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Aircraft Reactor Test Removal and Disassembly

Description: Report documenting the dissection of a reactor called the Aircraft Reactor Test (ART). Includes the removal of the reactor from its test cell, component removal, and plans for a for a disassembly building facility.
Date: 1960?
Creator: Abbatiello, A. A. & McQuilkin, F. R.
Partner: UNT Libraries Government Documents Department
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Bismuth

Description: This report provides a broad and in depth discussion of bismuth, discussing the properties of bismuth--including physical, electrochemical, and chemical properties. It then discusses the processes by which bismuth is detected and how bismuth can be separated and isolated, with discussions of dissolution, precipitation, and extraction.
Date: 1960
Creator: Fritz, James S.
Partner: UNT Libraries Government Documents Department
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Bremestrahlung in p-p-Collisions at an Energy of 150 MeV

Description: The differential cross-section for bremestrahlung in p-p collisions at an energy of 140 Mev is calculated at the upper end of the photon spectrum. the only transition which is considered is the E2 transition between 1D2 and the 1S0 state. The Siegart theorem is used and influence of the Coulomb force between the two protons is neglected.
Date: 1960
Creator: Dullemond, C. & de Swart, J. J.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division Annual Progress Report, August 31, 1960

Description: Report documenting the ongoing research of the Oak Ridge National Laboratory's Chemical Technology Division. This report includes tables, diagrams, graphs, and articles related to chemical technology.
Date: 1960
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program: Part 3, Status Report on Pressurized Water Reactors as of 1959

Description: Introduction: The U.S. Atomic Energy Commission has undertaken a study of various reactor concepts to develop a comprehensive plan for a 10-year civilian power reactor program. This study reports the status of pressurized water reactors on a technical, economic, and operating experience basis.
Date: 1960
Creator: U.S. Atomic Energy Commission
Partner: UNT Libraries Government Documents Department
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Control and Dynamics Performance of a Sodium Cooled Reactor Power System

Description: Introduction: Objectives and Method of Approach. High plant efficiencies can be realized without excessively high core temperatures and high coolant pressures by the use of liquid metal coolant. In an attempt to prove the feasibility of liquid sodium as a reactor coolant ALCO Products, Inc., under sponsorship of the Atomic Energy Commission, is undertaking a design study of three vital system components: the intermediate exchanger, the boiler, and the superheater. Since, in the past programs, the nuclear reactor had been the major focus of attention, the development of the sodium cooled reactor and sodium pumps for this application are thought to need the less development than the heat exchanger equipment. Consequently, parallel design studies of the reactor, pumps, and other system components have not yet been initiated.
Date: 1960
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
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The Crystal Structure of LiCuCl3-2H2O*

Description: This report undertakes research to study LiCuCl3-2H2O is from a structural standpoint, revealing the oxygen positions. The study uses the Levy-Bussing anisotropic temperature factor treatment and least squares program to determine a discrepancy factor for the visually determined intensities. The structure of the molecule is also found to have interesting magnetic properties which has inspired a new study at Brookhaven.
Date: 1960
Creator: Vossos, Peter H.; Fitzwater, D. R. & Rundle, R. E.
Partner: UNT Libraries Government Documents Department
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An Electrical Pass-Through for Clean, High Vacuum Use

Description: This report describes the method and research that led to the development of a "new type of mechanical seal for a high-voltage, vacuum pass-through...for use in a general utility 60º sector mass spectrometer." (From introductory paragraph)
Date: 1960
Creator: Jackson, Don M.; Wells, Garry & Soseman, Donald
Partner: UNT Libraries Government Documents Department
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Evaluation of the Technical, Economic and Practical Feasibility of Radiation Preservation of Fish

Description: From abstract: Based on exploratory studies conducted over the last six years on the radiation-preservation of various marine species, it is apparent that low dose substerilization-radiation treatment of certain selected sea foods can provide advantages for the procurer, processor, distributor and consumer of edible marine products.
Date: 1960?
Creator: Proctor, Bernard E.; Goldblith, Samuel A.; Nickerson, John T. R. & Farkas, D. F.
Partner: UNT Libraries Government Documents Department
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Fuel Element Development Program for the Pebble Bed Reactor

Description: ...Development during this quarter have caused a shift in emphasis of the Pebble Bed Reactor Fuel Element Development Program from coatings on the sphere surface to coatings on individual fuel particles as the major deterrent to fission product leakage. In a high level irradiation test, cracks developed in the coatings of specimens coated with pyrolytic carbon and siliconized silicon carbide. In another high level irradiation test, a graphite sphere fueled with Al2O3 coated with UO2 particles is showing excellent fission product retention. The leakage factors (i.e. rate of release/rate of production) for long lived volatile fission products such as Kr85m, Kr87, Kr88, Xe133, Xe135 are ranging from 10 to the negative 9th to 10 to the negative 6th. If this degree of fission product retention is maintained in a large power reactor, it would result in essentially a "clean" primary loop.
Date: 1960
Creator: Sanderson & Porter, Inc.
Partner: UNT Libraries Government Documents Department
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Fuel Element Development Program for the Pebble Bed Reactor

Description: A variety of spherical uranium-graphite fuel elements were fabricated with the objective of meeting the requirements of the Pebble Bed Reactor. Major emphasis was on silicon-silicon carbide coatings, pyrolytic carbon coatings and alumina coated fuel particles. An exploratory program on the limits of thorium oxide loadings by the infiltration process was started.Poor results with sintered alumina coated UO2 particles led to development work on alumina coating by vapor deposition for which the results have been most encouraging. A wide variety of sub-surface metal, metal carbide, and ceramic coatings located between an unfueled graphite shell and the fueled core of a PBR fuel element were prepared and examined.
Date: 1960
Creator: Sanderson & Porter, Inc.
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Project Quarterly Progress Report: May-July 1960

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: 1960
Creator: Oak Ridge National Laboratory
Partner: UNT Libraries Government Documents Department
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Idaho Division Summary Report: July, August, September, 1960

Description: Report issued by the Argonne National Laboratory covering a summary report of the work conducted by the Idaho Division. Experimental work and progress made on reactors are presented. This report includes tables, illustrations, and photographs.
Date: 1960
Creator: Novick, Meyer & Thalgott, F. W.
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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The Pebble Bed Reactor Program

Description: The coolant stream of all nuclear reactors caries some activity due to one or more of the following: a) neutron activation of coolant atoms, b) neutron activation of corrosion products carried by the coolant stream, c) fission recoil into the coolant stream, d) fission products leaking into the coolant stream. The Pebble Bed Reactor is not concerned with (1) and (b) since the helium working fluid, or coolant, has an activation cross-section which is essentially zero and its inert chemical nature effectively eliminates corrosion as a consideration. We are not concerned with (c) since developments to date, of fuel and particle coatings to reduce fission product leakage, will also prevent fission recoil into the coolant stream.
Date: 1960
Creator: Sanderson & Porter, Inc.
Partner: UNT Libraries Government Documents Department
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Performance of HNPF Prototype Free-Surface Sodium Pump

Description: Abstract: A free-surface centrifugal pump, incorporating a hydraulic bearing running in sodium, was operated at the conditions required for service in the HNPF.
Date: 1960
Creator: Atz, R. W.
Partner: UNT Libraries Government Documents Department
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Photoproduction of Beryllium-7

Description: From abstract: "The nuclide Be7 has been produced by photoactivation of Be9, B and C12 using the bremsstrahlung beam of an electron synchrotron operated at 45 Mev. Integrated cross sections for the formation of Be7 have been estimated by comparison with the Ta181([gamma],n)Ta180m reaction. The reaction C12([gamma],2p3n)Be7 has also been observed in irradiations at 30, 35 and 40 Mev maximum energy. Its yield has been compared with that of the C12([gamma],n) reaction at 45 Mev. The reaction A127([gamma],2p3n)Na22 was observed at 45 Mev."
Date: 1960
Creator: Foster, M. S. & Voigt, A. F.
Partner: UNT Libraries Government Documents Department
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