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 Decade: 1960-1969
 Collection: Technical Report Archive and Image Library
Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1969

Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1969

Date: October 1969
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
Description: Report documenting the ongoing research and development of the Oak Ridge National Laboratory's Chemical Technology Division.
Contributing Partner: UNT Libraries Government Documents Department
Nuclear Energy Centers : Industrial and Agro-Industrial Complexes

Nuclear Energy Centers : Industrial and Agro-Industrial Complexes

Date: November 1968
Creator: Oak Ridge National Laboratory
Description: Report regarding the use of low cost nuclear power to increase both industrial and agricultural production, especially in developing nations.
Contributing Partner: UNT Libraries Government Documents Department
Low-Radioactivity-Level Waste Treatment. Part II: Pilot Plant Demonstration of the Removal of Activity from Low-Level Process Wastes by a Scavenging-Precipitation Ion-Exchange Process

Low-Radioactivity-Level Waste Treatment. Part II: Pilot Plant Demonstration of the Removal of Activity from Low-Level Process Wastes by a Scavenging-Precipitation Ion-Exchange Process

Date: May 27, 1963
Creator: Brooksbank, R. E.; Browder, F. N.; Holcomb, R. R. & Whitson, W. R.
Description: Report documenting the process of decontaminating low-activity fuel waste water via the Scavenging-Precipitation Ion-Exchange process. This includes analyses of the costs of the process as well as a description of the operation of the pilot plant.
Contributing Partner: UNT Libraries Government Documents Department
Chemical Technology Division Annual Progress Report: for Period Ending June 30, 1962

Chemical Technology Division Annual Progress Report: for Period Ending June 30, 1962

Date: September 21, 1962
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
Description: Report issued by Oak Ridge National Laboratory that discusses progress and work performed by the Chemical Technology Division.
Contributing Partner: UNT Libraries Government Documents Department
Instrumentation and Controls Division Annual Progress Report: for Period Ending September 1, 1962

Instrumentation and Controls Division Annual Progress Report: for Period Ending September 1, 1962

Date: February 6, 1963
Creator: Oak Ridge National Laboratory. Instrumentation and Controls Division.
Description: Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.
Contributing Partner: UNT Libraries Government Documents Department
Specifications and Procedures Used in Manufacturing U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor

Specifications and Procedures Used in Manufacturing U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor

Date: October 21, 1963
Creator: Kucera, W. J.; Leitten, C. F., Jr. & Beaver, R. J.
Description: Report containing the description and design of U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor. Topics include the requirements of core materials, materials specifications, manufacturing procedures, and shipping preparation.
Contributing Partner: UNT Libraries Government Documents Department
Status Report Number Three on Clinch River Study

Status Report Number Three on Clinch River Study

Date: December 6, 1962
Creator: Morton, R. J.
Description: Report describing the progress made in the Clinch River Study for the period May to October 1961. This report is based off of multiple reports of water sampling conducted across six stations in order to evaluate the safety and radioactive content of the Clinch River.
Contributing Partner: UNT Libraries Government Documents Department
Evaluation of a Reduced Pressure Backflow Preventer Using Activation Analysis

Evaluation of a Reduced Pressure Backflow Preventer Using Activation Analysis

Date: 1963-01-uu
Creator: Baird, Justus N., Jr.; Sanford, W. R. & Cristy, G. A.
Description: Report containing tests performed to evaluate a reduced pressure backflow preventer. This includes preliminary tests, resulting improvements, and final rests. Appendices begin on page 23.
Contributing Partner: UNT Libraries Government Documents Department
Maritime Reactor Project Annual Progress Report: for Period Ending November 30, 1962

Maritime Reactor Project Annual Progress Report: for Period Ending November 30, 1962

Date: April 4, 1963
Creator: Oak Ridge National Laboratory
Description: Report documenting research and developments made by the Maritime Reactor Program of the Oak Ridge National Laboratory.
Contributing Partner: UNT Libraries Government Documents Department
Development of Fabrication Procedures for Core B Fuel Elements for the Enrico Fermi Fast Breeder Reactor

Development of Fabrication Procedures for Core B Fuel Elements for the Enrico Fermi Fast Breeder Reactor

Date: 1964
Creator: Donnelly, R. G.; Thurber, W. C. & Slaughter, G. M.
Description: Report describing the "development procedures for fabricating the proposed Core B fuel element of the Enrico Fermi Fast Breeder Reactor" (p. 1). This includes a description of various components, reactor assembly, and reported conclusions. Appendices begin on page 57.
Contributing Partner: UNT Libraries Government Documents Department
The ORNL GCR-3, a 750-Mw(e) Gas-Cooled Clad-Fuel Reactor Power Plant : A Joint Design Study

The ORNL GCR-3, a 750-Mw(e) Gas-Cooled Clad-Fuel Reactor Power Plant : A Joint Design Study

Date: 1963
Creator: unknown
Description: Report documenting the design of the Oak Ridge National Laboratory Gas-Cooled Clad-Fuel Reactor Power Plant. This includes design criteria and parameters, costs, and descriptions of systems.
Contributing Partner: UNT Libraries Government Documents Department
Procedures for Fabricating Aluminum-Base ATR Fuel Elements

Procedures for Fabricating Aluminum-Base ATR Fuel Elements

Date: June 1964
Creator: Beaver, R. J.; Patriarca, P. & Adamson, G. M.
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.
Contributing Partner: UNT Libraries Government Documents Department
Maritime Reactor Project Annual Progress Report for Period Ending November 30, 1963

Maritime Reactor Project Annual Progress Report for Period Ending November 30, 1963

Date: March 1965
Creator: McCurdy, H. C.
Description: Report issued by the Oak Ridge National Laboratory discussing annual progress made by the Maritime Reactor Program. Progress and studies conducted during 1963 are presented. This report includes tables, illustrations, and photographs.
Contributing Partner: UNT Libraries Government Documents Department
Microscopic and Autoradiographic Studies of Distribution of Uranium in the Rat Kidney

Microscopic and Autoradiographic Studies of Distribution of Uranium in the Rat Kidney

Date: February 1965
Creator: Jones, Edith Seymour
Description: Report issued by the Oak Ridge National Laboratory discussing studies conducted on uranium retention in rat kidneys. Methods, equipment, and results of the studies are presented. This report includes tables, illustrations, and photographs.
Contributing Partner: UNT Libraries Government Documents Department
Laboratory Development of Processes for Fixation of High-Level Radioactive Waste in Glassy Solids. [Part] 3, Wastes from the Purex Solvent Extraction Process

Laboratory Development of Processes for Fixation of High-Level Radioactive Waste in Glassy Solids. [Part] 3, Wastes from the Purex Solvent Extraction Process

Date: June 1965
Creator: Clark, W. E.; Godbee, H. W. & Fitzgerald, C. L.
Description: Report concerning the fixation and disposal of toxic waste derived from the Purex solvent extraction process.
Contributing Partner: UNT Libraries Government Documents Department
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
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