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

2. 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
PUMA PROGRAM

3. 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

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