The laboratory performs experimental and computational studies on various multiphase flow and reactor thermal-hydraulics topics. In the first area, we study the full spectrum of two-phase flow regimes that are of practical interest, ranging from bubble nucleation to film and droplet dynamics. Research activities include advanced instrumentation development, experimental studies, and model development for both 1-D system codes and 3-D CFD codes. In the area of reactor thermal-hydraulics, the focus is on reactor safety related issues. Specific topics include air entrainment in the Emergency Core Cooling System, flow structure development in rod bundles, flow induced vibration on piping elements, passive safety systems, and spent fuel pool safety.