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Investigations of Domestic Radioactive Raw Materials, Beryllium, and Other Trace Elements Monthly Report: March 1949
Monthly report of the U.S. Geological Survey's trace element investigations including an outline of field work, laboratory work, and staff activities that have been completed or are in process.
Date:
1949-04~
Creator:
Geological Survey (U.S.). Trace Elements Office.
System:
The UNT Digital Library
Corrosion Tests on Carboloy in Redox Process Solutions
Introduction: Static, total immersion corrosion tests were carried out at room temperatures with Carboloy grades 44-A, 78, 907, X-3119-A and X-3119-B in Redox process solutions (ANL, June 1, 1949 Flowsheet) 1AX, 1AF, and 1AS.
Date:
April 6, 1949
Creator:
Koenig, W. W.
System:
The UNT Digital Library
The solvent-extraction performance of small scale redox IA columns using Fenske helix packing, ammonium nitrate salting agent, and unirradiated uranium
A report which deals with the Redox IA Column studies made in small-scale columns packed with 3/16-in. Fenske helices and using NH4NO3 salting agent.
Date:
April 13, 1949
Creator:
Woodfield, F. W.; Bradley, J. G.; Switzer, W. O. & Merrill, E. T.
System:
The UNT Digital Library
The Critical Mass of a Spherical Reactor with Variable Intrinsic Buckling
Abstract: "The critical mass both of an untamped and water-tamped sphere with parabolic radial variation of the intrinsic buckling is calculated by a perturbation method. The result is applied to finding the minimum critical mass of plutonium in water suspension with infinite water temper; the calculations show that the minimum critical mass at constant concentration may be reduced by an amount of the order of 7.6% when the concentration of plutonium is permitted to vary throughout the suspension."
Date:
April 28, 1949
Creator:
Muller, G. M.
System:
The UNT Digital Library
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
The Machinability of Beryllium
The following report investigates the isolation of the cause of the unusual tool-wear rates found in machining beryllium as attributed to an inherent characteristic of beryllium, or an effect of inclusions in beryllium, as well as the evaluation of the comparative machinability of the various types of beryllium.
Date:
April 30, 1949
Creator:
Armstrong, E. T.; Dayton, Russell Wendt & Dawes, R. C.
System:
The UNT Digital Library