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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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SL-1 Annual Operating Report: February, 1960-January 3, [1961]

Description: The Stationary Low Power Reactor No. 1 (SL-1) was a boiling water reactor demonstration plant for remote military bases. The plant had been operated by Combustion Engineering, Inc. from February, l959 until January 3, 1961 at which time a nuclear excursion rendered the plant inoperable, This report summarizes the of operations of maintenance, test, health and safety, and administrative activities for the year February, 1960 until the incident.
Date: June 15, 1961
Partner: UNT Libraries Government Documents Department
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Effects of Major Parameters on Cycle Efficiency and Cost for a Gas-Cooled Reactor Turbine Power Plant

Description: Cycle study performed on a closed loop Brayton cycle incorporating a gas-cooled nuclear reactor, regeneration, and compressor intercooling. The purpose of the study was to determine the effect of various cycle parameters on efficiency and cost.
Date: October 5, 1962
Creator: Miskell, R. V.
Partner: UNT Libraries Government Documents Department
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The Cold Pressing of Sinterable UOâ‚‚

Description: The intent of this work was to explore more fully the pressing of sinterable UO2 powders into cylindrical compacts in the hope that a more precise prediction of green density in terms of powder properties, pressure, and geometry could be evolved.
Date: March 27, 1961
Creator: Levey, R. P., Jr.
Partner: UNT Libraries Government Documents Department
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The Influence of Design and Production Parameters on Fabrication Costs of Nuclear Reactor Fuel Elements

Description: The objectives for this study were to determine fuel fabrication and assembly costs in a large nuclear power industry for several reactors, fuel rod sizes, and fuel materials.
Date: November 1, 1961
Creator: Stein, P. E.; Ayers, A. C.; Braatz, R. J.; Bradford, C. M.; Holt, V. D. & Mattie, G. P.
Partner: UNT Libraries Government Documents Department
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Shipboard Cobalt-60 Radiopasteurizer for Marine Products

Description: Report issued by the Brookhaven National Laboratory discussing the shipboard cobalt-60 irradiator. As stated in the introduction, "this report discusses the conceptual design of a cobalt-60 shipboard irradiator for use to improve the keeping quality of fish landed aboard commercial fishing trawlers operating out of ports along the eastern seaboard of the commercial United States" (p. 1). This report includes tables, and illustrations.
Date: June 30, 1963
Creator: Manowitz, B.; Kuhl, A. O.; Galanter, L.; Armel, J.; Black, K. M.; Klaassen, W. J. et al.
Partner: UNT Libraries Government Documents Department
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Engineering Development of Fluid-Bed Fluoride Volatility Processes: Part 5. Description of a Pilot-Scale Facility for Uranium Dioxide-Plutonium Dioxide Processing Studies

Description: Report describing a pilot plant constructed at Argonne National Laboratory for studying two major process steps for the recovery of uranium and plutonium from spent nuclear fuels of power reactors. A major objective is the demonstration of optimum process conditions for the two steps for synthetic reactor fuel compositions, including those containing mixtures of inactive fission products.
Date: 1964
Creator: Vogel, G. J.; Carls, E. L. & Mecham, W. J.
Partner: UNT Libraries Government Documents Department
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Potential Applications of Nuclear Energy for Process and Space Heat in the United States

Description: A survey and analysis of the potential opportunity for the use of nuclear reactors to satisfy process and space heat requirements in the continental United States and Alaska has been completed. The greatest emphasis has been devoted to manufacturing industries that utilize large quantities of process heat.
Date: October 1958
Creator: Geiringer, Paul Ludwig & Goodfriend, Morton J.
Partner: UNT Libraries Government Documents Department
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A Technical and Economic Evaluation of Solid-Fuel Gasification using Nuclear Heat: Production of Pipeline Gas, Liquid Fuels, and Chemicals from Lignite and Bituminous Coal

Description: From abstract: Results are reported of a study to determine the most economical method of utilizing nuclear heat to gasify a North Dakota lignite and a West Virginia bituminous coal so that the resulting gas is suitable as a source of synthesis gas for fuels and chemicals.
Date: November 30, 1962
Partner: UNT Libraries Government Documents Department
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The Design Study of Fluid Engine Power Systems

Description: From abstract: This report presents information generated during a six month feasibility study of an engine which uses a supercritical working fluid as the secondary portion of nuclear powered electric generating system.
Date: April 12, 1963
Creator: Baker, C. H.; Hunter, T. A.; Pauliukonis, R. S. & Pradhan, A. V.
Partner: UNT Libraries Government Documents Department
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A Nuclear Reactor System for Generating Power and Supplying Steam to a Water Desalination Plant in the Florida Keys

Description: From foreword: The results of an engineering study directed toward the evaluation and selection of a nuclear reactor system designed to produce electricity and furnish steam to a water desalination plant in the Florida Keys are given in this report.
Date: March 1964
Creator: Burns and Roe
Partner: UNT Libraries Government Documents Department
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Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin

Description: Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."
Date: September 29, 1952
Creator: Schwope, A. D.; Muehlenkamp, G. T. & Chubb, Walston
Partner: UNT Libraries Government Documents Department
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Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin

Description: Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."
Date: September 29, 1952
Creator: Schwope, A. D.; Muehlenkamp, G. T. & Chubb, Walston
Partner: UNT Libraries Government Documents Department
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The Ductility of Brazed Stainless Steel Joints

Description: Abstract: "The ductility of Type 310 stainless steel T-joints brazed with GE-62 brazing alloy was measured at room temperatures 1200, 1650, and 1800 F. The measure of ductility was taken as the plastic axial strain required to crack braze fillets in T-section tensile specimens. At elevated temperatures, the ductility of as-brazed joints approximated that of the stainless steel, but at room temperature the brazed joints had only one-tenth the ductility of the base metal. Annealing for 16 hr at 1… more
Date: July 8, 1953
Creator: Saller, Henry A.; Stacy, J. T. & Eddy, N. S.
Partner: UNT Libraries Government Documents Department
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