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Darex Process: Processing of Stainless Steel-Containing Reactor Fuels with Dilute Aqua Regia

Description: From abstract: "The Darex process developed for the recovery of uranium from stainless steel-containing reactor fuels consists of three steps: (1) dissolution of the fuel material in dilute aqua regia, (2) removal of chloride from the solution to prevent corrosion of downstream stainless steel process equipment, and (3) adjustment of the nitrate solution to solvent extraction feed conditions."
Date: June 7, 1962
Creator: Kitts, F. G. & Clark, W. E.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Fourth Quarter, April-June 1960

Description: From introduction: "This is the fourth of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: January 1962
Creator: U.S. Atomic Energy Commission
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Eighth Quarter, April-June 1961

Description: From introduction: "This is the eighth of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: March 1962
Creator: Pennington, R. T.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Ninth Quarter, July-September 1961

Description: From introduction: "This is the ninth of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: June 1962
Creator: Pennington, R. T.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Eleventh Quarter, January-March 1962

Description: From introduction: "This is the eleventh of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: August 1962
Creator: Pennington, R. T.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Tenth Quarter, October-December 1962

Description: From introduction: "This is the tenth of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: July 1962
Creator: Pennington, R. T.
Partner: UNT Libraries Government Documents Department
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In-Pile Loop Investigations of Corrosion of Zircaloy-2 and Other Possible Reactor Materials in 0.04 m UO2SO4 AT 280°C

Description: One of a series of experiments to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various radiation intensities, temperatures, solution compositions, and velocities of flow past specimens.
Date: May 5, 1962
Creator: Jenks, G. H.
Partner: UNT Libraries Government Documents Department
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Comparative Cost Study of Processing Stainless Steel-Jacketed UO2 Fuel: Mechanical Shear-Leach vs Sulfex-Core Dissolution

Description: Comparison of the economics of mechanical shear-leach and Sulfex decladding-core dissolution head end treatments for processing typical tubular bundles of stainless steel-jacketed UO2 nuclear fuels.
Date: April 23, 1962
Creator: Adams, J. B.; Benis, A. M. & Watson, C. D.
Partner: UNT Libraries Government Documents Department
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Pulse Amplifier Manual

Description: Manual for the use and repair of repair pulse amplifiers. This covers general testing routines, specific tests, and a bibliography of related materials.
Date: 1962
Creator: Fairstein, E.
Partner: UNT Libraries Government Documents Department
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Molten-Salt Reactor Program Semiannual Progress Report, February 28, 1962

Description: Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Descriptions of design, construction, and experimental progress are presented. This report includes tables, illustrations, and photographs.
Date: 1962
Creator: Oak Ridge National Laboratory
Partner: UNT Libraries Government Documents Department
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Oak Ridge Analytical Chemistry Division Annual Progress Report: 1962

Description: Report issued by the Oak Ridge National Laboratory discussing progress and work conducted by the Analytical Chemistry Division. Instrumentation, analytical methods, reactor projects, service analysis, and special research is presented. This report includes tables, illustrations, and photographs.
Date: 1962~
Creator: Oak Ridge National Laboratory. Analytical Chemistry Division.
Partner: UNT Libraries Government Documents Department
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