A peer-reviewed journal published by K. N. Toosi University of Technology

Simulation of pool boiling for surfaces with various wettability

Document Type : Research Article

Author

Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute, 1439951113, Tehran, Iran

Abstract
A boiling model, specifically the Rensselaer Polytechnic Institute (RPI) model, is utilized by Computational Fluid Dynamics (CFD) code to calculate the pool boiling behavior on surfaces with varying wettability characteristics. The RPI model is an accurate method for predicting the heat transfer coefficient of nucleate boiling, which is based on a component-by-component heat flux analysis. With some modifications, the RPI model can also be employed to simulate pool boiling heat transfer and CHF. To validate the modeling approach, the calculated heat flux for the pool boiling regime is compared to experimental data from the literature. The results indicate that the modified RPI model has a good ability to accurately predict the heat flux for the pool boiling stage. Furthermore, this modified RPI model demonstrates close agreement with the experimental results obtained for surfaces exhibiting diverse wettability properties. This suggests the model's capability to effectively capture the impact of surface wettability on pool boiling heat transfer. The successful application and validation of the modified RPI model for pool boiling simulations, particularly its ability to account for varying surface wettability characteristics, represents a valuable contribution to the existing knowledge on computational modeling of boiling heat transfer phenomena.

Highlights

  • The Rensselaer Polytechnic Institute (RPI) model, is used to simulate surfaces with different wettability
  • With some modifications, the RPI model be employed to simulate pool boiling heat transfer and CHF.
  • The modified RPI model has a good ability to accurately predict the heat flux for the pool boiling stage.
  • The critical heat flux results from the simulation showed an error of less than 5% compared to the experimental results.

Keywords


Bowring, R. (1962). Physical model, based on bubble detachment, and calculation of steam voidage in He sub-cooled region of a heated channel. Technical report, Institutt for Atomenergi (Norway). OECD Halden Reaktor Prosjekt.
Drew, D. and Lahey, R. (1993). Particulate two-phase flow, Butterworth Heinemann, Boston. MA, pages 509–566.
Gerardi, C., Buongiorno, J., Hu, L.-w., et al. (2010). Study of bubble growth in water pool boiling through synchronized, infrared thermometry and high-speed video. International Journal of Heat and Mass Transfer, 53(19-20):4185–4192.
Hadad, K., Rahimian, A., and Nematollahi, M. (2013). Numerical study of single and two-phase models of water/Al2O3 nanofluid turbulent forced convection flow in VVER-1000 nuclear reactor. Annals of Nuclear Energy, 60:287–294.
Hadad, K., Rahimian, A., and Rabiee, A. (2015). Nanofluid application in post SB-LOCA transient in VVER-1000 NPP. Annals of Nuclear Energy, 79:101–110.
Ishii, M. and Mishima, K. (1984). Two-fluid model and hydrodynamic constitutive relations. Nuclear Engineering and Design, 82(2-3):107–126.
Kandlikar, S. G. (2001). A theoretical model to predict pool boiling chf incorporating effects of contact angle and orientation. J. Heat transfer, 123(6):1071–1079.
Liang, G. and Mudawar, I. (2019). Review of pool boiling enhancement by surface modification. International Journal of Heat and Mass Transfer, 128:892–933.
Liao, L., Bao, R., and Liu, Z. (2008). Compositive effects of orientation and contact angle on critical heat flux in pool boiling of water. Heat and Mass Transfer, 44:1447-1453.
Rahimian, A., Kazeminejad, H., Khalafi, H., et al. (2019). Boiling heat transfer and critical heat flux enhancement using electrophoretic deposition of sio2 nanofluid. Science and Technology of Nuclear Installations, 2019(1):1272156.
Rahimian, A., Kazeminejad, H., Khalafi, H., et al. (2020a). Effect of gamma irradiation on the critical heat flux of nano-coated surfaces. Nuclear Engineering and Technology, 52(10):2353–2360.
Rahimian, A., Kazeminejad, H., Khalafi, H., et al. (2020b). Effect of nano-particle coating techniques of SiO2 on improvement of Critical Heat Flux. Journal of Nuclear Science, Engineering and Technology (JONSAT), 41(4):65–73.
Rahimian, A., Kazeminejad, H., Khalafi, H., et al. (2020c). An experimental study of the steel cylinder quenching in water-based nanofluids. International Journal of Engineering, 33(1):28–33.
Rahimian, A., Kazeminejad, H., Khalafi, H., et al. (2022). Effect of gamma irradiation on the critical heat flux of sintered nano-coated surfaces. Radiation Physics and Chemistry, 199:110297.
Sharma, S. K., Shukla, R., and Sikarwar, B. (2015). Experimental Study for Investigating the Mechanism of Heat Transfer Near the Critical Heat Flux in Nucleate Pool Boiling. International Journal of Engineering, 28(8):1241–1250.
Zuber, N. (1959). Hydrodynamic Aspects of Boiling Heat Transfer.
Volume 6, Issue 3
Spring 2025
Pages 35-40

  • Receive Date 10 September 2024
  • Revise Date 06 January 2025
  • Accept Date 20 January 2025