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Poster De Conférence Année : 2023

CFD simulations of boiling flows in nuclear reactor conditions

Résumé

Despite decades of work in the thermal hydraulics community, modeling interfacial area in boiling bubbly flows remains a challenge for multiphase CFD. However, bubble diameters are required for many momentum and heat transfer closures. Simulating flows without access to experimental bubble diameters is therefore difficult. This is problematic for design applications or extreme conditions as in Pressurized Water Reactors (PWR's). Here, we build a two-fluid CFD framework to compare different approaches to interfacial area. We select momentum closures, implement them in an open-source code and validate them using experiments with known bubble diameters. In the medium-term, we will compare interfacial area transport equations.
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Dates et versions

cea-04456457 , version 1 (14-02-2024)

Identifiants

  • HAL Id : cea-04456457 , version 1

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Corentin Reiss, Antoine Gerschenfeld, Catherine Colin. CFD simulations of boiling flows in nuclear reactor conditions. ICMF 2023 - The 11th International Conference on Multiphase Flow, Apr 2023, Kobe, Japan. , 2023. ⟨cea-04456457⟩
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