On Development and Validation of subcooled nucleate models for OpenFOAM Foundation Release


On Development and Validation of subcooled nucleate models for OpenFOAM Foundation Release

Peltola, J.; Bainbridge, W.; Lehnigk, R.; Schlegel, F.; Pättikangas, T. J. H.

Abstract

Subcooled nucleate boiling capability based on [1] was introduced to OpenFOAM 4.0 [2] within multiphase framework called reactingEulerFoam that supports two- and multiphase simulations. Since then the capability has been further refined and extended in subsequent releases 5.0 and 6. The present implementation - available in OpenFOAM Foundation development release [3] - includes the RPI wall boiling model [4] with run time selectable nucleation site density and bubble departure diameter and frequency models. Runtime selectable wall heat transfer models for distribution of wall heat flux between gas and liquid phases are also included for non-equilibrium phase change simulations. Interfacial heat transfer and phase change are calculated with two-resistance approach and interface temperature using user selectable heat transfer models and saturation temperature model. For turbulence modelling, single-phase models available in the release can be selected and there are also specialized k-ε and k-ω two-phase models available. For bubble diameter modelling algebraic [5], IATE [6] and inhomogeneous class method models are available [7, 8].

The present paper compares simulation results obtained with different model combinations to publicly available experimental data from DEBORA and other experiments. The implications of the choices of the models and model parameters on accuracy and performance are discussed and practical recommendations are given for those that intend to use this publicly available resource for further research.

[1] Peltola, J., & Pättikangas, T.J.H. (2012). CFD4NRS-4, paper 59.
[2] OpenFOAM Foundation, OpenFOAM 4.0, (2016) https://openfoam.org/version/4.0/
[3] OpenFOAM Foundation, OpenFOAM-dev, (2014-2018) https://openfoam.org/version/dev/
[4] N. Kurul and M.Z. Podowski, 27th National Heat Transfer Conference, Minneapolis, USA, July 28–31, 1991.
[5] Anglart, H., Nylund, O., Kurul, N., & Podowski, M. Z. (1997). Nuc. Engineering and Design, 177(1-3), 215-228.
[6] Ishii, M., Kim, S., & Kelly, J. (2005). Nuclear Engineering and Technology, 37(6), 525-536.
[7] Kumar, S., & Ramkrishna, D. (1996). Chemical Engineering Science, 51(8), 1311-1332.
[8] Liao, Y., Oertel, R., Kriebitzsch, S., Schlegel, F., & Lucas, D. (2018). Int. J. Num. Meth. Fluids, 87(4), 202-215

  • Vortrag (Konferenzbeitrag)
    18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), 18.-23.08.2019, Portland, USA
  • Beitrag zu Proceedings
    18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), 18.-23.08.2019, Portland, USA
    Proceedings of NURETH-18

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