Abstract
The two-fluid model is widely used in the current two-phase flow analysis codes, such as nuclear reactor safety analysis codes RELAP5, TRAC, and CATHARE. In the conventional model, the interfacial area concentration is given by empirical correlations. The correlations are based on two-phase flow regimes and regime-transition criteria that do not dynamically represent the changes in interfacial structure. There exist the following shortcomings caused by this static approach.
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© 2006 Springer Science+Business Media, Inc.
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Ishii, M., Hibiki, T. (2006). Constitutive Modeling of Interfacial Area Transport. In: Thermo-Fluid Dynamics of Two-Phase Flow. Springer, Boston, MA. https://doi.org/10.1007/978-0-387-29187-1_11
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DOI: https://doi.org/10.1007/978-0-387-29187-1_11
Publisher Name: Springer, Boston, MA
Print ISBN: 978-0-387-28321-0
Online ISBN: 978-0-387-29187-1
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