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An Application of the Concepts of Particle Packing to the Consolication of Silicon Carbide Powders

Description: From introduction: Silicon carbide is being considered as a basis material for nonmetallic fuel elements because of its high thermal conductivity, low nuclear cross section, high resistance to thermal rupture, and high degree of stability at high temperature in air. A requirement of the fuel elements is that they be thin and have as low porosity as possible. One shape of element under consideration is 0.050 to 0.070 inch thick by a few inches in width and breadth.
Date: August 15, 1952
Creator: Harman, Cameron G.; Shinn, J., Jr. & Wagner, H. E.
Partner: UNT Libraries Government Documents Department
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Hydrogen Embrittlement of Zirconium

Description: Abstract: "The amount of hydrogen normally present in zirconium and zirconium alloys suffices to reduce their ductility greatly in an impact test at room temperature, after slow cooling from 600 F. Quenching from 600 F or above gives high impact strength, as does removal of hydrogen by high-temperature vacuum annealing. This report discusses the evidence on hydrogen embrittlement, the diffusion, solid solubility, and equilibrium pressure of hydrogen of hydrogen in zirconium, the microstructure,… more
Date: August 22, 1952
Creator: Dayton, Russell Wendt; Schwope, A. D.; Muehlenkamp, G. T.; Saller, Henry A.; Dickerson, R. F.; Schwartz, C. M. et al.
Partner: UNT Libraries Government Documents Department
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The Fabrication of Subassemblies for the Supercritical-Water Reactor

Description: In studies of the fabrication of fuel subassemblies for the supercritical-water reactor, the limited ductility of stainless steel-UO₂ fuel sheet made the fabrication of corrugated-flat-plate-type subassemblies impractical. A fabricable MTR-type assembly, 5/8 in. square and 30 in. long, was developed. Methods for edge cladding fuel sheet were developed and a brazing alloy, GE-75, was found to be corrosion resistant in supercritical water.
Date: August 16, 1954
Creator: Keeler, J. R. & Hare, Alan W.
Partner: UNT Libraries Government Documents Department
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Enamels and Enameling Techniques for Coating Uranium Slugs

Description: From introduction: "This report describes research on the development of compositions and techniques for porcelain enameling uranium fuel slugs used in Hanford production reactors."
Date: August 2, 1955
Creator: Tripp, Harlan P.; Schultz, John; King, Burnham William, 1907- & Duckworth, Winston H.
Partner: UNT Libraries Government Documents Department
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The Kinetics of the Zirconium-Uranium Dioxide Reaction

Description: This report discusses three experimental methods used to study the kinetics of the reaction between zirconium and UO2.
Date: August 15, 1955
Creator: Mallett, Manley William, 1909-; Gerds, Arnold F.; Lemmon, Alexis W. & Chase, Dan L.
Partner: UNT Libraries Government Documents Department
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MoSi₂-UO₂ Ceramics for High-Temperature Fuel Elements

Description: This report follows a study that was aimed at the collection of experimental data needed to estimate the maximum safe temperatures and dispersed UO2 contents for MoSi2--UO2 fuel elements exposed to air.
Date: August 18, 1955
Creator: Gambino, John R.; Quirk, John F. & Duckworth, Winston Howard
Partner: UNT Libraries Government Documents Department
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Eddy-Current Inspection of a Possible PWR Fuel Element

Description: The following report follows the inspections of a number of eddy-current instrument procedures. The objectives of these tests were to detect both weld defects and lack of integrity of the body of the fuel elements.
Date: August 22, 1955
Creator: Stutz, David E.; Gibbs, Richard L.; Dickerson, Ronald F. & Wenk, Samuel A.
Partner: UNT Libraries Government Documents Department
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Enamels for the Protection of Aluminum Cans for Uranium Slugs

Description: The following report examines the most suitable enamels recommended for protection of aluminum slug cans.
Date: August 31, 1955
Creator: Schultz, John; Tripp, Harlan P.; King, Burnham William, 1907- & Duckworth, Winston H.
Partner: UNT Libraries Government Documents Department
open access

Development of Cermet Fuel Elements

Description: Abstract: "Fabrication techniques for making metal-ceramic fuel elements containing 60 to 90 volume per cent of UN or UO2 in a Type 302B stainless steel matrix was investigated. A hot press-forging procedure was most successful for fabricating fuel cores with a density of 90 per cent of theoretical or better. This procedure consisted of sealing the cold-pressed core compacts in stainless steel picture-frame packs, heating to 1900 F, and pressing to a total reduction in thickness of 35 per cent.… more
Date: August 11, 1958
Creator: Paprocki, Stan J.; Keller, Donald L.; Cunningham, G. W. & Kizer, Donald E.
Partner: UNT Libraries Government Documents Department
open access

Extrusion Cladding of Uranium Fuel Plates

Description: The following report describes two methods of extrusion cladding of uranium fuel plates that were investigated and evaluated.
Date: August 22, 1958
Creator: Fiorentino, Robert J.; Drennen, David C.; Slunder, Charles J. & Hall, A. M.
Partner: UNT Libraries Government Documents Department
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