Research on interfacial area transport : the present and future efforts

In the current nuclear reactor system analysis codes, the interfacial area concentration in the two fluid model is given by empirical correlations that are based on the two-phase flow regimes and regime transition criteria. Due to its inherent shortcomings, such approach not only presents various problems in the numerical analysis, but also inaccurate. In view of this, a new dynamic approach employing the interfacial area transport equation has been studied. It is expected that the interfacial area transport equation can make a leapfrog improvement in the current capability of the two-fluid model from both scientific and practical point of view. This paper discusses the current status and proposes future direction in the development of interfacial area transport equation. The one-group and two-group interfacial area transport equations that are available at the present time are reviewed to address the feasibility and reliability of the model. Based on the status and assessment of the current model, some suggestions are made for the future efforts in the development of interfacial area transport equation