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Preprints, Working Papers, ... Year : 2024

A Diameterless Boiling-Flow Multiphase CFD Framework for Nuclear Reactor Conditions

Abstract

We develop a two-fluid Euler-Euler CFD framework based on the PolyMAC numerical scheme in CEA’s open-source TrioCFD code. Interfacial momentum closure terms are selected and validated using bubbly adiabatic experiments on vertical flows. The local experimental bubble diameter is enforced to avoid the use of interfacial area closures. Independently, it is shown that in a high-pressure developed boiling pipe flow, changing the entrance temperature while measuring flow characteristics at the outlet is equivalent to changing the distance from the inlet where the flow characteristics are measured. This enables us to simulate the DEBORA experiment, an ascending boiling R12-freon flow in a tube, using a 3D map of the experimental diameter. Atmospheric-pressure closure terms are shown not to be able to reproduce measured void fraction profiles. We propose a new set of closures that is based on the hypothesis that bubbles are deformable in nuclear reactor conditions. This enables us to avoid bubble diameter modeling through an interfacial area transport equation or population balance model, as in system-scale codes extensively used in the nuclear industry. Void fraction predictions are improved compared with the baseline set of closures.
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hal-04527149 , version 1 (29-03-2024)

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  • HAL Id : hal-04527149 , version 1

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Corentin Reiss, Antoine Gerschenfeld, Catherine Colin. A Diameterless Boiling-Flow Multiphase CFD Framework for Nuclear Reactor Conditions. 2024. ⟨hal-04527149⟩
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