10 Matching Results

Search Results

Results: 1 - 10
open access

Fast Flux Test Facility Studies Progress Report: April 1965

Description: From abstract: "...limited study work was performed on the conceptual design of the proposed fast flux test facility and information was obtained in important areas of supporting technology."
Date: April 1965
Creator: Astley, E. R.
Partner: UNT Libraries Government Documents Department
open access

A Sequence for Predicting Waste Transport by Ground Water

Description: From introduction: "This paper describes a sequence for analyzing the effects of ground water flow on waste transport in natural soils."
Date: April 15, 1965
Creator: Nelson, R. William
Partner: UNT Libraries Government Documents Department
open access

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
open access

Welding of High-Strength Stainless Steels for Pressure Vessels

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

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

Description: 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 b… more
Date: April 27, 1956
Creator: Reynolds, James E.; Berry, Warren E., 1922-; Ogden, Horace R.; Peoples, Robert S. & Jaffee, Robert Isaac, 1917-
Partner: UNT Libraries Government Documents Department
open access

Corrosion of thorium and uranium during long-term storage

Description: From introduction: "The over-all objective of the present study was to determine the nature and extent of the present study was to determine the nature and extent of the corrosion of these materials under a variety of such storage conditions and to determine the ability of several potential protective coatings to retard this corrosion."
Date: April 10, 1962
Creator: Stephan, Elmer F.; Miller, P. D. & Fink, Frederick W.
Partner: UNT Libraries Government Documents Department
open access

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

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Hazards Summary Report for the Battelle Research Reactor

Description: 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.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen