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Liquid Metal Fast Breeder Reactor Design Study

Description: From introduction: "The primary objective of the present study was to develop a conceptual design of a large sodium cooled fast breeder reactor of a nominal electrical rating of 1000 Mw operating on the uranium-plutonium cycle."
Date: January 1964
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.
Partner: UNT Libraries Government Documents Department
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Uranium Migration in UO₂-Bearing Ceramics

Description: This report follows a preliminary study on uranium migration in pressed and sintered UO2-bearing bodies based on MoSi2 or Al2O3.
Date: September 4, 1953
Creator: Quirk, J. F.; Smalley, A. K.; Duckworth, W. H. & Ferrell, Edward Francis.
Partner: UNT Libraries Government Documents Department
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Studies on Uranium Recovery From Unirradiated Reactor Fuel Elements by Volatile Separation in Inert Fluidized Beds

Description: This technical report presents the results of studies on the recovery of uranium by fluoride volatilization from the following unirradiated reactor fuels: zirconium-uranium alloy, uranium oxide, uranium carbide, and uranium metal. The inert fluidized bed technique was found to be a promising approach to the volatile reprocessing of spent nuclear fuels. This report is accompanied by 9 tables and 10 figures.
Date: 1962
Creator: Reilly, J. J., (Of the Brookhaven National Laboratory, Associated Universities Incorporated); Regan, W. H.; Wirsing, E. & Hatch, L. P.
Partner: UNT Libraries Government Documents Department
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Uniformly Reactive Uranium Dioxide from a Single Oxidation-Reduction Cycle

Description: Abstract: By use of a modified thermobalance and reactor as the primary experimental tool for sample preparation and evaluation, a process has been developed by which parent uranium feed materials of a widely variable reactivity and composition may be converted to a uniformly reactive uranium dioxide.
Date: August 28, 1963
Creator: Orrick, N. C.; Jones, C. G.; Hale, C. F.; Barber, E. J. & Rapp, Karl E.
Partner: UNT Libraries Government Documents Department
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Refabrication and Encapsulation of Highly Irradiated Uranium Dioxide

Description: Abstract: One hundred gram quantities of uranium dioxide, irradiated to burnup as great as 21,000 Mwd/MTU and previously reprocessed by AIROX (Atomics International Reduction Oxidation), were refabricated into high density pellets and encapsulated for re-irradiation.
Date: December 1, 1964
Creator: Guon, J.; Bodine, J. E. & Sullivan, R. J.
Partner: UNT Libraries Government Documents Department
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Uranium Oxide Slurry Pumping Experiments

Description: Abstract: Experiments on colloid milling and pumping show that uranium trioxide, when carefully dehydrated, can be dispersed in water to form a relatively stable slurry, suitable for a homogeneous slurry pile. At temperatures considerably below those of anticipated pile operation particle size growth occurs attended by increase in settling rate and decrease in viscosity. Theses properties of the slurries may be strongly affected by impurities present as well as by special operating condition… more
Date: September 15, 1944
Creator: Brandt, R. & Dean, G. R.
Partner: UNT Libraries Government Documents Department
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Preliminary Report on a Colorimetric Method for the Determination of Microgram Quantities of Thorium : Experiments in the Dissolution of O2 Metal [UO2]

Description: Abstract. thorium can be precipitated as a salt of p-dimethylaminoazophenylarsonic acid at a pH of about 1.5. the precipitate, collected on a sintered glass filter is washed with dilute ammonium hydroxide to dissolve the dye. the amount of thorium is determined by measuring the concentration of the dye spectrophotometrically at a wavelength of 450 millimicrons. Zirconium, which interferes, can be separated and determined using the same reagent in strong hydrochloric. the behavior of thorium… more
Date: January 1, 1945
Creator: Byerly, W.; Niedrach, L.; Davin, W.; Dyas, H. & Bane, R. W.
Partner: UNT Libraries Government Documents Department
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Some Studies of the Reactions of Uranium Oxides with Hydrogen, Oxygen and Water

Description: Abstract: The purpose of this research was to obtain data that would be useful in predicting changes that might be expected to occur in the oxidation state and degree of hydration of powdered uranium oxides maintained for long periods of time at temperatures between 30 and 300 degrees C. in the presence of excess water, hydrogen, oxygen and possibly hydrogen peroxide. The reaction of hydrogen and oxygen with water slurries of U3O8 were studied at 100-300 degree C.
Date: June 1946
Creator: Gillies, Daniel M.
Partner: UNT Libraries Government Documents Department
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Recovery of D2O and UO2F2 by Distillation

Description: Technical report describing the purification and separation by distillation of UO2F2 from D2O. In the experiment which is discussed 2,129.6 lbs of UO2F2 were dissolved in 6,605 lbs of D2O. The average isotopic purity of the D2O decreased during the distillation from 99.77% to 99.73%. The dissolved impurities were less than those present originally in the heavy water.
Date: October 10, 1945
Creator: Fischer, R. & Wattenberg, Albert, 1917-
Partner: UNT Libraries Government Documents Department
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The Crystal Structure of Trichlorides, Tribromides and Trihydroxides of Uranium and of Rare Earth Elements

Description: Abstract: "The compounds UCl3, UBr3, IaCl3, LaBr3, La(OH)3, CeCl3, CeBr3, PrCl3, PrDr3, Pr(OH)3, HdCl3, and Hd(OH)3 are shown to be isomorphous. They have hexagonal structures with two molecules per unit cell. The complete structures are determined and described."
Date: 1948
Creator: Zachariasen, William H.
Partner: UNT Libraries Government Documents Department
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The Solubility of Uranyl Oxalate and the Existence of Undissociated Uranyl Oxalate in Solution

Description: Abstract: "The solubility of the solid, UO2C2O4 x rH2O, was measured at various acid and uranyl nitrate concentrations. The results of the measurements prove the existence of the uranyl oxalate complex - UO2C2O4, in solutions containing excess UO2^2."
Date: September 8, 1945
Creator: Pimentel, George C. & Stevenson, F. R.
Partner: UNT Libraries Government Documents Department
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Effect of Iron on the Low Temperature Precipitation of Tubanyl Peroxide in Beta

Description: Abstract: "In the low temperature precipitation of tubanyl peroxide from Beta gunks, process modifications are described which minimize the effect of iron on decompisition of H2O2. These include the addition of excess H2O2 to the slurry only after attaining a reduced temperature, the use of malonic and acetic acid complexing when the H2O2 is added at room temperature, and the use of wetting agents when the entire process is carried out at 2 C."
Date: 1945
Creator: Brown, K. B.; Swanson, D. H.; Wagner, E. L. & Miller, A. J.
Partner: UNT Libraries Government Documents Department
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Tuballoy Peroxide

Description: The following report is the third in a series of reports discussing tuballoy peroxide. This report in particular discusses the solubility of tuballoy peroxide in sulphate solutions based on the tubanyl sulphate association hypothesis discussed in previous reports.
Date: 1945
Creator: Grieger, P. F. & Gates, J. W.
Partner: UNT Libraries Government Documents Department
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Tuballoy Peroxide

Description: The following report determines the solubility of tuballoy peroxide over a fairly wide range of sulphate, hydrogen ion and hydrogen peroxide concentrations.
Date: 1945
Creator: Grieger, P. F.; Christopherson, E. W.; Oringer, Roy & Gates, J. W.
Partner: UNT Libraries Government Documents Department
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TO₃ Reduction and Chlorination in the Experimental Glass Fluidizer

Description: Abstract: "Temperatures above 400 C are required before reduction will take place with AH3. Above 500 C, a pyrophoric product was obtained. The chlorination temperature should be about 350 C initially and above 450 C at the end of the reaction to achieve 99% chlorination."
Date: December 20, 1945
Creator: Lowrie, Robert Sydney & Hubbard, J. V.
Partner: UNT Libraries Government Documents Department
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Tuballoy Oxides in the Reduction of TO₃

Description: Introduction: "This investigation was undertaken because of the importance of the reduction of TO3 to TO2 by hydrogen gas in the conversion of TO3 to TF4. We hoped to discover what factors affect the rate of reduction and the quantitativeness of the yield."
Date: 1945
Creator: Tanford, Charles; Tichenor, R. L. & Larson, C. E.
Partner: UNT Libraries Government Documents Department
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Flotation Characteristics of Florida Phosphate Leached-Zone Material, Progress Report No . 7

Description: Although the results reported herein are rather encouraging and show the possibilities of utilizing flotation to increase recoveries and in some instances grades, they should not not be considered an optimum. As stated previously, time did not permit a detailed investigation of all reagents an conditions to obtain maximum grades and recoveries, but sufficient data, with enough typical samples, have been obtained to indicate a definite trend and encouragement for further studies. A comparison of… more
Date: December 20, 1955
Creator: Snow, Robert E. (Robert Ellis)
Partner: UNT Libraries Government Documents Department
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Investigations of Radioactive Fuel-Bearing Glasses

Description: "A series of high urania-content glasses were fiberized and examined for high-temperature strength properties. One glass, RX360 containing 60% U/sub 3/O/ sub 8/ by weight, had better high-temperature tensile properties than any glass previously reported. It was observed that many of the glasses studied separated into immiscible phases and that the fiberizable glass phase had lower U/sub 3/O/ sub 8/ content than the base compositions. A physical analysis of crystal structures of the devitrificat… more
Date: June 30, 1962
Creator: Lockwood, P. A.
Partner: UNT Libraries Government Documents Department
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Investigations of Radioactive Fuel-Bearing Glasses

Description: "A series of glass compositions containing uranium oxide was investigated to determine fiberizability and physical properties of resultant fibers. The basic properties to be determined were the maximum U/sub 3/O/sub 8/ content in a fiberizable glass and the maximum service temperature of the fibers. Glasses containing 60 wt% U/sub 3/O/sib 8/ were fiberizable; the fibers had strengths of 100,000 psi at 1600 deg F. Fiber-forming equipment was installed at Moun Laboratory to produce glass fibers c… more
Date: July 31, 1961
Creator: Lockwood, P. A.
Partner: UNT Libraries Government Documents Department
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The Effect of Crystallite Size on the Bulk Density and Strength Properties of Uranium Dioxide Specimens

Description: Fused uranium dioxide was separated into fractions of varying particle size by air separation. Specimens of the nominal size of 1/8 by 1/4 by 1½ in. were formed by hydrostatic pressing, firing, and lapping. Specimens prepared from the 0 to 5 μ fraction were the strongest and most dense. The room-temperature density was about 92% of theoretical and the room-temperature flexural strength was about 12,000 1b. per sq. in. When tested at 1000°C., the strength was about 18,000 1b. per sq. in. The fle… more
Date: June 1, 1955
Creator: Burdick, Milton D. & Parker, H. S.
Partner: UNT Libraries Government Documents Department
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