Abstract
In this paper a convective flow boiling of refrigerant R-11 in a vertical annular channel has been investigated. Measurements were performed under various conditions of mass flux, heat flux, and inlet subcooling, which enabled to study the influence of different boundary conditions on the development of local flow parameters. Also, some measurements have been compared to the predictions by the three-dimensional two-fluid model of subcooled boiling flow carried out with the computer code ANSYS-CFX-13. Simulation results successfully predict the main experimental tendencies associated with the heat flux and Reynolds number variation. A sensitivity analysis of several modelling parameters on the radial distribution of flow quantities has highlighted the importance of correct description of the boiling boundary layer. In general a good quantitative and qualitative agreement with experimental data was obtained.
Similar content being viewed by others
References
Končar B, Krepper E, Egorov Y (2005) CFD modeling of subcooled flow boiling for nuclear engineering applications. International conference nuclear energy for New Europe 2005 Bled, Slovenia, 5–8 Sept 2005
Končar B, Kljenak B, Mavko B (2004) Modelling of local two-phase flow parameters in upward subcooled flow boiling at low pressure. Int J Heat Mass Transf 47:1499–1513
Končar B, Matkovič M (2012) Simulation of turbulent boiling flow in a vertical rectangular channel with one heated wall. Nucl Eng Design 245:131–139
Končar B, Mavko B (2003) Modelling of low-pressure subcooled flow boiling using the RELAP5 code. Nucl Eng Des 220:255–273
ANSYS Inc. (2009) ANSYS CFX 12.0: users manual
Tu JY, Yeoh GH (2002) On numerical modeling of low pressure subcooled boiling flows. Int J Heat Mass Transf 45:1197–1209
Chen E, Li Y, Cheng X (2009) CFD simulation of upward subcooled boiling flow of refrigerant-113 using two fluid model. Int J Appl Thermal Eng 29:2508–2517
Končar B, Mavko B (2008) Simulation of boiling flow experiments close to CHF with the Neptune CFD code, Hindawi Publishing Corporation Science and Technology of Nuclear Installations, vol 2008, article ID 732158, p 8
Končar B, Kljenak I, Mavko B (2004) Modeling of local two-phase flow parameters in upward subcooled flow boiling at low pressure. Int J Heat Mass Transf 47:1499–1513
Končar B, Krepper E (2007) CFD simulation of convective flow boiling of refrigerant in a vertical annulus. Nucl Eng Design 238:693–706
Anglart H, Nylund O, Kurul N, Podowski MZ (1997) “CFD prediction of flow and phase distribution in fuel assemblies with spacers”, NURETH-7, Saratoga Springs, New York, 1995. Nucl Eng Design (NED) 177:215–228
Bouaichaoui Y, Semine (2007) “Experimental study of forced convection with phase change in an annular channel”, first international conference on physics and technology of reactors and applications. Marrakech, Morocco, 14–16 Mar 2007
Bouaichaoui Y, Kibboua R, Bousbia-Salah A, Belkaid A (2009) Theoretical and experimental study of the forced convection with phase change in annular channel, 2nd international symposium on nuclear energy. Amman, Jordan, 26–28 Oct 2009
Gopinath R, Basu N, Dhir VK (2002) Interfacial heat transfer during subcooled flow boiling. Int J Heat Mass Transf 45:3947–3959
Lemmert M, Chwala JM (1977) Influence of flow velocity on surface boiling heat transfer coeffecient. Heat Transf Boil 237–247
Van Stralen SJD, Cole R, Sluyter WM, Sohal MS (1975) Bubble growth rates in nucleate boiling of water at sub atmospheric pressures. Int J Heat Mass Transf 18:655–669
Tolubinsky VI, Kostanchuk DM (1970) Vapour bubbles growth rate and heat transfer intensity at subcooled water boiling. In: Proceedings of the 4th international heat transfer conference, vol 5, paper No. B-2.8. Paris
Sato Y, Sadatomi M, Sekoguchi K (1998) Momentum and heat transfer in two phase bubble flow. Int J Multiphase Flow 7:167–177
Ishii M, Zuber N (1979) Drag coefficient and relative velocity in bubbly, droplet or particulate flows. AIChE J 25:843–855
Le Corre JM, Yao SC, Amon CH (2010) Two-phase flow regimes and mechanisms of critical heat flux under subcooled flow boiling conditions. Nucl Eng Des 240:245–251. doi:10.1016/j.nucengdes.2008.12.008
Celata GP, Cumo M, Mariani A, Zummo G (1998) Physical insight in the burnout region of water-subcooled flow boiling. Rev Gen Therm 37:450–458
Bang IC, Chang SH, Baek WP (2004) Visualization of the subcooled flow boiling of R-134a in a vertical rectangular channel with an electrically heated wall. Int J Heat Mass Transf 47:4349–4363
Acknowledgments
The authors gratefully acknowledge close cooperation with researcher Boštjan Končar from Reactor Engineering Division at Jožef Stefan Institute in Slovenia.
Author information
Authors and Affiliations
Corresponding author
Rights and permissions
About this article
Cite this article
Bouaichaoui, Y., Kibboua, R. & Matkovič, M. Experimental measurements and CFD simulation of convective boiling during subcooled developing flow of R-11 within vertical annulus. Heat Mass Transfer 51, 735–748 (2015). https://doi.org/10.1007/s00231-014-1449-3
Received:
Accepted:
Published:
Issue Date:
DOI: https://doi.org/10.1007/s00231-014-1449-3