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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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Applied Health Physics Annual Report for 1963

Description: Report issued by the Oak Ridge National Laboratory discussing work and progress made by the Health and Physics Division during 1963. Instrumentation, personnel monitoring, and laboratory monitoring is presented. This report includes maps, tables, illustrations, and photographs.
Date: August 1964
Creator: Morgan, K. Z.; Davis, D. M.; Hart, J. C.; Abee, H. H.; Gupton, E. D. & Warden, A. D.
Partner: UNT Libraries Government Documents Department
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Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959

Description: Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design criteria, and the fabrication of reactor components" (p. 1).
Date: May 25, 1959
Creator: Aerojet-General Corporation
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division Annual Progress Report, May 31, 1968

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: September 1968
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
Partner: UNT Libraries Government Documents Department
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A Computer Code (CDC 1604A or IBM 7090) for Calculating the Cost of Shipping Spent Reactor Fuels as a Function of Burnup, Specific Power, Cooling Time, Fuel Composition, and Other Variables

Description: Report presenting the calculation of the costs incurred in shipping irradiated uranium-containing fuel elements. A computer code that designs a cask and calculates the shipping costs is presented. By use of the code, shipping costs were calculated for typical reactor fuels.
Date: August 1964
Creator: Salmon, Royes
Partner: UNT Libraries Government Documents Department
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Corrosion of the Volatility Pilot Plant INOR-8 Hydrofluorinator and Nickel 201 Fluorinator During Forty Fuel-Pprocessing Runs with Zirconium-Uranium Alloy

Description: Report documenting the corrosion of fluorinators of the Oak Ridge National Laboratory's volatility pilot plant. Includes descriptions of the fluorinators, their operating environments, and the results of their corrosion.
Date: March 1965
Creator: Youngblood, E. L.; Milford, R. P.; Nicol, R. G. & Ruch, J. B.
Partner: UNT Libraries Government Documents Department
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Evaporation of Iron-, Nickel-, and Cobalt-Base Alloys at 760 to 980°C in High Vacuums

Description: Report issued by the Oak Ridge National Laboratory discussing the evaporation of alloys in high vacuums. As stated in the introduction, "the investigation encompasses measurements of the evaporation rates, identification of the evaporating elements, and correlation of these measurements to the alloy composition for specimens in both the polished and oxidized conditions" (p. 2). This report includes tables, illustrations, and photographs.
Date: November 1964
Creator: Bourgette, D. T.
Partner: UNT Libraries Government Documents Department
open access

Gas-Cooled Fast Reactor Concepts: a Study

Description: Report describing the performance characteristics of gas-cooled fast reactors, which compare well with those of sodium-cooled fast reactors. With oxide fuel and helium, CO2, and SO2 coolant at pressures of 1000 to 1500 psia, the reactors have slightly higher breeding ratios than comparable sodium-cooled reactors.
Date: September 1964
Creator: Bender, M.; Carlsmith, R. S.; Delene, J. G.; Gall, W. R.; Goldman, A. E.; Holcomb, R. S. et al.
Partner: UNT Libraries Government Documents Department
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