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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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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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High-Boron Steels for Reactor Shielding

Description: This report follows work performed to determine the effects of large boron additions on the fabricability and room-temperature tensile properties of various steels for reactor shielding.
Date: September 27, 1955
Creator: Saller, Henry A.; Stacy, John T. & Klebanow, Herbert L.
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
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The Mechanical Properties of Beta-Quenched Uranium at Elevated Temperatures

Description: The creep strength and tensile properties-were determined in vacuum for beta-quenched, derby uranium. The stresses to produce a secondary creep rate of- 0.0001 per cent per hr at 100, 250, 400, and 500 deg C were 48,000, sile strengths were 114,500, 35,100, 11,100, and 8,500 psi at temperatares of 28, 300, 500, and 700 deg C, respectively. The creep and tensile strengths decrease quite rapidly with increasing temperature in the temperatare range 250 to 400 deg C.
Date: September 6, 1955
Creator: Shober, Frederic R.; Marsh, Lyle L. & Manning, G. K.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Dissolution of Aluminum-Canned Thorium

Description: The following report studies the dissolution of aluminum-canned thorium, providing results that suggest a dissolution cycle that permits the separation of the canned-slug components.
Date: July 26, 1955
Creator: Beach, John G.; Schickner, William C. & Faust, Charles L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plastic Flow During Extrusion of Tubing

Description: Abstract: "A study of plastic flow during the extrusion of tubing was made by extruding colored Plasticine billets in a small-scale extrusion press. Decreasing the included angle of the conical die and tapering the ram end of the billet decreased the amount of coextrusion of the backer block into the tubing, lubricating the billet also decreased coextrusion."
Date: July 26, 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
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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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Grain Refinement of the As-Cast Uranium-5 w/o Chromium Alloy by Ternary Additions

Description: Abstract: "Refinement of grain size of the base uranium-chromium eutectic alloy (uranium-5 w/o chromium) by ternary additions is discussed. Thirteen additions to the base alloy were investigated, and three additions were found to exhibit worthwhile grain-refinement tendencies. The three alloys, uranium-5 w/o chromium-0.2 w.o molybdenum, uranium-5 w/o chromium-0.2 w/o germanium, and uranium-5 w/o chromium-0.2 w/o niobium, were heat treated to produce final grain-size structures of between 0.015 … more
Date: July 5, 1955
Creator: Saller, Henry A.; Dickerson, Ronald F.; Murr, William E. & Bauer, Arthur A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Ceramic Investigations of UO₂

Description: This report covers the progress made on an intensive program to develop and evaluate UO2 as a possible fuel element for the PWR.
Date: June 16, 1955
Creator: Allison, Adrian G. & Duckworth, Winston H.
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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Evaluation and Consolidation of Electrolytic Thorium

Description: Abstract: "Sound, fabricable ingots of thorium were produced by triple are melting of electrolytic thorium. Consumable electrodes were fabricated by tack welding of cold-pressed and vacuum-sintered bars of the granular thorium electrodeposited from a molten-salt bath. The hydrogen content of the electrodeposited material was reduced from 80 to 4 ppm by vacuum sintering at 1250 C at pressures below 1 x 10-(-3) mm of mercury. Both sodium and chlorine content were reduced during melting; sodium fr… more
Date: June 15, 1955
Creator: Saller, Henry A.; Dickerson, Ronald F. & Foster, Ellis L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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
open access

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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