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Interim Report: Faret Experimental Program

Description: From Introduction: "The Fast Reactor Test (FARET) program is part of the United States Fast Reactor Program directed toward the demonstration of breeder reactors essential to the long-range goal of utilizing fertile fuels. (1) With-in this program is the current thinking that the early construction and operation of two or three prototype nuclear power plants of the order of 250 Mw(e) will lead eventually to the construction of practical and economic full scale breeder reactors by the early 1980… more
Date: April 1963
Creator: Smaardyk, A.; Bump, T. R.; Handwerk, J. & Handwerk, J.
Partner: UNT Libraries Government Documents Department
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Irradiation of an Aluminum Alloy-Clad, Aluminum-Uranium Alloy-Fueled Plate

Description: Report issued by the Argonne National Laboratory discussing irradiation tests of an aluminum alloy-clad, aluminum-uranium alloy fuel plate. As stated in the introduction, "calculations were made to determine the lowest possible pressure which would allow the maximum possible local boiling on the plate and still assure a margin of safety against burnout" (p. 9). This report includes tables, illustrations, and photographs.
Date: July 1960
Creator: Gavin, A. P. & Crothers, C. C.
Partner: UNT Libraries Government Documents Department
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Irradiation of an Aluminum Alloy-Clad Ceramic Pellet-Fueled Plate

Description: From Introduction: "An experiment, designated MTR-W10, was designed to determine the effects of high burnup on the cladding and fuel of an aluminum-1% nickel alloy (M-388)-clad ceramic pellet-fuelded plate if the type manufactured at Argonne for the BORAX-IV core. Conditions of irradiation were selected to allow local boiling at the high flux end of the plate at a pressure of 600 psig."
Date: May 1960
Creator: Gavin, A. P.
Partner: UNT Libraries Government Documents Department
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The Isolation and Purification of Neptunium-237 Obtained From Hanford Wastes

Description: Through the efforts of the Hanford Engineer Works a quantity of neptunium-237 was separated from uranium waste solutions by a modification of the standard plutonium precipitation process, This material, as concentrates, was shipped to Argonne for final isolation and purification of the neptunium.
Date: May 6, 1953
Creator: Hindman, J. C.; Wehner, Philip, 1917-; Sullivan, J. C. & Cohen, Donald
Partner: UNT Libraries Government Documents Department
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IsotopesProduction Reactor: Summary of Complete Design

Description: Report describing an Isotope Production Reactor, which may be of interest to industrial groups studying the possibilities of entering the radioactive isotopes production field. Detailed drawings and specifications for the construction of the reactor are included.
Date: 1955
Creator: Winkleblack, R. K
Partner: UNT Libraries Government Documents Department
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A laboratory Ivestigation of the Fluorination of Crude Uranium Tertrafluoride

Description: Ore concentrates have been converted directly to crude uranium tetrafluoride by hydrogen reduction and hydrofluorination in fluidized-bed reactors. Small-scale laboratory experiments demonstrated that this process can be extended to the production of crude uranium hexafluoride through fluorination of the uranium tetrafluoride in a fluidized bed. The satisfactory temperature range for the reaction lies between 300°C and 600°C. At 450°C the fluorine utilization is between 50 and 80 per cent. With… more
Date: December 1957
Creator: Sandus, O. & Steunenberg, R. K.
Partner: UNT Libraries Government Documents Department
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Lecture Notes on Reactor Shielding

Description: Report issued by the Argonne National Laboratory discussing the shielding of radiation produced by nuclear reactors. As stated in the introduction, "these lectures will be an attempt to discuss the design of a reactor shield and the solution of the associated shielding problems by simple hand-computing methods" (p. 19). This report includes tables, and illustrations.
Date: March 1959
Creator: Grotenhuis, Marshall
Partner: UNT Libraries Government Documents Department
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Liquid MHD Power Cycle Studies

Description: Report issued by the Argonne National Laboratory discussing the magnetohydrodynamics (MHD) power cycle for liquid metals. The benefits, and different phases of the MHD power cycle are presented. This report includes tables, and illustrations.
Date: June 1965
Creator: Petrick, Michael & Lee, Kung-You
Partner: UNT Libraries Government Documents Department
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LMFBR Nuclear Safety Program Annual Report: July 1, 1969, to June 30, 1970

Description: Report issued by the Argonne National Laboratory discussing the Liquid Metal Fast Breeder Reactor Nuclear Safety Program. The work completed by the program between 1969 and 1970 is presented. This report includes tables, illustrations, and photographs.
Date: July 1971
Creator: Simmons, W. R. & Marchaterre, J. F.
Partner: UNT Libraries Government Documents Department
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The Manufacture of Enriched ZPR-III Fuel Plates

Description: This report is essentially a procedural account of the fabrication of certain enriched ZPR-III fuel plates for use in the ANL fast critical experiments at Arco, Idaho. A total of 208.92 kilograms of fully enrich, unalloyed uranium was processed. Of this amount 202.74 kilograms was received in the form of Oak Ridge type reduction buttons and 6.18 kilograms as pressed-powder plates. The completed fabrication consisted of 720 rectangular fuel plates having the nominal dimensions 3in. x 2in. x 1/8i… more
Date: October 1956
Creator: Yaggee, Frank L.
Partner: UNT Libraries Government Documents Department
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The Manufacture of Internal Blanket and Fuel Blanket Slugs for the Experimental Breeder Reactor

Description: Surrounding the core of the Experimental Breeder Reactor (EBR) is located the Internal Blanket (see Figure 2 of Reference 1). This blanket is compromised of natural uranium rods jacketed in stainless steel. The active portion of each rod is made up of five natural uranium slugs 0.873" diameter x 4.050" long. The slugs, stacked one of top of another, are held together and protected by a drawn-on stainless steel tube with welded and closures. These internal blanket rods are located inside the ext… more
Date: December 1953
Creator: Macherey, R. E. & Zegler, S. T.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Report [for] October, November, and December, 1952

Description: This quarterly progress report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses (1) water-cooled reactors, (2) liquid metal-cooled reactors, (3) reactor development - fuel metallurgy, (4) reactor development - component metallurgy, (5) basic metallurgy, (6) basic ceramics, (7) aqueous corrosion, and (8) applied metallurgy.
Date: December 31, 1952
Creator: Foote, Frank G. & Schumar, James F.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Report [for] October, November, and December 1955

Description: A total of nine clad plates, containing uranium -5 w/o zirconium 1.5 w/o niobium alloy cores and clad with Zircaloy-II, were rolled in plain carbon steel jackets, heat treated, physically evaluated, and corrosion tested. All these plates were found to be within predetermined dimensional tolerance in width, thickness, length, cladding thickness, and core distribution. Improved control of wielding variables and of the length of the seal pin projecting above the end plugs resulted in the eliminati… more
Date: June 1965
Creator: Foote, Frank G.; Schumar, James F. & Chiswik, Haim H.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Report January, February, and March 1954

Description: This quarterly report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses water cooled reactors, liquid metal cooled reactors, reactor development metallurgy, basic metallurgy, applied metallurgy, and aqueous corrosion.
Date: March 31, 1954
Creator: Foote, Frank G. (Frank Gale), 1906- & Schumar, James F.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Report July, August, and September 1953

Description: This quarterly report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses water cooled reactors, liquid metal cooled reactors, reactor development metallurgy, basic metallurgy, applied metallurgy, and aqueous corrosion,
Date: September 30, 1953
Creator: Foote, Frank G. (Frank Gale), 1906- & Schumar, James F.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Report October, November, and December 1953

Description: This quarterly report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses water cooled reactors, liquid metal cooled reactors, reactor development metallurgy, basic metallurgy, applied metallurgy, and aqueous corrosion.
Date: December 31, 1953
Creator: Foote, Frank G. (Frank Gale), 1906- & Schumar, James F.
Partner: UNT Libraries Government Documents Department
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Midwest Tandem Cyclotron: A Proposal for a Regional Accelerator Facility

Description: Report issued by the Argonne National Laboratory discussing the proposal of the Midwest Tandem-Cyclotron accelerator facility. Descriptions of the facility designs, methods, and operations are presented. This report includes tables, illustrations, and photographs.
Date: June 1969
Creator: Argonne National Laboratory
Partner: UNT Libraries Government Documents Department
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On The Steady-State Thermal Stresses in Cylindrical Fuel Pins Due to Axial Variations in Their Internal Heat-Generation Rate

Description: From Introduction: "Specifically, we shall be concerned with the case of a solid right circular cylinder of infinite axial extent, having a stress-free outer boundary, being cooled by a temperature-independent boundary conductance, and having an axial heat-generation rate of form shown in Fig. 1. The inclusion of a radial dependence proportional to I^0(r/L) is only a minor complication in solving the required heat-transfer problem and, for reference, has been included in the solution for the te… more
Date: December 1966
Creator: Valentin, Richard A.
Partner: UNT Libraries Government Documents Department
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Operating Manual for the Argonaut Reactor

Description: The design of the Argonaut (Argonne Nuclear Assembly for University Training) was initiated by the Reactor Engineering Division of Argonne National Laboratory to satisfy needs for a low-power reactor facility within the Laboratory, and for training uses within the international School of Nuclear Science and Engineering (ISNSE). It was intended primarily for instruction and research in reactor physics. It was also considered as a possibility that it would fulfill the requirements of universities… more
Date: August 1959
Creator: Argonne National Laboratory
Partner: UNT Libraries Government Documents Department
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Particle Accelerator Division Summary Report: April 15, 1958 through October, 1958

Description: Report issued by the Argonne National Laboratory discussing a summary report of work completed between April and October, 1958. Summaries of the studies conducted and work completed are presented. This report includes tables, and illustrations.
Date: February 1959
Creator: Argonne National Laboratory. Particle Accelerator Division.
Partner: UNT Libraries Government Documents Department
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Particle Accelerator Division Summary Report: April Through September 1960

Description: Report issued by the Argonne National Laboratory discussing a summary report of the Particle Accelerator Division. As stated in the summary, "this report outlines two methods applicable respectively to longhand and computer calculations" (p. 4). This report includes tables, illustrations, and photographs.
Date: 1960
Creator: Crewe, Albert V.; FitzPatrick, John P.; Foss, Martyn H. & Manson, David S.
Partner: UNT Libraries Government Documents Department
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