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PUMA : Purdue University Multi-Dimensional Integral Test Assembly Scientific Design of the Scaled Facility for GE SBWR Design SBWR : S implified B oiling W ater R eactor. OBJECTIVES: To assess the integral performance of safety systems (GDCS and PCCS).

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PUMA : Purdue University Multi-Dimensional Integral Test AssemblyScientific Design of the Scaled Facility for GE SBWR DesignSBWR : 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

PUMA PROGRAM
thermal hydraulics and reactor safety laboratory
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
ICONA: Intelligent re-Construction of Visual Information for On-line Nuclear Safety Applications

Churn Flow

Slug Flow

Bubbly Flow

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