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ALPR Preliminary Design Study (Argonne Low Power Reactor) Phase 1

Description: A preliminary design study, Phase I of the ALPR project, has been made in accordance with the Army Reactors Branch specifications for a nuclear "package" power plant with a 200-260-kw electric and 400 kw heating capacity. The plant is to be installed at the Idaho Reactor Testing Station as a prototype for remote arctic installations. The "conventional" power plant as well as the exterior reactor components are described in the accompanying report and cost estimate by Pioneer Service and Enginee… more
Date: April 20, 1956
Creator: Treshow, M.; Pearlman, H.; Rossin, D. & Shaftman, D.
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Effects of Metal Purity and Heat Treatment on the Corrosion of Uranium in Boiling Water

Description: Corrosion rates of present reactor grade uranium were measured in boiling distilled water and were found to have higher values almost by a factor of two then previously reported corrosion rates of uranium. Mallinckrodt biscuit metal showed corrosion rates in the same medium somewhat lower than reactor grade uranium, and high purity metal prepared at Argonne National Laboratory corroded considerably less rapidly than the biscuit metal.
Date: April 14, 1953
Creator: Draley, Joseph Edward, 1919- & McWhirter, J. W.
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The Manufacture of Aluminum Clad Aluminum-Plutonium Alloy Irradiation Specimens

Description: This report describes the manufacture of 25 Aluminum clad, 10 w/o plutonium-aluminum alloy and 5 w/o plutonium-aluminum alloy cored specimens for Argonne National Laboratory-University of California irradiation tests in the Materials Testing Reactor. The manufacturing method: preparation of cores and cladding material, assembly and welding of compacts, outgassing, roll bonding, shearing, identification marking and final fabrication into napkin "rings" is described in detail. Of ninety-six speci… more
Date: April 17, 1952
Creator: Shuck, Arthur B., 1918-
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Quarterly Progress Report on Reactor Development 400 Program

Description: Physics calculations have been made for various combinations of the four types of fuel assemblies to be used in the EBWR core. Two thicknesses of plates, 0.205 in. and 0.274 in., including the two 0.020-in. cladding layers, are to be made of both natural U and U containing 1.44% U235. A total of 148 assemblies, 74 natural and 74 enriched, are to be fabricated with six identical plates each. Various configurations of these fuel assemblies will be used to (1) change the critical size of the core,… more
Date: April 30, 1956
Creator: Stuart McLain & Members of the Laboratory Staff
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Reactor Engineering Division Quarterly Report: December 1, 1953 Through March 30, 1954

Description: Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date: April 15, 1954
Creator: Argonne National Laboratory. Reactor Engineering Division.
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Reactor Engineering Division Quarterly Report [for] October, November, December 1955. Section I

Description: The gastight steel building (400,000 cu ft) in which all radioactive components are to be housed has been completed by the Graver Tank Company. This structure was tested for strength at 18.75 psig (20% above design pressure) and then tested for leaks. No leaks were found in soap bubble testing of all welded seams. Continuous measurements of temperature and pressure over a ten-day period showed the leakage, if any, to be less than the 500 cu/ ft/day at 15 psig specified. The gastight cylinder wa… more
Date: April 1956
Creator: Members of the Reactor Engineering Division
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Thermal Annealing of Neutron Induced Discomposition in Artificial Graphite : [Part] III, Heating-During-Irradiation Experiments

Description: Experiments are described in which the pile-induced changes in electrical resistivity and elastic modulus of graphite were investigated as functions of the sample temperature during bombardment and the amount of bombardment. The data are for relatively low bombardment times (up to ca. 20 L-units) and temperatures (up to 340*C) and are not sufficiently extensive to permit unequivocal conclusions.
Date: April 13, 1953
Creator: Neubert, T. J.
open access

Zrclad Zirconium-Uranium Alloy Rod for Heat Thru-Put Test

Description: The purpose of this work was (1) to investigate the possibility of producing zirconium-clad zirconium-uranium alloy objects by casting the core alloy directly into zirconium and zirconium-3 w/o tin jackets, producing a diffusion bond at the jacket-core interfaces, and (2) to produce small scale heat thru-put test specimens by this method.
Date: April 17, 1952
Creator: Shuck, Arthur B., 1918-
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