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A Comparative Analysis of the Liquid Metal Heat Transfer Systems for WMA
Introduction. As stated in Report KAPL 116, one of the objectives of the KAPL reactor is "to provide a prototype demonstration of the practical general of electrical power from Nuclear energy using molten sodium as the primary coolant. The reactor will generate steam at a temperature of 550 degrees F and 465 psia, including 90 degree superheat potentially capable of an efficiency of twenty-eight per cent in electrical output." The work reported here is intended to increase the scope and supply an independent check on the heat transfer system analysis that has previously been done. The purpose of these analyses is to investigate the effects on load rating and top reactor temperature.
Date:
April 29, 1949
Creator:
Selby, J. D.
System:
The UNT Digital Library
Corrosion of Zircaloy in Crevices under Nucleate Boiling Conditions
Abstract: The MSAR corrosion test loop was used to study the effect of VKE-shaped crevices on the corrosion resistance of Zircaloy under boiling heat-transfer condtions in both ammoniated and lithiated water at pH 10.5.
Date:
April 1962
Creator:
Anderson, W. Kermit & McGoff, M. J.
System:
The UNT Digital Library
Mechanical Properties of Zircaloy-2 Weld Metal
Abstract: Zircaloy-2 weld metal, obtained by inert gas non-consumable-electrode welding, was subjected to tensile, strain fatigue, and creep-rupture testing.
Date:
April 15, 1961
Creator:
Beitscher, S.
System:
The UNT Digital Library
Physical Properties of High Density Concrete
The purpose of this report is to summarize the work done at KAPL on physical properties of high density concretes.
Date:
April 10, 1950
Creator:
Blinder, W.
System:
The UNT Digital Library