PUMA : Purdue University Multi-Dimensional Integral Test Assembly

Scientific Design of the Scaled Facility for GE SBWR DesignSBWR : Simplified Boiling Water Reactor

The Next Generation BWRs:

• Power generation costs cheaperthan those of coal

• Plant safety systems simpler thancurrent design

• Shorter construction schedules

• Electrical rate in 600MW range

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

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

FLOW VISUALIZATIONWITH ADVANCED TWO-PHASE INSTRUMENTATIONExperimental data obtained with the

non-intrusive multi-electrodeimpedance void meter is used as theinput for a neurofuzzy diagnosticsystem designed for flowvisualization and flow regimeidentification.

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ICONA: Intelligent re-Construction of Visual Information for On-line Nuclear Safety Applications

Impedance Sensor

Neurofuzzy Modules

Virtual Flow Visualization

Flow

Virtu a l Flo w Visu a liza tio n

Vi r t ual Fl ow Vi sual i z at i on

Bubbly Flow

Slug Flow

Churn Flow