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Metallurgy Division Quarterly Progress Report for Period Ending October 31, 1950

Description: Technical report outlining the rate of production of modified MTR type fuel elements for the Bulk Shielding Facility has proceeded. Includes compatibility test that were started as a guide in the selection of materials suitable for fuel-element fabrication. [From Summary]
Date: February 8, 1951
Creator: Frye, J. H.; Miller, E. C. & Bridges, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending December 10, 1950

Description: Technical report detailing expansion of the Aircraft Nuclear Propulsion at the Oak Ridge National Laboratory. Major facilities completed at this time were the Shielding Rector, the ANP Critical Facility, and the 86-in. Cyclotron. Outlines further need for radiation damage studies. [From Summary]
Date: February 27, 1951
Creator: Briant, R. C.; Ellis, C. B. & Cottrell, W. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calorimetric Calibration of a Graphite Walled, Cavity-Type Ionization Chamber

Description: Technical report outlining cavity-type ionization chambers with graphite walls that are used to measure heat dissipation in the graphite reflector of the MTR mock-up. Studies the relationship between the ionization occurring in the chamber and the heat generated in the surrounding graphite medium. [From Abstract]
Date: January 23, 1951
Creator: Jenks, G. H.; Breazeale, W. M. & Hairston, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Studies on the Removal of Radioisotopes From Liquid Wastes by Coagulation

Description: Technical report covering work completed on the removal of radioisotopes from water using a calcium phosphate floc as a carrier. This research was performed as part of the Health Physics Waste Disposal Research Section work on the removal of small quantities of radioactivity from large volumes of water. [From Abstract]
Date: January 23, 1951
Creator: Lauderdale, Robert A., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Corrosion of Various Stainless Steels in Synthetic Waste Solutions

Description: Technical report describing the tests on types 309, 316, and 347 stainless steel. These steels were tested for a total of 779 to 828 hours in three different synthetic waste solutions. Results shoe that the best all-around corrosion resistance to the test conditions was exhibited by 316 stainless steel, but in one solution 347 stainless steel was more resistant. [From Abstract]
Date: February 12, 1951
Creator: English, James L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Study of a Uranium - Bismuth Liquid Fuel Power Reactor L. F. R . 2

Description: Technical report and preliminary design calculations describing a type of liquid fuel reactor adaptable for production or breeding on a U-233 cycle based on data at Brookhaven National Laboratory. Describes design calculations for generating significant amounts of power and neutrons by use of uranium-bismuth solutions with fused salts in the reactor system.
Date: April 27, 1951
Creator: Gurinsky, D. H.; Kaplan, I.; Miles, F. T.; Williams, C. & Winsche, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Continuous Fission Product Separation Process; I. Removal of the Rare Earths (Lanthanum Cerium, Praseodymium, and Neodymium) From a Typical Liquid Bismuth-Uranium Reactor Fuel by Contact with Fused LiCl-KCl Mixtures

Description: Technical report investigating the distribution of rare earth elements between a liquid bismuth-uranium solution and fused KCI-LiCi mixtures. Report warrants further research on the liquid bismuth-uranium-fused salt system due to the benefit of continuous fission removal processes.
Date: July 1, 1951
Creator: Bareis, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Progress Report of Reactor Science and Engineering Department; July 1 - September 30, 1951

Description: Technical report covering the classified tests on two types of nuclear reactors of the Department of Reactor Science and Engineering. Outlines tests on heat transfer and hydraulics, fabrication and corrosion studies on the normal water.
Date: 1951
Creator: Brookhaven National Laboratory
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plate Efficiency in the Exchange of Deuterium Between Ammonia and Hydrogen

Description: Technical report outlining measurements of the equilibrium in the exchange of deuterium between ammonia and hydrogen and of the kinetics of this reaction. Details a series of tests carried out to measure Murphree plate efficiencies.
Date: December 3, 1951
Creator: Perlman, Morris L. & Bigeleisen, Jacob
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Concentration of Deuterium by Chemical Exchange Between Hydrogen and Ammonia

Description: Technical report describing the results of the chemical reaction between potassium amide and liquid ammonia and the exchange of hydrogen between hydrogen gas and liquid ammonia. This report finds that the reactions may be sufficiently rapid to be useful for isotope separations on a larger scale.
Date: December 15, 1951
Creator: Perlman, M. L. & Bigeleisen, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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