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PUMA PROGRAM

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

  2. 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

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

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