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The HGCR-1, a Design Study of a Nuclear Power Station Employing a High-Temperature Gas-Cooled Reactor with Graphite-UO₂ Fuel Elements

Description: "The preliminary design of a 3095-Mw(thermal), helium-cooled, graphite- moderated reactor employing sign conditions, 1500 deg F reactor outlet gas would be circulated to eight steam generators to produce 1050 deg F, 1450-psi steam which would be converted to electrical power in eight 157-Mw(electrical) turbine- generators. The over-all efficiency of this nuclear power station is 36.5%. The significant activities released from the unclad graphite-UO₂ fuel appear to be less than 0.2% of those pro… more
Date: 1959
Creator: Cottrell, William B.; Copenhaver, C. M.; Culver, H. N.; Fontana, M. H.; Kelleghan, V. J. & Samuels, G.
Partner: UNT Libraries Government Documents Department
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Darex Process: Processing of Stainless Steel-Containing Reactor Fuels with Dilute Aqua Regia

Description: From abstract: "The Darex process developed for the recovery of uranium from stainless steel-containing reactor fuels consists of three steps: (1) dissolution of the fuel material in dilute aqua regia, (2) removal of chloride from the solution to prevent corrosion of downstream stainless steel process equipment, and (3) adjustment of the nitrate solution to solvent extraction feed conditions."
Date: June 7, 1962
Creator: Kitts, F. G. & Clark, W. E.
Partner: UNT Libraries Government Documents Department
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The ORNL Four-Linear-Element Package Analog Computer (FLEPAC) Instruction Manual

Description: Report describing a computing device called the Four-Linear-Element Package Analog Computer (FLEPAC) at the Oak Ridge National Laboratory. The report includes a description of FLEPAC as well as instructions for its use.
Date: 1959
Creator: Green, F. P.
Partner: UNT Libraries Government Documents Department
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Generalized Heat Conduction Code for the IBM-704 Computer

Description: Report regarding a code that solves "steady-state and/or transient heat conduction problems in three-dimensional geometry" (p. 1).
Date: 1959
Creator: Fowler, T. B. & Volk, E. R.
Partner: UNT Libraries Government Documents Department
open access

Corn Pone: A Multigroup, Multiregion Reactor Code

Description: Report covering the development of a set of difference equations for machine solution. In addition, this report serves as user's manual for Corn Pone, which is a code for the Oracle, the Oak Ridge National Laboratory computer.
Date: 1961?
Creator: Kinney, W. E. & Coveyou, R. R.
Partner: UNT Libraries Government Documents Department
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Analytical Chemistry Division Annual Progress Report for Period Ending November 15, 1964

Description: Report issued by the Oak Ridge National Laboratory discussing progress and work conducted by the Analytical Chemistry Division. Instrumentation, analytical methods, reactor projects, service analysis, and special research is presented. This report includes tables, illustrations, and photographs.
Date: January 1965
Creator: Kelley, M. T.; Susano, C. D. & Fisher, D. J.
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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Applied Nuclear Physics Division Annual Progress Report for Period Ending September 10, 1956

Description: Report issued by the Oak Ridge National Laboratory discussing work completed by the Applied Nuclear Physics Division during 1956. Summaries of experiments conducted and project developments are presented. This report includes tables, illustrations, and photographs.
Date: November 20, 1958
Creator: Blizard, E. P.; Simon, A.; Callihan, A. D.; Clifford, C. E.; Maienschein, F. C. & Peelle, R. W.
Partner: UNT Libraries Government Documents Department
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Gas-Cooled Reactor Project Semiannual Progress Report: September 1964

Description: Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Gas-Cooled Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: February 1965
Creator: Trauger, D. B. & Whitman, G. D.
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
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Physics Division Annual Progress Report, January 31, 1964

Description: Report containing ongoing research and development of the Oak Ridge National Laboratory's Physics Division.
Date: June 1964
Creator: Oak Ridge National Laboratory. Physics Division.
Partner: UNT Libraries Government Documents Department
open access

Mechanical Properties of Some Refractory Metals and their Alloys

Description: Report regarding the mechanical properties of Niobium, Molybdenum, Tantalum, and Tungsten alloys. Includes a review of the scant literature regarding these elements.
Date: April 1964
Creator: McCoy, H. E., Jr.; Stephenson, R. L. & Weir, J. R., Jr.
Partner: UNT Libraries Government Documents Department
open access

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
open access

Procedures for Fabricating Aluminum-Base ATR Fuel Elements

Description: Report concerning the relatively inexpensive fabrication of an aluminum-based fuel element for the Oak Ridge National Laboratory's 250-Mw Advanced Test Reactor.
Date: June 1964
Creator: Beaver, R. J.; Patriarca, P. & Adamson, G. M.
Partner: UNT Libraries Government Documents Department
open access

Oak Ridge National Laboratory Radioisotopes Procedures Manual

Description: Manual for the Oak Ridge National Laboratory's Isotopes Development Center. Includes procedures for the production, storage, and shipment of radioisotopes.
Date: June 1964
Creator: Case, F. N.; Fuccillo, D. A., Jr.; Ewing, Sylvia B.; Acree, E. H.; McFarland, C. E.; Massey, B. J. et al.
Partner: UNT Libraries Government Documents Department
open access

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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