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Extrusion Cladding of Fuel Element

Description: From introduction: "This investigation was undertaken with the general objective of determining whether uranium core could be sheathed with aluminum by an extrusion-cladding process. The ultimate objective of this work was to determine the feasibility of extrusion cladding flat plates of uranium."
Date: March 22, 1955
Creator: Slunder, C. J.; Fiorentino, R. J. & Hall, A. M.
Partner: UNT Libraries Government Documents Department
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Aluminum Cladding Long Uranium Plates by Solid-State Bonding

Description: From introduction: This report covers an investigation of solid-state bonding as a technique for aluminum cladding uranium plates of 3 by 0.180-in. cross section in lengths up to 14 ft.
Date: March 29, 1955
Creator: Saller, Henry A.; Dickerson, R. F. & Carlson, R. J.
Partner: UNT Libraries Government Documents Department
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Electrodeposition of Aluminum on Uranium

Description: Abstract: "Aluminum electroplating was studied in a search for new methods of cladding uranium fuel elements. Uranium electroclad with 12 mils of aluminum over a 0.5-mil (or nickel plus copper) electroplate resisted corrosion for more than 100 hr in boiling water. This quality of protection was effected by hot pressing the electroclad uranium with 5.1 tons per sq in. for 5 min at 950 F. The electroclad uranium with hot-pressed samples paralleled those of later experiments with hot-pressed wroug… more
Date: March 30, 1955
Creator: Beach, John G.; Schickner, William C.; Hopkinson, Dolores. & Faust, Charles L.
Partner: UNT Libraries Government Documents Department
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The Preparation of Large-diameter Zirconium Crystal Bar by the De Boer Process

Description: This report discusses the production of large-diameter zirconium crystal bars in a 16 inch diameter, Hastelloy B, de Boer unit in order to increase production efficiency.
Date: March 6, 1951
Creator: Bulkowski, H. H.; Beale, L. C.; Sebenick, J. J.; Campbell, Ivor E. & Gonser, B. W.
Partner: UNT Libraries Government Documents Department
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Hydroxides as Moderator Coolants in Power-Breeder-Reactors

Description: The following report describes work that was udertaken to determine whether a homogeneous breeder reactor using an alkili metal hydroxide solution is capable of breeding.
Date: March 26, 1952
Creator: Dayton, Russell Wendt & Chastain, Joel W.
Partner: UNT Libraries Government Documents Department
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The Fabrication of Stainless Steel-Uranium Dioxide Fuel Elements

Description: Abstract: "Stainless steel-clad fuel sheet 0.020 in. thick with a 0.008-in. core of stainless steel plus UO2 was produced by roll cladding a powder metal compact. The effects of processing variables, core-matrix composition, quantity of oxide, and oxide particle size on the properties of the sheet were investigated. The strength and ductility of the core decreased sharply as the quantity of oxide in the core increased from 20 to 40 w/o. Over the range of matrix compositions investigated the par… more
Date: March 2, 1954
Creator: Keeler, J. R.; Keller, D. L. & Cuddy, L. J.
Partner: UNT Libraries Government Documents Department
open access

Progress Report for the Month of February, 1952

Description: This progress report of the Battelle Memorial Institute covers information in many categories for February, 1952. These include development of ceramic fuel elements, general ceramics, uranium and its alloys, thorium and its alloys, development of metallic fuel elements and assemblies, metals and alloys for reactor components, miscellaneous metallurgical work, liquid coolants and fuels, reactor engineering studies, and mechanism development.
Date: March 1, 1952
Creator: Russell, H. W.; Nelson, H. R. & Dayton, Russell W.
Partner: UNT Libraries Government Documents Department
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