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Liquid Metal Fast Breeder Reactor Design Study

Description: From introduction: "The primary objective of the present study was to develop a conceptual design of a large sodium cooled fast breeder reactor of a nominal electrical rating of 1000 Mw operating on the uranium-plutonium cycle."
Date: January 1964
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analytical Electron Microscopy Characterization of Fernald soils. Annual Report, October 1993 - September 1994

Description: A combination of backscattered electron imaging and analytical electron microscopy (AEM) with electron diffraction have been used to determine the physical and chemical properties of uranium contamination in soils from the Fernald Environmental Management Project in Ohio. The information gained from these studies has been used in the development and testing of remediation technologies.
Date: March 1995
Creator: Buck, E. C.; Brown, N. R. & Dietz, N. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Test Plan for Reactions Between Spent Fuel and J-13 Well Water Under Unsaturated Conditions

Description: Two complentary test plans are presented, one to examine the reaction of spent fuel and J-13 well water under unsaturated conditions and the second to examine the reaction of unirradiated uranium dioxide pellets and J-13 well water under unsaturated conditions. The former test plan examines the importance of the water content, the oxygen content as affected by radiolysis, the fuel burnup, fuel surface area, and temperature. The latter test plant examines the effect of the non-presence of Teflon… more
Date: January 1993
Creator: Finn, P. A.; Wronkiewicz, David J.; Hoh, J. C.; Emery, J. W.; Hafenrichter, L. D. & Bates, J. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Dissolution Characteristics of Mixed UO₂ Powders in J-13 Water Under Saturated Conditions

Description: The Yucca Mountain Project/Spent Fuel program at Argonne National Laboratory is designed to determine radionuclide release rates by exposing high-level waste to repository-relevant groundwater. To gain experience for the tests with spent fuel, a scoping experiment was conducted at room temperature to determine the uranium release rate from an unirradiated uranium dioxide powder mixture (14.3 wt % enrichment in uranium-235) to J-13 water under saturated conditions. Another goal set for the exper… more
Date: March 1991
Creator: Veleckis, Ewald & Hoh, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Fabrication of Stainless Steel-Uranium Dioxide Fuel Elements

Description: Abstract: "Stainless steel-clad fuel sheet 0.020 in. thick with a 0.008-in. core of stainless steel plus UO2 was produced by roll cladding a powder metal compact. The effects of processing variables, core-matrix composition, quantity of oxide, and oxide particle size on the properties of the sheet were investigated. The strength and ductility of the core decreased sharply as the quantity of oxide in the core increased from 20 to 40 w/o. Over the range of matrix compositions investigated the par… more
Date: March 2, 1954
Creator: Keeler, J. R.; Keller, D. L. & Cuddy, L. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Uranium Migration in UO₂-Bearing Ceramics

Description: This report follows a preliminary study on uranium migration in pressed and sintered UO2-bearing bodies based on MoSi2 or Al2O3.
Date: September 4, 1953
Creator: Quirk, J. F.; Smalley, A. K.; Duckworth, W. H. & Ferrell, Edward Francis.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Ceramic Investigations of UO₂

Description: This report covers the progress made on an intensive program to develop and evaluate UO2 as a possible fuel element for the PWR.
Date: June 16, 1955
Creator: Allison, Adrian G. & Duckworth, Winston H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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MoSi₂-UO₂ Ceramics for High-Temperature Fuel Elements

Description: This report follows a study that was aimed at the collection of experimental data needed to estimate the maximum safe temperatures and dispersed UO2 contents for MoSi2--UO2 fuel elements exposed to air.
Date: August 18, 1955
Creator: Gambino, John R.; Quirk, John F. & Duckworth, Winston Howard
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Identification of Slag Constituents from Uranium Metal Production Bombs

Description: Abstract: "X-ray and microscopic examination of slags from uranium metal production bombs which gave good and bad yields in the plant at St. Louis have indicated the significance of uranium oxide formation. Apparently the oxide (UO2) results from reaction of the UF4 with linear material, particularly with moisture in the liner."
Date: January 31, 1952
Creator: Vaughan, D. A.; Cocks, G. G. & Schwartz, C. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Progress Relating to Civilian Applications During September, 1958

Description: A report about thermal-conductivity and electrical-resistivity measurements made on a uranium-1.5 w/o zirconium alloy surrounded by NaK enclosed in a Zircaloy-2 capsule which were in poor agreement with measurements made directly on a uranium-1.5 w/o zirconium specimen.
Date: October 1, 1958
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Program Relating to Civilian Applications During October, 1958

Description: A report pertaining to the thermal-conductivity and electrical-resistivity measurements of uranium encapsulated in zircaloy-2 and surrounded with NaK as a heat-transfer material which is not in agreement with results obtained from unclad uranium.
Date: November 1, 1958
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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