Abstract

In relation to recent V & V standard stream, accurate benchmark of two-phase flow CFD (Computational Fluid Dynamics) using interfacial area transport equation is indispensable to validate the interfacial area transport equation, interfacial force models and two-phase flow turbulence models. This is particularly true for future detailed three-dimensional nuclear reactor core analysis. This paper intends to provide the state-of-the-art review on the two-phase flow CFD using the interfacial area transport equation. This paper discussed the basics of two-group interfacial area transport equation and component sink and source terms of interfacial area concentration such as bubble interaction terms and wall nucleation term. Brief overviews of interfacial force models and two-phase flow turbulence models are also provided. Due to the importance of databases for benchmarking two-phase flow CFD using the interfacial area transport equation, databases utilized for the CFD simulations have been summarized. A critical review has been conducted for vertical upward two-phase flow CFD simulations for adiabatic bubbly flows, boiling bubbly flows and adiabatic flows in cap-bubbly, cap-turbulent and churn-turbulent flow regimes. The review of extensive existing two-phase flow CFD using the interfacial area transport equation provides the state-of-the-art knowledge of the advancement and the current status of the two-phase flow CFD and its limitation at present. Although extensive efforts have been made for benchmarking the two-phase flow CFD using the interfacial area transport equation in the past decade, further efforts to improve the prediction accuracy of the two-phase flow CFD should be made for general use. Some discussions for future research directions are given.

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