Calibration of the liquid-level detector for steam-water facility is complete from 600 to 2000 psig. Permissible steam release rates for 24 and 36 inches above the interface are established for the test pressures. The correlalation equation which relates steam void fraction to basic system parameters is further refined to include ail the data from this program as well as from the low-pressure steam-water facility. By addition of another dimensionless term to the equation it is possible to extend the equation to include the radial gradient in the void fraction. Collection of carryunder in the downcomer region of the natural separation reactor mockup is complete. From this data it is possible to establish an equation for the downcomer slip ra...
Reprinted from Symposium on Steam Quality. Special Technical Publication no. 192, American Society f...
Tests are described to determine the amount of entrained moisture occurring in the steam of the Path...
International audienceComputational fluid dynamics (CFD) research for nuclear reactor safety dedicat...
Installation of the test equipment and checkout of the steam-water test facility's controls for the ...
For purposes of analysis and experiment the centrifugal type downflow separator was divided into the...
A full-scale novel conical swirl-vane steam separator with a conical barrel is studied by test and n...
The phenomenon of carryover, i.e entrainment of liquid along with separated steam is observed in all...
The pressure drop of a moisture separator in a steam generator is the important design parameter to ...
The nuclear fusion reactor ITER (International Thermonuclear Experimental Reactor) foresees a Pressu...
The main aim of the current work is to increase operation efficiency and reliability of moisture sep...
Citation: Whipple, James Halley and Seaton, Roy A. Tests of the efficiency of steam separators. Seni...
The nuclear fusion reactor ITER (International Thermonuclear Experimental Reactor) foresees a Pressu...
In any conceptual reactor design under postulated accidental conditions, one parameter that is consi...
In normal operation, there is no significant thermal stratification phenomenon in the tube bundle ar...
Access restricted to the OSU CommunityIn any conceptual reactor design under postulated accidental c...
Reprinted from Symposium on Steam Quality. Special Technical Publication no. 192, American Society f...
Tests are described to determine the amount of entrained moisture occurring in the steam of the Path...
International audienceComputational fluid dynamics (CFD) research for nuclear reactor safety dedicat...
Installation of the test equipment and checkout of the steam-water test facility's controls for the ...
For purposes of analysis and experiment the centrifugal type downflow separator was divided into the...
A full-scale novel conical swirl-vane steam separator with a conical barrel is studied by test and n...
The phenomenon of carryover, i.e entrainment of liquid along with separated steam is observed in all...
The pressure drop of a moisture separator in a steam generator is the important design parameter to ...
The nuclear fusion reactor ITER (International Thermonuclear Experimental Reactor) foresees a Pressu...
The main aim of the current work is to increase operation efficiency and reliability of moisture sep...
Citation: Whipple, James Halley and Seaton, Roy A. Tests of the efficiency of steam separators. Seni...
The nuclear fusion reactor ITER (International Thermonuclear Experimental Reactor) foresees a Pressu...
In any conceptual reactor design under postulated accidental conditions, one parameter that is consi...
In normal operation, there is no significant thermal stratification phenomenon in the tube bundle ar...
Access restricted to the OSU CommunityIn any conceptual reactor design under postulated accidental c...
Reprinted from Symposium on Steam Quality. Special Technical Publication no. 192, American Society f...
Tests are described to determine the amount of entrained moisture occurring in the steam of the Path...
International audienceComputational fluid dynamics (CFD) research for nuclear reactor safety dedicat...