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On the validity of the two-fluid model for simulations of bubbly flow in nuclear reactors

Henrik Ström (Institutionen för tillämpad mekanik, Strömningslära) ; Srdjan Sasic (Institutionen för tillämpad mekanik, Strömningslära) ; Klas Jareteg (Institutionen för teknisk fysik, Nukleär teknik) ; Christophe Demazière (Institutionen för teknisk fysik, Nukleär teknik)
Proceedings of the 13th International Conference on Multiphase Flow in Industrial Plants (MFIP-13) (2014)
[Konferensbidrag, refereegranskat]

In the present work, we formulate a simplistic two-fluid model for bubbly steam-water flow existing between fuel pins in nuclear fuel assemblies. Numerical simulations are performed in periodic 2D domains of varying sizes. The appearance of a non-uniform volume fraction field in the form of meso-scales is investigated and shown to be varying with the bubble size as well as the domain size. In addition, the predictions from the two-fluid model are compared against the results from a dense Eulerian-Lagrangian particle-in-cell model in which the motion of individual bubbles are resolved in a Lagrangian frame of reference. The results obtained in this work contribute to a rigorous foundation in on-going efforts to derive a consistent meso-scale formulation of the traditional two-fluid model for multiphase flows in nuclear reactors.

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Denna post skapades 2014-09-24. Senast ändrad 2015-05-08.
CPL Pubid: 203210