主讲人 : Caleb Brooks
The two-fluid model has long been the backbone of thermal hydraulics calculations for the nuclear power industry and increasingly relied upon for determination of safety margin, course of accident progression, and design of new reactor concepts and safety systems. It is important to provide an accurate constitutive relation for the interfacial area concentration to solve the two-fluid model. The implementation of the interfacial area transport equation into thermal-hydraulic system analysis codes has been recommended to improve prediction capability and solve current shortcomings. These shortcomings include inability to simulate the dynamic changes in interfacial structure across flow regimes and in developing flow, significant compound errors stemming from the two-step flow regime d method, possible numerical oscillation, and limited applicable range of interfacial area correlations. The interfacial area transport equation can replace the traditional flow regime maps and regime transition by mechanistically predicting the changes in the two-phase flow structure through modeling the effects of the boundary conditions and flow development. This presentation will detail the development of the Interfacial Area Transport Equation from a historical perspective and provide the road map for future work.