Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores (open access)

Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores

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.
System: The UNT Digital Library
Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores (open access)

Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores

This report describes progress in testing non-aqueous extraction methods for leaching Western ores of uranium and vanadium.
Date: April 15, 1953
Creator: Ewing, R. A.; Pobereskin, M.; Kimball, R. B. & Bearse, A. E.
System: The UNT Digital Library
Welding of High-Strength Stainless Steels for Pressure Vessels (open access)

Welding of High-Strength Stainless Steels for Pressure Vessels

The following report describes the welding characteristics of several high-strength stainless steels that were considered for use as a pressure vessel to operate at high pressures at 800 F.
Date: April 5, 1954
Creator: Vagi, J. J.; Thompson, V. R. & Martin, D. C.
System: The UNT Digital Library
The Effects of Ternary Alloying Additions on the Corrosion Resistance of Epsilon-Phase Uranium-Zirconium Alloys (open access)

The Effects of Ternary Alloying Additions on the Corrosion Resistance of Epsilon-Phase Uranium-Zirconium Alloys

Abstract: "The corrosion rate in 680 F water of the uranium-50 w/o zirconium binary alloy was found to be -0.20 mg/(cm2)(hr), and that of the uranium-40 w/o zirconium binary alloy was -0.34 mg/(cm2)(hr). Both alloys correlated uniformly, with no evidence of discontinuous failure. Normal variations in interstitial content in either alloy had no significant effect on corrosion behavior. Tantalum additions, in the range of 0.2 to 5 w/o, improved the corrosion rate of the uranium-50 w/o zirconium base, with a minimum rate of -0.06 mg/(cm2)(hr) for the 5 w/o tantalum alloy. The 5 w/o tantalum addition to the uranium-40 w/o zirconium alloy. The 5 w/o tantalum addition to the uranium-40 w/o zirconium alloy decreased the corrosion rate of the base to -0.11 mg/(cm2)(hr) in the [...] condition only. In either conditions, the 5 w/o tantalum alloy failed discontinuously. All other additions to both bases either had no effect or decreased corrosion resistance. These included aluminum, chromium, iron, molybdenum, nickel, platinum, tin, titanium, tungsten, and vanadium additions."
Date: April 27, 1956
Creator: Reynolds, James E.; Berry, Warren E., 1922-; Ogden, Horace R.; Peoples, Robert S. & Jaffee, Robert Isaac, 1917-
System: The UNT Digital Library
Study of Aluminum Alloys Containing Up to 45 W/O Uranium (open access)

Study of Aluminum Alloys Containing Up to 45 W/O Uranium

Report discussing a study on casting techniques for the production of sound homogeneous extrusion blanks composed of aluminum-uranium alloys with 30 to 45 w/o uranium.
Date: April 30, 1957
Creator: Daniel, Norman E.; Foster, Ellis L.; DeMastry, John A.; Bauer, Arthur A. & Dickerson, Ronald F.
System: The UNT Digital Library
Hazards Summary Report for the Battelle Research Reactor (open access)

Hazards Summary Report for the Battelle Research Reactor

From summary: "This report was prepared for the Advisory Committee on Reactor Safeguards for their review and consideration of the potential hazards concerning the Battelle Memorial Institute Research Reactor."
Date: April 4, 1955
Creator: Chastain, J. W.; Redmond, R. F.; Klickman, A.; Anno, J. & Fawcett, S. L.
System: The UNT Digital Library