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Competition in the Nuclear Power Supply Industry

Description: From purpose and scope: The Justice Department and the AEC embarked upon this joint study so as to provide the basis for preparation and consideration of guidelines for the nuclear industry best designed to foster vigorous growth and to provide a sound basis for government action.
Date: December 1968
Creator: Arthur D. Little, Inc.
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Complex Ions of Lanthanum in Aqueous Solutions

Description: The complexing of lanthanum by various anions and weak acids was investigated by observing the light absorption of the complex formed with thenoyltrifluoracetone (TTA). This species showed the properties needed for a satisfactory specgtrophotometric method of analysis.
Date: August 1, 1951
Creator: Mattern, Kenneth Lawrence
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Complexing Agents for the Solvent Extraction of Uranium from Thorium. I. The Use of Thiocyanate in the Extraction of Uranium. II. The Use of Antipyrine in Solvent Extraction

Description: Abstract. In the first section of this technical report a new method of extracting uranium from thorium nitrate solution is discussed. This method consists of extracting an aqueous solution of thorium nitrate, nitric acid, sodium sulphate, and potassium thiocyanate with hexone. By this procedure, using an equal volume of hexone it is possible to extract 83 percent of the uranium while only 0.3 percent of the thorium is extracted. other experiments show that even greater separations are possi… more
Date: February 16, 1945
Creator: Reas, W. H.
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Composition and Thermal Decomposition of Uranyl Peroxide

Description: Technical report on the studies that have been made on the composition and thermal decomposition of uranyl peroxide. The conditions of precipitation and drying have been found to have no appreciable effect on the composition of the compound, but do affect the physical appearance of the precipitate and the rate of thermal decomposition. The UO4 + 2H2O appears to be thermodynamically unstable with respect to UO3 at 25 degrees C and atmospheric pressure, although the rate of conversion is extreme… more
Date: June 30, 1945
Creator: Leininger, R. F.; Hunt, J. P. & Koshland, D. E., Jr.
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A Computer Code (CDC 1604A or IBM 7090) for Calculating the Cost of Shipping Spent Reactor Fuels as a Function of Burnup, Specific Power, Cooling Time, Fuel Composition, and Other Variables

Description: Report presenting the calculation of the costs incurred in shipping irradiated uranium-containing fuel elements. A computer code that designs a cask and calculates the shipping costs is presented. By use of the code, shipping costs were calculated for typical reactor fuels.
Date: August 1964
Creator: Salmon, Royes
open access

Computer description APPR-1 simulator

Description: The APPR-1 is a pressurized water reactor having a low specific heat fuel and a water primary coolant. The primary coolant loop delivers heat from the reactor to the steam generator. The secondary water in the steam generator is converted to steam and then taken to the turbine to drive an electrical generator. The simulation of this system is broken down into three primary areas: the neutron kinetics in the reactor which are necessary to generate the primary power function, the heat transfer… more
Date: December 15, 1958
Creator: RCA Service Company
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Computer Programs Using Zonal Harmonics for Magnetic Properties of Current Systems with Special Reference to the IBM 7090

Description: Report that "discusses the magnetic vector and scalar potentials, magnetic field components and their derivatives, and flux linkage for single current systems, and the mutual inductance, forces and torques between two such systems, whose axes are coplanar but not necessarily coincident" (p. 1).
Date: December 4, 1962
Creator: Garrett, M. W.
open access

The Concentration of Deuterium by Chemical Exchange Between Hydrogen and Ammonia

Description: Technical report describing the results of the chemical reaction between potassium amide and liquid ammonia and the exchange of hydrogen between hydrogen gas and liquid ammonia. This report finds that the reactions may be sufficiently rapid to be useful for isotope separations on a larger scale.
Date: December 15, 1951
Creator: Perlman, M. L. & Bigeleisen, J.
open access

Concentration of Plutonium by Cation Exchange Part I - New Elutriants

Description: From summary: "The concentration of plutonium by cation exchange was significantly improved by using a solution of ammonium lactate and sulfamate as the elutriant instead of nitric and sulfamic acids. The new elutriant permitted essentially complete elution of the plutonium and also avoided formation of gases in the resin bed during elution. At 45ºC, 2.8M ammonium lactate plus 0.15M ammonium sulfamate eluted 99.3 per cent of the total plutonium at an average concentration of 43.8 grams per lite… more
Date: December 1956
Creator: Bonner, Oscar D.; Burney, Glenn A. & Tober, Frank W., 1919-1995
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Concentration of Plutonium by Cation Exchange -- Stabilization of Pu(Ill) in Nitric Acid

Description: Technical report. From Abstract : "Ascorbic and isoascorbic acids, used in conjunction with sulfamic acid, reduced Pu(IV) rapidly and completely to Pu(III) in solutions of nitric acid. The solutions of Pu(III) were stable. Aminoguanidine sulfate also retarded the oxidation of Pu(III) but did not reduce Pu(IV)."
Date: February 1959
Creator: Tober, Frank W., 1919-1995 & Russell, Edwin R.
open access

Conceptual Design for 75 MWe Mixed Spectrum Superheating Reactor Power Plant

Description: "This report presents the conceptual design of a 75 MWe prototype Mixed Spectrum Superheater power plant. The scope of the work has emphasized primarily the design, performance, and cost information on the nuclear portion of the plant. The research and development programs required to insure plant feasibility are also present."--Intro.
Date: February 25, 1962
Creator: U.S. Atomic Energy Commission
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A Conceptual Design of a Thorium-Uranium (233) Power Breeder Reactor

Description: From abstract: A conceptual design study has been performed for a sodium cooled, graphite moderated, thermal power-breeder reactor utilizing the Thorium-Uranium 233 breeding cycle. Several aspects of the design of the system are considered but no attempt has been made to supply all the details. It appears that the design presented is feasible and will allow the production of economic power as well as full utilization of thorium resources.
Date: February 1, 1954
Creator: Henrie, J. O. & Weisner, E. F.
open access

Concerning the Quenching of the Fluorescence of Chlorophyll and Magnesium Phthalocyanin and the Interaction of These Pigments with the Quenching Substance

Description: An investigation of the quenching of fluorescence of dyestuffs (pigments) by other molecules will clarify the nature of the photochemical effect exerted by dyestuffs in general and chlorophyll in particular.
Date: unknown
Creator: Evstigneyev, V. B.; Gavrilova, V.A. & Krasnovskiĭ, A. A. (Aleksandr Abramovich), 1913-
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