Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
9824432 | Annals of Nuclear Energy | 2005 | 14 Pages |
Abstract
Bubbly flows are relevant in nuclear reactors thermalhydraulics and safety analysis. Regularly, empirical constitutive laws are required to close the two-fluid equations, particularly in relating the interfacial area and the bubble number densities to the local void fraction. In this article, starting from a generalized Boltzmann transport equation for the bubble size spectrum, a convection equation for the bubble number density is derived using the method of moments. The equation is analyzed for a vertical bubbly flow in stagnated liquid, showing excellent agreement with experimental data. The model is useful as a mean to provide conservation-based correlations to complement the existing two-fluid models.
Related Topics
Physical Sciences and Engineering
Energy
Energy Engineering and Power Technology
Authors
M. Giménez, A. Clausse,