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Evaluation of Ultimate Disposal Methods for Liquid and Solid Radioactive Wastes: Part 2, Conversion to Solid by Pot Calcination
Economic and hazards calculation of pot calcination of Purex and Thorex wastes.
Date:
October 16, 1961
Creator:
Perona, J. J.; Bradshaw, R. L.; Roberts, J. T. & Blomeke, J. O.
System:
The UNT Digital Library
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
Homogeneous Reactor Project Quarterly Progress Report: May-July 1957
Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date:
October 10, 1957
Creator:
Briggs, R. B.; Winters, C. E.; Beall, S. E.; Lane, J. A.; Bohlmann, E. G.; Ferguson, D. E. et al.
System:
The UNT Digital Library
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
Health Physics Division Annual Progress Report, July 31, 1961
Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.
Date:
October 31, 1961
Creator:
Oak Ridge National Laboratory. Health Physics 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
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
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