical bubbly pipe flow, 5th Int. Conf. on Multiphase Flow, ICMF'04, Yokohama, Japan, 2004, Paper No. 187.
- [3] LUCAS D., KREPPER E. AND PRASSER H.-M.: Development of bubble size distributions in vertical pipe flow by consideration of radial gas fraction profiles, 4th Int. Conf. on Multiphase Flow, ICMF'01, New Orleans, USA, 2001, Paper 378.
- [4] LUCAS D., KREPPER E. AND PRASSER H.-M.: Modelling of the evolution of bubble flow along a large vertical pipe, The 11th Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11), Avignon, France, October 2-6, 2005, Paper 051.
- [5] TOMIYAMA A.: Struggle with computational bubble dynamics, 3rd Int. Conf. on Multiphase Flow, ICMF'98, Lyon, France, 1998.
- [6] LUCAS D., KREPPER E. AND PRASSER H.-M.: Prediction of radial gas profiles in vertical pipe flow on basis of the bubble size distribution, Int. J. of Therm. Sci. 40(2001), 217-225.
- [7] KREPPER E., LUCAS D, PRASSER H.-M.: On the modelling of bubbly flow in vertical pipes, Nuclear Eng. and Design 235(2005), 597-611.
- [8] PRASSER H.-M., BEYER M., CARL H., GREGOR S., SCHÜTZ P., WEISS F.-P.: Flow structure during steam condensation in sub-cooled water in a large vertical pipe using wire-mesh sensors, Proc. of HEAT-2005, Gdansk, Poland, June 26-30, 2005.
- [9] PRASSER, H.-M., BÖTTGER, A., ZSCHAU, J.: A new electrode-mesh tomograph for gas-liquid flows, Flow Measurement and Instrumentation, 9(1998), 111-119.
- [10] PRASSER, H.-M., BEYER, M., CARL, H., GREGOR, S., LUCAS, D., PIETRUSKE, H., SCHÜTZ, P., WEISS, F.-P.: Evolution of the structure of a gas-liquid two-phase flow in a large vertical pipe, The 11 Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11), Avignon, France, October 2-6, 2005, paper 399.
- [11] PRASSER, H.-M., SCHOLZ, D., ZIPPE, C.: Bubble size measurement using wire-mesh sensors, Flow Measurement and Instrumentation, 12/4, 2001 299-312.
- [12] BURNS A.D., FRANK T., HAMILL I., SHI J.-M.: The favre averaged drag model for turbulence dispersion in Eulerian multi-phase flows, 5th Int. Conf. on Multiphase Flow, ICMF'2004, Yokohama, Japan, 2004.
- [13] HUGHMARK, G.A: Mass and heat transfer from a rigid sphere, AIChE Journal 13(1967), 1219.
- [14] WELLEK, R.M., AGRAWAL A.K., SKELLAND, A.H.P: Shapes of liquid drops moving in liquid media, AIChE Journal, 12(1966), 854-860.
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-article-BGPK-1398-5506