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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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Electroplated Metals on Uranium for Aluminum Cladding

Description: Abstract: "Aluminum-clad nickel-plated uranium is corrosion resistant in boiling water. Samples with intentional defects in the aluminum-nickel clodding layers, after testing for more than 300 hr. showed no sign of rapid failure. The study of electroplated metals on uranium for aluminum cladding has defined the effects of several processing variables on the corrosion resistance. The quality of the uranium and the quality of the aluminum-nickel bond were important. Heat treatment and vacuum outg… more
Date: May 4, 1955
Creator: Beach, John G.; Schickner, William C.; Hopkinson, Dolores. & Faust, Charles L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Apparatus for visual study of corrosion by hot water

Description: Report describing an apparatus for visual study of corrosion of uranium by hot water. A windowed autoclave was designed and constructed to permit visual study of the reaction under conditions simulating a cladding failure in service.
Date: 1955
Creator: Grieser, Daniel R. & Simons, Eugene M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Grain Refinement of the As-Cast Uranium-5 w/o Chromium Alloy by Heat Treatment

Description: Introduction: "The uranium-5 w/o chromium alloy has been intensively investigated for use in a power reactor in the as-cast condition. However, when cast sample fuel elements were subjected to irradiation, their stability was found to be unsatisfactory. In order to improve the behavior of the alloy, a program of grain refinement by heat treatment was begun. The effect of chill casting on the heat-treated grain size was also investigated."
Date: May 13, 1955
Creator: Saller, Henry A.; Rough, Frank A. & Bauer, Arthur A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Low-Melting Alloys for Cast Fuel Elements

Description: The following report follows an investigation made to determine the composition of uranium-rich ternary eutectic alloys most suitable for reactor application in the as-cast condition. These determinations were made based metallographic examination and thermal analysis of as-cast alloys.
Date: May 19, 1955
Creator: Saller, Henry A.; Rough, Frank A. & Bauer, Arthur A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Annealing of crystal distortion in irradiated graphite

Description: From introduction: "As part of the program for improvement of graphite, the structural characteristics of graphite have been studied to determine the relation between physical and structural changes during irradiation."
Date: 1955
Creator: Austin, Alfred E. & Harrison, Ralph J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Ammonium Carbonate Pressure Leaching of Uranium Ores Proposed as Feed to the Pilot Plant at Grand Junction, Colorado : Progress Report

Description: From introduction: This is Progress report BMI-282, the first of a series covering the operation of the pressure-leaching towers for the extraction of uranium by an ammonium carbonate leach...This report discusses the data obtained from tests run to show the effects of such variables as the amount of air and carbon dioxide passed through the pulp, temperature, pressure, and concentration of ammonium carbonate and ammonium bicarbonate in the leach solution on the extraction of uranium.
Date: June 15, 1955
Creator: Wheeler, C. M.; Langston, B. G. & Stephens, F. M., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Properties and Heat Treatment of Zirconium-Uranium Alloys

Description: From Abstract: "The heat treatment and mechanical properties of four zirconium alloys...were investigated. Tensile, hardness, Jominy end-quench, and metallographic data constitute the basis for much of the report. Other data reported include the results of high-temperature creep, tensile, hardness, cold rolling, thermal-cycling, and dynamic-modulus tests." A connection is made between the behavior of these four alloys and more alloys in the zirconium-uranium system.
Date: January 10, 1955
Creator: Chubb, Walston; Muehlenkamp, G. T. & Manning, G. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Reactivity of Uranium and Blacosolv

Description: Abstract: "Blacosolv, trichloroethylene, is used in degreasing uranium metal. Tests were made under possible industrial conditions to determine whether a hazardous reaction between uranium and Blacosolv could occur. Temperature-rise measurements showed that there was no reaction of the metal, in various states of subdivision, with Blacosolv at temperatures up to 850 F. However, a reaction was observed in tests under which the finely divided metal, wet with solvent, was subjected to a severe imp… more
Date: January 21, 1955
Creator: Hannan, H. D.; Miller, P. D. & Peoples, R. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Composition of vapors from boiling nitric acid solutions

Description: From abstract: "The composition of vapors from aqueous nitric acid solutions boiling at 200 mm mercury total pressure is established for solutions containing between - and 67.5 w/o nitric acid. The volatility characteristics of low concentrations of chloride in the same concentration range of nitric acid have been measured in solutions boiling at 200 mm mercury. The effects of chloride concentration and pressure of boiling are evaluated. A spectrophotometric method of the determination of chlor… more
Date: February 9, 1955
Creator: Crooks, R. C.; Wilson, R. Q.; Bearse, A. E. & Filbert, Robert B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reaction of Hydrogen With Uranium

Description: Report discussing reaction of hydrogen with uranium in a range of temperatures and pressures. Experimental materials, methods and results are included.
Date: February 17, 1955
Creator: Albrecht, William M. & Mallett, Manley William, 1909-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Centrifugal casting of plate-type fuel elements

Description: From introduction: "Centrifugal casting appeared to be the only method by which the intricate shape could be produced in a cold mold. With this in mind, a program was initiated for the purpose of determining the feasibility of centrifugally casting plates of uranium-5 w.o chromium and uranium-2 w/o zirconium."
Date: November 10, 1955
Creator: Saller, Henry A.; Dickerson, Ronald F. & Murr, William E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Vapor-Deposited Zirconium on Uranium

Description: From introduction: "This report describes the second phase of the work on the application of protective coatings to uranium by vapor deposition to reduce or prevent its corrosion by water."
Date: July 20, 1955
Creator: Powell, Carroll F.; Jones, Robert P.; Girod, Fleet T. & Campbell, Ivor E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plastic Deformation in Grooved Rolls

Description: This report covers a study of the deformation characteristics of uranium in grooved rolls. The study's purpose was to provide a basis for possible improvements in the uniformity of the rolled rod produced for the Hanford and Savannah River reactors.
Date: September 27, 1955
Creator: Saller, Henry A.; Keeler, John R. & Cuddy, Lee J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Corrosion in 650 F Degassed Water of Uranium-Molybdenum Alloys Containing Impurity Additions

Description: From introduction: "At the request of WAPD, a study has been made of the effect of minor compositional variables on the corrosion behavior of uranium-molybdenum alloys in 650 F degassed water."
Date: October 6, 1955
Creator: Cawthorne, Edward W.; Berry, Warren E., 1922-; Reynolds, James E.; Jaffee, Robert Isaac, 1917- & Peoples, Robert S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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