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 Decade: 1960-1969
 Collection: Technical Report Archive and Image Library
A Comparative Evaluation of Advanced Converters

A Comparative Evaluation of Advanced Converters

Date: January 1965
Creator: Rosenthal, M. W.; Adams, R. E.; Bennett, L. L.; Carter, W. L.; Douglas, D. A., Jr.; Hoskins, R. E. et al.
Description: Report issued by the Oak Ridge National Laboratory discussing advanced converters. Comparisons of advanced converters are presented. This report includes tables, and illustrations
Contributing Partner: UNT Libraries Government Documents Department
Interim Report on Corrosion by Zirconium-Base Fluorides

Interim Report on Corrosion by Zirconium-Base Fluorides

Date: January 17, 1961
Creator: Adamson, G. M.; Crouse, R. S. & Manly, W. D.
Description: Report issued by the Oak Ridge National Laboratory discussing studies conducted on corrosion by fluorides. Equipment, procedures, results, and analysis is presented. This report includes tables, illustrations, and photographs.
Contributing Partner: UNT Libraries Government Documents Department
Gas-Cooled Reactor Project Semiannual Progress Report, September 30, 1963

Gas-Cooled Reactor Project Semiannual Progress Report, September 30, 1963

Date: [1963-09-30..1964-01-29]
Creator: Oak Ridge National Laboratory
Description: Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Contributing Partner: UNT Libraries Government Documents Department
Type 316 Stainless Steel, Inconel, and Haynes Alloy No. 25 Natural-Circulation Boiling-Potassium Corrosion Test Loops

Type 316 Stainless Steel, Inconel, and Haynes Alloy No. 25 Natural-Circulation Boiling-Potassium Corrosion Test Loops

Date: June 1965
Creator: Jansen, D. H. & Hoffman, E. E.
Description: Report issued by the Oak Ridge National Laboratory discussing natural-circulation corrosion test loops. As stated in the abstract, "an investigation was undertaken to determine the compatibility of conventional nickel, iron, and cobalt-base high-temperature alloys with boiling potassium. The tests were designed to obtain quantitative information on the dissolution of the container alloys by condensing potassium and the subsequent deposition of solute in the subcooled liquid region of the test device" (p. 1). This report includes tables, illustrations, and illustrations.
Contributing Partner: UNT Libraries Government Documents Department
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending February 28, 1965

Molten-Salt Reactor Program Semiannual Progress Report for Period Ending February 28, 1965

Date: June 1965
Creator: Briggs, R. B.
Description: Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Progress of operations, construction, engineering analysis, and development is presented. This report includes tables, illustrations, and photographs.
Contributing Partner: UNT Libraries Government Documents Department
Evaporation of Iron-, Nickel-, and Cobalt-Base Alloys at 760 to 980°C in High Vacuums

Evaporation of Iron-, Nickel-, and Cobalt-Base Alloys at 760 to 980°C in High Vacuums

Date: November 1964
Creator: Bourgette, D. T.
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.
Contributing Partner: UNT Libraries Government Documents Department
High-Density Concrete for Gamma and Neutron Attenuation

High-Density Concrete for Gamma and Neutron Attenuation

Date: March 1965
Creator: Northup, T. E.
Description: Report issued by the Oak Ridge National Laboratory discussing the development of a high-density concrete. As stated in the abstract, "the basic approach to high-density concrete mix design is reviewed to show that theoretical calculations for concrete mixes do give results that are reliable" (p. 1). This report includes tables, illustrations, and photographs.
Contributing Partner: UNT Libraries Government Documents Department
Irradiation Testing of Fuel for Core B of the Enrico Fermi Fast Breeder Reactor

Irradiation Testing of Fuel for Core B of the Enrico Fermi Fast Breeder Reactor

Date: November 1964
Creator: Thurber, W. C.; McQuilkin, F. R.; Long, E. L., Jr. & Osborne, M. F.
Description: Report issued by the Oak Ridge National Laboratory discussing irradiation testing of fast breeder reactors. As stated in the introduction, "it is the purpose of this report to describe the irradiation studies carried out in support of the Core B fuel element development program" (p. 3). This report includes tables, illustrations, and photographs.
Contributing Partner: UNT Libraries Government Documents Department
Thermodynamic Calculations Relating to Chloride Volatility Processing of Nuclear Fuels: [Part] 2. The Capacity of Chlorine for Transporting Plutonium Tetrachloride Vapor During Reaction of U3O8-PuO2 with Carbon Tetrachloride

Thermodynamic Calculations Relating to Chloride Volatility Processing of Nuclear Fuels: [Part] 2. The Capacity of Chlorine for Transporting Plutonium Tetrachloride Vapor During Reaction of U3O8-PuO2 with Carbon Tetrachloride

Date: October 1964
Creator: Gens, T. A.
Description: Report issued by the Oak Ridge National Laboratory discussing thermodynamic calculations of nuclear fuels. As stated in the introduction, "the equations developed in this report could be used to calculate the capacity of chlorine for transporting plutonium tetrachloride" (p. 2). This report includes tables, and illustrations.
Contributing Partner: UNT Libraries Government Documents Department
An Experimental Investigation of Instantaneous-Collapse and Creep-Buckling Characteristics of Cylindrical Shells

An Experimental Investigation of Instantaneous-Collapse and Creep-Buckling Characteristics of Cylindrical Shells

Date: 1964
Creator: Greenstreet, B. L. & Corum, J. M.
Description: Report tests "conducted on nominal 8.0-in.-OD by 0.25-in.-wall and 4.0-in.-OD by 0.12-in.-wall specimens made from commercial pipe and tubing" (p. 1).
Contributing Partner: UNT Libraries Government Documents Department