Post on 31-Dec-2015
description
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