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The system consisted of a pressure vessel with simulated reactor internals, an intact loop with a steam generator, pump, and pressurizer, a blowdown loop with rupture assemblies, a simulated steam generator, and a simulated pump and a pressure suppression system with a suppression tank and header. The semiscale apparatus was designed to simulate a 100% double-ended offset shear of the cold leg of a pressurized water reactor to investigate the system response to a Loss of Coolant Accident (LOCA). The break areas in Test lOll were reduced by 20% so that the system behavior would be significantly different from the previous semiscale tests.
1 1/2 Loop Semiscale System consisted of a pressure vessel with internals, including 9 electrically heated fuel rod simulators;
1 intact loop with steam generator, simulated pump and bypass line
1 broken loop simulator
emergency core cooling injection system
volume to break area equal to volume to break area of a large PWR
other parameters not scaled, facility should only yield data for comparison to analyses
Parameters offered for Comparison:
2 pressures ( upper plenum and upstream break nozzle) ; containment pressure
4 differential pressures (hot leg-cold leg, across pump, pressure vessel containment)
6 local fluid densities
7 flow rates and including break flow
time to start high pressure injection system (HPIS) and low pressure injection system (LPIS)
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Keywords: data, isothermal, loss-of-coolant accident, primary coolant loop.