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The Influence of a Precipitation Hardening Heat Treatment on the Hardness of Several Uranium-Molybdenum Alloys

Description: Four uranium alloys containing nominally 0.5, 1.0, 1.5, and 2.0 w/o molybdenum were investigated with respect to their response to hardening by heat treatment. The several alloys were heated at elevated temperatures to secure solid solution, then quenched and reheated at lower temperatures to obtain hardening. The procedure followed the well known industrial practice of solution treatment and precipitation hardening. The results showed that all the alloys could be hardened by a suitable heat tr… more
Date: August 1954
Creator: Jones, T. I.; Hoffman, C. G.; Taub, J. M.; Doll, D. T. & Montoya, F. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Teflon Bellows Pulse Generators for Solvent Extraction Pulse Columns

Description: The feasibility of using Teflon bellows as the pulsing device for solvent extraction pulse columns has been previously demonstrated by life test of various sizes of Teflon bellows. This report describes a compact Teflon bellows pulse generator and drive assembly which was designed, built, and tested by the Chemical Development Unit. The pulse generator assembly is suitable for a number of applications where pulse generators are required to pulse solvent extraction columns.
Date: January 1, 1954
Creator: McCarthy, P. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effects of Certain Variables Upon the Reactions for Preparation, by the Dry Method, of UF4 from U3O8

Description: The effects of certain process variables on the production of uranium tetrafluoride from U3O8 on the 250 g. (uranium) scale, and smaller scales in a few cases, have been studied. It was found that the initial step (reduction of U3O8 to UO2 by hydrogen) is essentially complete in 15 minutes at 700 degree C. The rate of conversion was shown to be temperature dependent, the greatest increase in rate of conversion occurring in the vicinity of 500 degree C. In the conversion of UO2 to UF4 by hydroge… more
Date: November 1954
Creator: Fry , O. E. & Kewish , R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Investigation of Materials for a Water Cooled and Moderated Reactor [Secret Version]

Description: An investigation of the materials for use in the water-moderated and cooled Aray Package Power Reactor (APPR) operating at about 500°F was made. The available literature was analyzed, and the results of the different investigators were compared and averaged. Twenty different materials, including stainless steels, nickel alloys, Stellites and others, were investigated from the point of view of physical properties, susceptibility to radiation damage, and corrosion resistance. Corrosion rates were… more
Date: August 1954
Creator: Scheib, Louis
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Metallurgy Division Quarterly Report January, February, and March 1954

Description: This quarterly report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses water cooled reactors, liquid metal cooled reactors, reactor development metallurgy, basic metallurgy, applied metallurgy, and aqueous corrosion.
Date: March 31, 1954
Creator: Foote, Frank G. (Frank Gale), 1906- & Schumar, James F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Investigation of Materials for a Water Cooled and Moderated Reactor [Declassified Version]

Description: An investigation of the materials for use in the water-moderated and cooled Aray Package Power Reactor (APPR) operating at about 500°F was made. The available literature was analyzed, and the results of the different investigators were compared and averaged. Twenty different materials, including stainless steels, nickel alloys, Stellites and others, were investigated from the point of view of physical properties, susceptibility to radiation damage, and corrosion resistance. Corrosion rates were… more
Date: August 1954
Creator: Scheib, Louis
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Soduim Graphite Reactor, Quarterly Progress Report, September-November 1953

Description: "For a central station reactor power plant of the sodium-graphite type, two designs have been investigated. The first operates as a converter using slightly enriched uranium fuel and produces 150 electrical megawatts. The second operates as a thermal breeder using a U233-Th alloy fuel and produces 300 electrical megawatts. Consideration has also been given to the problem associated with the design and operation of the Sodium Reactor Experiment. All work related to the plutonium plus power … more
Date: July 1, 1954
Creator: Inman, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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