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

1
PUMA Purdue University Multi-Dimensional
Integral Test Assembly Scientific Design of the
Scaled Facility for GE SBWR DesignSBWR
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

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

4
(No Transcript)
5
ICONA Intelligent re-Construction of Visual
Information for On-line Nuclear Safety
Applications
Churn Flow
Slug Flow
Bubbly Flow