Health Physics Division Annual Progress Report, July 31, 1969 (open access)

Health Physics Division Annual Progress Report, July 31, 1969

From summary: "Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory."
Date: October 1969
Creator: Oak Ridge National Laboratory. Health Physics Division.
System: The UNT Digital Library
Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1969 (open access)

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

Report documenting the ongoing research and development of the Oak Ridge National Laboratory's Chemical Technology Division.
Date: October 1969
Creator: Oak Ridge National Laboratory. Chemical Technology 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
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
Specifications and Procedures Used in Manufacturing U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor (open access)

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

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.
Date: October 21, 1963
Creator: Kucera, W. J.; Leitten, C. F., Jr. & Beaver, R. J.
System: The UNT Digital Library