Thermal-hydraulics in nuclear reactors involves both single-phase and multiphase flows. In particular, gas-liquid two-phase flow plays a critical role in reactor design and safety analysis, while posing significant challenges for accurate prediction. We develop high-fidelity numerical analysis codes to simulate such complex multiphase flow phenomena.
As a detailed thermal-hydraulics analysis code, it handles thermal-hydraulics behavior of multiple fluids with free surfaces.
Open-source code available!!
An interface-resolved two-phase flow solver that directly captures the motion and deformation of gas-liquid interfaces.
A three-dimensional two-fluid model code that enables efficient simulation of two-phase flows over a wide range of conditions using constitutive models and void fraction transport.