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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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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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Computer Programs Using Zonal Harmonics for Magnetic Properties of Current Systems with Special Reference to the IBM 7090

Description: Report that "discusses the magnetic vector and scalar potentials, magnetic field components and their derivatives, and flux linkage for single current systems, and the mutual inductance, forces and torques between two such systems, whose axes are coplanar but not necessarily coincident" (p. 1).
Date: December 4, 1962
Creator: Garrett, M. W.
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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Evaluation of an Engineering Demonstration of the Modified Zirflex and Neuflex Processes for the Preparation of Solvent Extraction Feeds from Unirradiated Zirconium-Base Reactor Fuels

Description: Report that investigates the concept of using ammonium fluoride-oxidant systems to dissolve spent U-Zr-Sn reactor fuels in both batch and continuous operation.
Date: March 1964
Creator: Kitts, F. G.
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
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Fuels and Materials Development Program Quarterly Progress Report, September 30, 1968

Description: From Foreword: "Report containing information about ongoing research and development taking place in the Oak Ridge National Laboratory's Fuels and Materials Development Program. This includes a series of test reports covering such subjects as reactor fuels, the development of nitride fuels, and the effects of radiation on structural materials."
Date: February 1969
Creator: Oak Ridge National Laboratory. Metals and Ceramics Division.
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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