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Calculation of Suspension Peptization

Description: Report regarding the combination the theories of flocculation, particle repulsion, and particle attraction in order to "understand the flocculation characteristics of TH02 suspensions" (p. 2).
Date: 1960
Creator: Sweeton, F. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Laboratory Development of a Tributyl Phosphate Solvent Extraction Process for Processing 20% Enriched Uranium Alloy Fuel

Description: Report containing a preliminary chemical flowsheet "for the preparation of feed and two solvent extraction cycles for the processing of silicon-containing aluminum-uranium alloy, 20% enriched, fuel elements" (p. 2).
Date: 1961
Creator: Goode, J. H. & Flanary, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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

Description: 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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Corrosion of the Volatility Pilot Plant INOR-8 Hydrofluorinator and Nickel 201 Fluorinator During Forty Fuel-Pprocessing Runs with Zirconium-Uranium Alloy

Description: Report documenting the corrosion of fluorinators of the Oak Ridge National Laboratory's volatility pilot plant. Includes descriptions of the fluorinators, their operating environments, and the results of their corrosion.
Date: March 1965
Creator: Youngblood, E. L.; Milford, R. P.; Nicol, R. G. & Ruch, J. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design Report for Nuclear Merchant Ship Reactor Pressurized Water Loop at Oak Ridge National Laboratory Research Reactor

Description: Report describing a pressurized water loop that was constructed for use in the Maritime Reactor Program. The report also includes the operational experience of using the device. Appendices begin on page 48.
Date: 1963
Creator: Dudley, I. T.; Tidwell, D. E. & Trauger, Donald B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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