On the validity of the two-fluid model for simulations of bubbly flow in nuclear reactors
Paper in proceedings, 2014

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.

Author

Henrik Ström

Chalmers, Applied Mechanics, Fluid Dynamics

Srdjan Sasic

Chalmers, Applied Mechanics, Fluid Dynamics

Klas Jareteg

Chalmers, Applied Physics, Nuclear Engineering

Christophe Demaziere

Chalmers, Applied Physics, Nuclear Engineering

Proceedings of the 13th International Conference on Multiphase Flow in Industrial Plants (MFIP-13)

Driving Forces

Sustainable development

Subject Categories

Other Engineering and Technologies

Energy Engineering

Chemical Engineering

Fluid Mechanics and Acoustics

Areas of Advance

Energy

Roots

Basic sciences

Infrastructure

C3SE (Chalmers Centre for Computational Science and Engineering)

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Created

10/8/2017