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Comparative Cost Study of Processing Stainless Steel-Jacketed UO2 Fuel: Mechanical Shear-Leach vs Sulfex-Core Dissolution

Description: Comparison of the economics of mechanical shear-leach and Sulfex decladding-core dissolution head end treatments for processing typical tubular bundles of stainless steel-jacketed UO2 nuclear fuels.
Date: April 23, 1962
Creator: Adams, J. B.; Benis, A. M. & Watson, C. D.
Partner: UNT Libraries Government Documents Department
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Thermal Conductivity of UO2

Description: Report discussing the thermal conductivity of uranium dioxide. The first part of the report includes the thermal effects on the substance's physical form, while the second part describes the experimental details.
Date: September 1962
Creator: Daniel, J. L.; Matolich, J., Jr. & Deem, H. W.
Partner: UNT Libraries Government Documents Department
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In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes: Part 2, May and June, 1962

Description: Report containing the results of a two year program wherein the 85 zircaloy-2 pressure tubes in Hanford Laboratories' Plutonium Recycle Test Reactor (PRTR) were monitored. Experimental procedures and results are described.
Date: August 1962
Creator: Doman, D. R. & Pankaskie, P. J.
Partner: UNT Libraries Government Documents Department
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Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements

Description: Report regarding the study of the calculated costs of fabricating plutonium-enriched fuel elements for Hanford Laboratories' Plutonium Recycle Program. Topics include descriptions of the process, design study of plants that use U235 and plutonium enriched fuel, and estimates of costs.
Date: August 1962
Creator: Hanthorn, H. E.
Partner: UNT Libraries Government Documents Department
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In-Pile Loop Investigations of Corrosion of Zircaloy-2 and Other Possible Reactor Materials in 0.04 m UO2SO4 AT 280°C

Description: One of a series of experiments to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various radiation intensities, temperatures, solution compositions, and velocities of flow past specimens.
Date: May 5, 1962
Creator: Jenks, G. H.
Partner: UNT Libraries Government Documents Department
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Darex Process: Processing of Stainless Steel-Containing Reactor Fuels with Dilute Aqua Regia

Description: From abstract: "The Darex process developed for the recovery of uranium from stainless steel-containing reactor fuels consists of three steps: (1) dissolution of the fuel material in dilute aqua regia, (2) removal of chloride from the solution to prevent corrosion of downstream stainless steel process equipment, and (3) adjustment of the nitrate solution to solvent extraction feed conditions."
Date: June 7, 1962
Creator: Kitts, F. G. & Clark, W. E.
Partner: UNT Libraries Government Documents Department
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