PUMA : Purdue University Multi-Dimensional Integral Test Assembly Scientific Design of the Scaled Facility for GE SBWR Design SBWR : Simplified Boiling Water Reactor

PUMA PROGRAM OBJECTIVES: To assess the integral performance of safety systems (GDCS and PCCS). To assess relevant SBWR phenomena important to Loss Of Coolant Accidents (LOCAs) and other transients. ON-GOING EXPERIMENTS Integral Effect Test Main steam line break Bottom head drain line break GDCS injection line break Separate Effect Test Direct contact condensation

THERMAL-HYDRAULICS AND REACTOR SAFETY LABORATORY The TRSL performs researches in: Reactor safety experiments and analysis Flow visualization and virtual flow visualization Two-phase flow modeling and local instrumentation development Global and industrial two-phase flow diagnostic systems Two-phase flow computational code development Graphical user interface development

ICONA: Intelligent re-Construction of Visual Information for On-line Nuclear Safety Applications Bubbly Flow Slug Flow Churn Flow