PUMA : Purdue University Multi-Dimensional Integral Test Assembly
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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 PROGRAM

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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


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

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

Churn Flow

Slug Flow

Bubbly Flow


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