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Studies on the Electrolytic Reduction of Nitric Acid

Description: Report discussing the reduction of nitric acid that results from its use at the cathode for the electrolysis of uranyl nitrate. From introduction: "It is the purpose of this report to give the results of studies on the reduction of nitric acid of different concentrations, at different types of electrodes, and for various current densities in order to ascertain the effects of such changes."
Date: March 27, 1943
Creator: Hamer, Walter J.
Partner: UNT Libraries Government Documents Department
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Experimentation on the Extraction of Uranium from Western Ores

Description: The following report supplements a previous report by E.R. Saunders and M. C. Carosella and a report by A. J. Gailey and E. O. Brimm based around the same subject. This report describes a number of tests in which leaching temperatures of 115 and 125 C were tried for the extractions of uranium from western ores.
Date: December 27, 1943
Creator: Saunders, E. R. & Carosella, M. C.
Partner: UNT Libraries Government Documents Department
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The Leakage of Neutrons from a Heterogeneous Pile

Description: Abstract: "The leakage of neutrons from a heterogenous pile with finite aides is calculated developing the method used in CP-992. The change in the fraction of neutrons absorbed by the moderator is obtained using the results of the calculation of the leakage."
Date: December 27, 1943
Creator: Plass, Gilbert N.
Partner: UNT Libraries Government Documents Department
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The Motion of Massive Particles Through Solid Matter

Description: Report concerning the behavior of atoms dislodged from their positions in solid constituents by neutrons during the transition from high energy to thermal energy.
Date: April 27, 1944
Creator: Seitz, Frederick, 1911-2008
Partner: UNT Libraries Government Documents Department
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Recovery of Tuballoy From Solutions Containing Fluoride Ion

Description: "Another extraction method is described herein for the quantitative recovery of tuballoy from solutions containing high concentrations of fluoride ion. The method consists of the addition of aluminum nitrate to the solution in order to complex the fluoride ion, followed by saturation with calcium nitrate and extraction of the tuballoy with dibutyl carbitol.
Date: February 27, 1945
Creator: Smith, Fred; Tober, Frank W., 1919-1995; Lord, E. J.; Andrews, L. J. & Gates, J. W., Jr.
Partner: UNT Libraries Government Documents Department
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The Preparation of TClâ‚„ With Hexachloropropylene

Description: Report discussing various reaction methods for preparing TClâ‚„ with hexachloropropylene, as well as various methods for drying the TClâ‚„ after the reaction. Experimental methods are described in detail, and experimental results are presented.
Date: July 27, 1945
Creator: Pitt, B. M.; Curran, W. F.; Schmitt, J. M.; Wagner, E. L. & Miller, A. J.
Partner: UNT Libraries Government Documents Department
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The Rapid Determination of Nitric Acid and Thorium in Thorium Nitrate Solutions

Description: Abstract. The physico-chemical methods of determining nitric acid and thorium nitrate in solutions containing these two materials were investigated. Conductimetric titration with sodium hydroxide can be used to determine nitric acid accurately. the titration of thorium nitrate requires a separate standardization of the base however, since a basic salt is precipitated rather the normal hydroxide. The titration of thorium is reproductible however, so and empirical standardization can be used.… more
Date: November 27, 1945
Creator: Newton, A. S.; Powell, J. (James), 1932- & Figard, P
Partner: UNT Libraries Government Documents Department
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Electrolytic Reduction of Uranyl Ion

Description: From introduction: "Due to the hydrogen overvoltage at the surface of a mercury cathode, uranium solutions is hydrochloric acid may be reduced not only to the tetravalent state, but until considerable trivalent uranium is formed. Other metallic ions act as oxidation-reduction catalysts as well as being reduced themselves. The following paper is a study of the various reactions taking place in solution and at the surface of the cathode."
Date: May 27, 1946
Creator: Nichols, Ambrose R., Jr.
Partner: UNT Libraries Government Documents Department
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The Preparation of High-Purity Beryllium Oxide

Description: Abstract. A method for the preparation of beryllium oxide of high purity is presented. Beryllium basic acetate (BeO-3Be(C2H3O2)2) is prepared from the metal or a convenient salt, a chloroform solution of this material extracted with redistilled water, the dried basic acetate distilled in a quartz apparatus, and this purified material converted to the oxide by fuming down with sulfuric acid and igniting at 1000 degrees C. Impurities detectable spectrographically were reduced to a very low leve… more
Date: May 27, 1946
Creator: Tomkins, F. S.; Cressman, G. W. & Tolmach, L. J.
Partner: UNT Libraries Government Documents Department
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Fractionation of Fission Products and Heavy Elements by Volatilization Methods

Description: Technical report describing the attempt to separate the long lived fission product oxides by volatilization methods. A fractionization crucible was used. The fractionations give a fair idea of the relative volatilities of the longer lived fission products and also of the degrees of separation of the plutonium oxide or oxides from the fission products.
Date: August 27, 1946
Creator: Erway, N. D. & Simpson, O. C.
Partner: UNT Libraries Government Documents Department
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Identification and Characterization of Shielded Isotopes in Uranium Fission

Description: Abstract: "The first shielded isotope, 34th Br-82 has been isolated in fission. Its fission yield is about 3 x 10-(-5)%. This is a direct measurement of the yield of a primary fission product and gives direct information as to the distribution of nuclear charge among primary fission fragments of given mass numbers as discussed by Glendenin and Coryell."
Date: November 27, 1946
Creator: Feldman, Milton H.
Partner: UNT Libraries Government Documents Department
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The Ion Velocitron

Description: This report analyzes the separation of ions using the velocity of the ion measured through a long evacuated drift tube.
Date: January 27, 1947
Creator: Cameron, A. E. & Eggers, D. F.
Partner: UNT Libraries Government Documents Department
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Summary of the Research Progress Meeting

Description: Technical report includes three reports of research progress: 1)Neutron scattering by A. Bratenahl; 2) Nuclear Cross Sections, Norman Knable.
Date: May 27, 1948
Creator: Wakerling, R. K.
Partner: UNT Libraries Government Documents Department
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The copper-uranium deposits in White Canyon, Utah

Description: Field work in White Canyon was initiated to determine reserves of uranium ores and to determine the nature of the physical, geological, and economic conditions affecting mining and milling of such ores.
Date: January 27, 1949
Creator: Smyth, Sam K.
Partner: UNT Libraries Government Documents Department
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Alkyl Phosphoric Acids as Extraction Agents for Uranium

Description: The recent interest in tributyl phosphate as an extracting solvent for uranium indicated that consideration of n-butyl phosphoric acid for this application might be of interest if some way could be devised to overcome the manipulation and miscibility difficulties. It was found that if the material was placed in any one of a number of carrier solvents, it had a remarkably strong extractive effect on uranyl ion out of acid solutions without a salting agent present.
Date: January 27, 1950
Creator: Stewart, D. C., (Donald Charles), 1912-1996
Partner: UNT Libraries Government Documents Department
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The Separation of Trace Amounts of Radioactive Cs From Macro Quanitites of Sodium and Potassium Salts

Description: Summary: A method for the separation of cesium from macro quantities of sodium and potassium using an ion exchange resin, Dowex 50, has been developed. A 95% recovery of cesium with a reduction of the solid content of 95% was found possible. Curves illustrating the effect of acidity, column length, and flow rate are presented in the report. The sodium form, hydrogen form and ammonium form of Dowex 50 were investigated; the hydrogen form was found to give the best separation.
Date: January 27, 1950
Creator: Thorburn, R. C.
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending December 10, 1950

Description: Technical report detailing expansion of the Aircraft Nuclear Propulsion at the Oak Ridge National Laboratory. Major facilities completed at this time were the Shielding Rector, the ANP Critical Facility, and the 86-in. Cyclotron. Outlines further need for radiation damage studies. [From Summary]
Date: February 27, 1951
Creator: Briant, R. C.; Ellis, C. B. & Cottrell, W. B.
Partner: UNT Libraries Government Documents Department
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The Counting Efficiency of Pa²³³

Description: Abstract: "The counting efficiency of Pa²³³ has been determined by comparison of the counting rate of Pa²³³, under stated conditions, with the disintegration rate of U²³³ produced by Pa²³³ decay."
Date: February 27, 1951
Creator: Karraker, David George, 1923-
Partner: UNT Libraries Government Documents Department
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Summary of Research on Experimental Refractory Bodies of High-Melting Nitrides, Carbides, and Uranium Dioxide

Description: First 31 pages of a quarterly report discussing the progress made on research projects during the period from October 1950 to December 1950. This section of the report discusses progress on studies of the metabolic properties of various elements.
Date: February 27, 1951
Creator: Chiotti, P. & Hamilton, J. G.
Partner: UNT Libraries Government Documents Department
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Dry Fluoride Process Status Report

Description: Technical report outlining how uranium hexaflouride was prepared be the direct combination of irradiated uranium metal with elemental fluorine and subsequently decontaminated by adsorption, filtration, and sublimation on a laboratory scale. Report proposes a survey of other methods of preparing UF6 from uranium metal, a study of adsorption techniques for removing plutonium from UF6, and an investigation of fractional distillation for removing the volatile fission product fluorides from UF6. [Fr… more
Date: March 27, 1951
Creator: Leuse, R. E.
Partner: UNT Libraries Government Documents Department
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The Effect of Fluoride on the Corrosion of Stainless Steel in the Presence of Excess Al+3 Ion

Description: Technical report detailing corrosion tests of Type 347 stainless steel for two weeks in boiling uranyl nitrate, sulfuric acid media, with and without additions of Al+3 and F-1 in a 2:1 mole ratio. The results of these tests show that although the presence of aluminum greatly reduces the deleterious effect of fluoride, the corrosion rates are still three to four times greater than when no fluoride is present. [From Abstract]
Date: March 27, 1951
Creator: Olsen, Arnold R.
Partner: UNT Libraries Government Documents Department
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Preliminary Study of a Uranium - Bismuth Liquid Fuel Power Reactor L. F. R . 2

Description: Technical report and preliminary design calculations describing a type of liquid fuel reactor adaptable for production or breeding on a U-233 cycle based on data at Brookhaven National Laboratory. Describes design calculations for generating significant amounts of power and neutrons by use of uranium-bismuth solutions with fused salts in the reactor system.
Date: April 27, 1951
Creator: Gurinsky, D. H.; Kaplan, I.; Miles, F. T.; Williams, C. & Winsche, W. E.
Partner: UNT Libraries Government Documents Department
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