In-Pile Test of Prototype ML-1 Fuel Elements (open access)

In-Pile Test of Prototype ML-1 Fuel Elements

Report documenting the testing of prototype fuel elements used in a mobile nuclear power plant. Includes descriptions and evaluations of the test.
Date: June 1964
Creator: Brunhouse, J. S.; Burgess, A. B.; Geering, G. T.; Nakazato, S. & Titus, G. W.
System: The UNT Digital Library
Applied Health Physics Annual Report for 1963 (open access)

Applied Health Physics Annual Report for 1963

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.
System: The UNT Digital Library
Physics Division Annual Progress Report, January 31, 1964 (open access)

Physics Division Annual Progress Report, January 31, 1964

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.
System: The UNT Digital Library
Mechanical Properties of Some Refractory Metals and their Alloys (open access)

Mechanical Properties of Some Refractory Metals and their Alloys

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.
System: The UNT Digital Library
Procedures for Fabricating Aluminum-Base ATR Fuel Elements (open access)

Procedures for Fabricating Aluminum-Base ATR Fuel Elements

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.
System: The UNT Digital Library
Oak Ridge National Laboratory Radioisotopes Procedures Manual (open access)

Oak Ridge National Laboratory Radioisotopes Procedures Manual

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.
System: The UNT Digital Library
Development of the Assembly Method for Fuel Elements for the Advanced Test Reactor (open access)

Development of the Assembly Method for Fuel Elements for the Advanced Test Reactor

Report regarding the development of fuel elements for the Advanced Test Reactor. The designs for the side plates and joints are documented, as well as the assembly process of the fuel element.
Date: 1964
Creator: Knight, R. W. & Leitten, C. F., Jr.
System: The UNT Digital Library
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 (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

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
System: The UNT Digital Library
Analytical Chemistry Division Annual Progress Report, September 30, 1968 (open access)

Analytical Chemistry Division Annual Progress Report, September 30, 1968

Report containing the ongoing research and development of the Oak Ridge National laboratory's Analytical Chemistry Division.
Date: 1964-12~
Creator: Oak Ridge National Laboratory. Analytical Chemistry Division.
System: The UNT Digital Library
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending July 31, 1964 (open access)

Molten-Salt Reactor Program Semiannual Progress Report for Period Ending July 31, 1964

Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Descriptions of design, construction, and experimental progress is presented. This report includes tables, illustrations, and photographs.
Date: November 1964
Creator: Briggs, R. B.
System: The UNT Digital Library
Electronuclear Research Division Annual Progress Report, December 31, 1963 (open access)

Electronuclear Research Division Annual Progress Report, December 31, 1963

Report containing ongoing research and development taking place at the Oak Ridge National Laboratory's Electronuclear Division.
Date: June 1964
Creator: Oak Ridge National Laboratory. Electronuclear Research Division.
System: The UNT Digital Library
Solid State Division Annual Progress Report, May 31, 1964 (open access)

Solid State Division Annual Progress Report, May 31, 1964

Report containing ongoing research and development of the Solid State Division of the Oak Ridge National Laboratory.
Date: October 1964
Creator: Oak Ridge National Laboratory. Solid State Division.
System: The UNT Digital Library
Thorium-Uranium-233 Oxide (Kilorod) Facility : Rod Fabrication Process and Equipment (open access)

Thorium-Uranium-233 Oxide (Kilorod) Facility : Rod Fabrication Process and Equipment

Report documenting "the design, construction, and operation of the Kilorod Facility and its fabrication equipment" (p. 42) as well as its economic viability.
Date: April 1964
Creator: Sease, J. D.; Lotts, A. L. & Davis, F. C.
System: The UNT Digital Library
An Experimental Investigation of Instantaneous-Collapse and Creep-Buckling Characteristics of Cylindrical Shells (open access)

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

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).
Date: 1964
Creator: Greenstreet, B. L. & Corum, J. M.
System: The UNT Digital Library
Some Major Fuel-Irradiation Test Facilities of the Oak Ridge National Laboratory (open access)

Some Major Fuel-Irradiation Test Facilities of the Oak Ridge National Laboratory

Report describing various reactors, six thermal conduction capsules, three loop facilities, miscellaneous equipment, and shop facilities maintained by the Oak Ridge National Laboratory.
Date: April 1964
Creator: Trauger, Donald B.
System: The UNT Digital Library
Evaporation of Iron-, Nickel-, and Cobalt-Base Alloys at 760 to 980°C in High Vacuums (open access)

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

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.
System: The UNT Digital Library
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 (open access)

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

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.
Date: October 1964
Creator: Gens, T. A.
System: The UNT Digital Library
Irradiation Testing of Fuel for Core B of the Enrico Fermi Fast Breeder Reactor (open access)

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

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.
Date: November 1964
Creator: Thurber, W. C.; McQuilkin, F. R.; Long, E. L., Jr. & Osborne, M. F.
System: The UNT Digital Library
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 (open access)

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

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.
System: The UNT Digital Library
Development of Fabrication Procedures for Core B Fuel Elements for the Enrico Fermi Fast Breeder Reactor (open access)

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

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.
Date: 1964
Creator: Donnelly, R. G.; Thurber, W. C. & Slaughter, G. M.
System: The UNT Digital Library
Fuel Cycle Costs for a Plutonium Recycle System (open access)

Fuel Cycle Costs for a Plutonium Recycle System

Report containing the estimated costs of the chemical and metallurgical steps in plutonium recycling for large desalination reactors.
Date: January 20, 1964
Creator: Harrington, F. E.; Arnold, E. D.; Brater, D. C.; Douglas, D. A.; Smiley, S. H.; Stockdale, W. G. et al.
System: The UNT Digital Library
The High Flux Isotope Reactor: Volume 2, Selected Construction Drawings (open access)

The High Flux Isotope Reactor: Volume 2, Selected Construction Drawings

Report containing a series of drawings detailing the Oak Ridge National Laboratory's high flux isotope reactor, its surroundings, and its systems.
Date: August 1964
Creator: Binford, F. T.; Cramer, E. N. & Cramer, E. N.
System: The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1964 (open access)

Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1964

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date: November 13, 1964
Creator: Aerojet-General Corporation
System: The UNT Digital Library
Gas-Cooled Fast Reactor Concepts (open access)

Gas-Cooled Fast Reactor Concepts

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: Oak Ridge National Laboratory. Reactor Division. Gas-Cooled Reactor Project.
System: The UNT Digital Library