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Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores

Description: The following progress reports continues the investigation of the HCl-acetone process for extracting uranium, discovering that it is applicable to most Western ores, yielding high uranium recoveries. The economics of the process have been improved by substitution of sulfuric acid for part of the hydrochloric acid requirements.
Date: April 20, 1954
Creator: Ewing, R. A.; Pobereskin, M.; Kiehl, S. J.; Foley, D. D.; Filbert, Robert B.; Kimball, R. B. et al.
Partner: UNT Libraries Government Documents Department
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Electroplated Metals on Uranium

Description: The following report follows the studies of electroplating on uranium and concurrent metallurgical clodding.
Date: May 7, 1954
Creator: Beach, John G.; Schickner, W. C.; Konecny, C. R. & Faust, Charles L.
Partner: UNT Libraries Government Documents Department
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A Recirculating Supercritical Water Loop

Description: From Abstract: "A recirculating high-pressure stainless steel loop was developed for the study of heat transfer from small-bore tubes to supercritical water. It was found that under certain conditions, hot spots developed on the test section. The conditions leading to the formation of hot spots were investigated; the results of several runs are tabulated here."
Date: October 25, 1954
Creator: Epstein, H. M.; Goldthwaite, W. H.; Chastain, Joel W. & Fawcett, Sherwood L.
Partner: UNT Libraries Government Documents Department
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A Recirculating Supercritical Water Loop

Description: From abstract: "A recirculating high-pressure stainless steel loop was developed for the study of heat transfer from small-bore tubes to supercritical water. It was found that under certain conditions, hot spots developed on the test section. The conditions leading to the formation of hot spots were investigated; the results of several runs are tabulated here."
Date: October 25, 1954
Creator: Epstein, H. M.; Goldthwaite, W. H.; Chastain, Joel W. & Fawcett, Sherwood L.
Partner: UNT Libraries Government Documents Department
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The Fabrication of Subassemblies for the Supercritical-Water Reactor

Description: In studies of the fabrication of fuel subassemblies for the supercritical-water reactor, the limited ductility of stainless steel-UO₂ fuel sheet made the fabrication of corrugated-flat-plate-type subassemblies impractical. A fabricable MTR-type assembly, 5/8 in. square and 30 in. long, was developed. Methods for edge cladding fuel sheet were developed and a brazing alloy, GE-75, was found to be corrosion resistant in supercritical water.
Date: August 16, 1954
Creator: Keeler, J. R. & Hare, Alan W.
Partner: UNT Libraries Government Documents Department
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Nondestructive Measurements of Aluminum and Nickel Layers on Uranium

Description: From introduction: "This report covers the development of nondestructive techniques for measuring quantitatively: (1) thickness of electrodeposited-nickel diffusion barriers, and (2) thickness of aluminum cladding on flat-plate fuel elements."
Date: June 12, 1954
Creator: Glaze, E. W.; Rhoten, M. L.; Kulp, B. A.; Cooley, K. D. & Wenk, S. A.
Partner: UNT Libraries Government Documents Department
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Corrosion of Type 347 Stainless Steel in the Uranium-Derby Pickle Bath

Description: Abstract: In one of the final stages of the process at the Mallinckrodt Uranium Refining Center, a 45 per cent nitric acid solution at about 170 F is used to pickle the calcined magnesium fluoride scale off the uranium derbies. The increase in the fluoride-ion content of the bath tends to promote corrosion of the Type 347 stainless tanks. This attack becomes excessive if 0.3 g/liter of fluoride ion or more is present. It was found that if aluminum ion is added to the solution the corrosiveness … more
Date: July 14, 1954
Creator: Peoples, R. S.; Fink, F. W.; Stewart, O. M. & Braun, W. J.
Partner: UNT Libraries Government Documents Department
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Evaluation of Methods of Brazing Aluminum Spacing Fins to Flat-Plate Aluminum-Clad Fuel Elements

Description: Abstract: "Four brazing methods and one other joining process were evaluated for the joining of aluminum spacer fins to flat-plate aluminum-clad fuel elements. None of these methods appear completely suitable for use in a mass-production operation. Furnace brazing and salt-bath brazing were most promising. However, the mechanical problems involved in the application of either process deter their recommendation. Resistance brazing and torch-brazing were proven impractical. The great difference i… more
Date: July 23, 1954
Creator: Evans, R. M. & Martin, D. C.
Partner: UNT Libraries Government Documents Department
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The Effects of Chemical Impurities on the Quality of Rolled Uranium Rod

Description: Abstract: "Thirty-four uranium ingots containing controlled amounts of carbon, nitrogen, and Mgl2 slag were cast, rolled, and examined to investigate the relation between these impurities and the quality of the rolled rod. Carbon in concentrations up to 1400 ppm and nitrogen up to 170 ppm, either singly or in combination, had no significant effect on the number of defects observed in the rolled rod. The quality of the rods, however decreased with increasing amount of slag necessary to cause obs… more
Date: October 1, 1954
Creator: Saller, Henry A.; Keeler, J. R. & Cuddy, L. J.
Partner: UNT Libraries Government Documents Department
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A study of the dip coating of uranium sheet with aluminum-silicon alloy

Description: A report which covers an investigation of techniques for producing hot-dip Al-Si coatings on uranium sheet. Also, the study is concerned with the effects of time and temperature of dipping on the intermetallic zone and its ductility.
Date: 1954
Creator: Cawthorne, E. W.; Craighead, C. M; Berry, Warren E., 1922-; Pray, H. A. & Jaffee, Robert Isaac, 1917-
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.
Partner: UNT Libraries Government Documents Department
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Temperature distributions in a reactor fuel plate

Description: A report about the effects upon the fuel plate temperatures of introducing channel spacers into the proposed curved plate subassembly for the super critical water reactor.
Date: 1954
Creator: Redmond, R. F.; Chastain, Joel W.; Long, J. K.; Jung, R. G. & Fawcett, Sherwood L.
Partner: UNT Libraries Government Documents Department
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Temperature distributions in a reactor fuel plate

Description: A report pertaining to heat-transfer characteristics , the supercritical water reactor, and flat fuel plates separated by cylindrical spacers perpendicular to the plates.
Date: 1954
Creator: Long, J. K.; Chastain, Joel W.; Redmond, R. F.; Jung, R. G. & Fawcett, Sherwood L.
Partner: UNT Libraries Government Documents Department
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