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Aqueous Corrosion of Uranium Fuel-Element Cores Containing 0 to 20 w/o Zirconium

Description: Abstract: A description is given of the design and operation of a windowed autoclave system employed in the study of corrosion by pressurized hot water. The device has been used to obtain time-lapse motion pictures of the swelling and rupture of deliberately defected zirconium-clad uranium specimens. A method is described by which corrosion rates were calculated from pressure and temperature measurements. A typical set of pictures taken during a test is presented, and corrosion rates are report… more
Date: January 7, 1957
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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Carbide Coatings on Graphite

Description: From abstract: "A Method has been developed for the uniform coating of graphite tubes with carbides of niobium, tantalum, and zirconium by thermal composition of their respective halide vapors."
Date: 1957
Creator: Blocher, John M., Jr.; Ish, Carl J.; Leiter, Don P.; Plock, Layne F. & Campbell, Ivor E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Characterization of Inclusion in Dingot Uranium

Description: Abstract: The nonmetallic inclusions in both as-reduced and fabricated dingot uranium have been studied for comparison with those in ingot uranium. Special attention was paid to the hydride for the purpose of determining the amount and distribution in the various types of uranium. The types and distribution of other inclusions were also studied. It was found that the dingot uranium was of a higher quality than ingot uranium and was comparable to as-reduced derby uranium on the basis of over-all… more
Date: January 11, 1957
Creator: Cheney, Donald M. & Dickerson, Ronald F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Cladding of Delta-Phase Zirconium Hydride

Description: Abstract: A study has been made of the cladding of solid and powdered delta-phase zirconium hydride is both red and flat shapes with stainless steel. The program included investigations of metallurgical bonding, both with and without the sore of metallic barrier materials. Types 304 and 347 stainless steel were used for cladding material. The intermediate barrier-layer materials used were niobium, molybdenum, a combination of copper and molybdenum, and a combination of copper and niobium. The p… more
Date: December 27, 1957
Creator: Paprocki, Stan J.; Hodge, Edwin S. & Boyer, Charles B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Delta-Phase Zirconium Hydride as a Solid Moderator

Description: Abstract: "In a study of the preparation and properties of delta-phase zirconium hydride it was found that large, sound bodies of the hydride can be prepared by direct combination of the elements if the rate of the reaction is retarded by limiting the supply of available hydrogen. Specimens up to 1-in. diameter were prepared using this technique. Because delta phase zirconium hydride does not readily form eutectics with iron-and nickel-base alloys below 1800 F these materials may be utilized fo… more
Date: December 18, 1957
Creator: Vetrano, James B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Reactor Core Materials for a Gas-Cooled Reactor Experiment

Description: From introduction: "On February 1, 1956, Batelle was awarded a contract by the Army Reactor Branch (ARB) to select, develop, and test core materials which could be used successfully in conducting a Gas Cooled Reactor Experiment (GCRE). The prime objective of the GCRE would be to evaluate small portable reactor systems for military application...The present report is concerned with the GCRE activities at Batelle during approximately the 7 months' period following the first report of this series,… more
Date: July 11, 1957
Creator: Keller, Donald L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fabrication of Dispersed Uranium Fuel Elements Using Powder-Metallurgy Techniques

Description: Abstract: "Fabrication techniques for producing dispersion fuel elements with cores of 30 volume per cost of UC, U2Tl, U3Si, or U6Ni dispersed in Zircology 2 and 30 volume per cent of UC or UN dispersed in Type 18-8 stainless steel have been investigated. Roll-clad plate-type elements of all these compositions may be fabricated by powder-metallurgy methods in such a manner that good core-to-cladding bonds and cores with uniform dispersions of discrete uranium-composed particles are obtained. Fr… more
Date: May 6, 1957
Creator: Paprocki, Stan J.; Keller, Donald L. & Cunningham, G. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High-Temperature Oxidation Resistance of Thin Iron-Chromium-Aluminum Alloy Sheet

Description: Abstract: "The oxidation resistance of thin sheets of iron-28 w/o chromium-2.67 to 10.0 w/o alloys, nominally 0.004, 0.006, 0.008, 0.012, and 0.016 in. thick, was determined by exposure in static air for 100 hr at 2100 and 2300 F. A minimum of 3.67 and 9.37 w/o aluminum was necessary to prevent excessive oxidation of 0.004-in.-thick sheet material at 2100 and 2300 F, respectively. Correspondingly, specimens of lower aluminum content and greater thickness withstood the oxidation attack. Oxidatio… more
Date: October 22, 1957
Creator: Jablonowski, Edward J.; Shober, Frederic R. & Dickerson, Ronald F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

New Beta Heat-Treating Salt Baths for Reducing Hydrogen Pickup by Uranium Rods

Description: The following report summarizes the results of the laboratory-scale work and pilot-plant scale work of a salt-batch composition that reduces the hydrogen pickup by uranium rods during the beta heat treatment, and the study of the influence of humidity over the salt bath on hydrogen pickup.
Date: June 18, 1957
Creator: Lortscher, Lawrence L.; Sense, Karl A. & Filbert, Robert B., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preparation, Cladding, and Evaluation of Titanium-boron Dispersions

Description: This report discusses tests on the preparation and cladding of hot-pressed and pressure-bonded titanium-boron. It explores the properties of titanium-boron as a control material in reactors.
Date: June 9, 1957
Creator: Paprocki, Stan J.; Keller, Donald L.; Hodge, Edwin S.; Cunningham, George W.; Gedwill, Michael A. & Lozier, Donald E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Segregation in Arc-Melted Uranium-Niobium Alloys

Description: Report discussing a study aimed at pinpointing the cause of banding segregation in arc-melted uranium-niobium alloys and suggesting possible methods for eliminating banding.
Date: August 28, 1957
Creator: Dickerson, Ronald F.; Foster, Ellis L. & Chubb, Walston
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Studies Relating to Hydrogen in Dingot Uranium

Description: Report discussing a study to obtain a quantitative measurement of the movement and distribution of hydrogen among components such as magnesium metal chips, uranium tetrafluoride, and magnesium fluoride slag, similar to what would occur during a reaction in a thermite bomb.
Date: September 20, 1957
Creator: Trzeciak, Max J. & Mallett, Manley William, 1909-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Study of Aluminum Alloys Containing Up to 45 W/O Uranium

Description: Report discussing a study on casting techniques for the production of sound homogeneous extrusion blanks composed of aluminum-uranium alloys with 30 to 45 w/o uranium.
Date: April 30, 1957
Creator: Daniel, Norman E.; Foster, Ellis L.; DeMastry, John A.; Bauer, Arthur A. & Dickerson, Ronald F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Tracer Study of the Transport of Chromium in Fluoride Fuel Systems

Description: The following report follows an experimental study that was made on the mass transport of chromium in polythermal inconel-fluoride fuel systems, followed by the technique of adding radioactive chromium-51 to the system as either CrF3 in the salt or as elemental chromium in the solid phase.
Date: June 18, 1957
Creator: Price, Robert B.; Sunderman, Duane Neuman; Pobereskin, Meyer & Calkins, George D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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