12 Matching Results

Search Results

Results: 1 - 12
open access

Creep Strength of Uranium Alloys at 1500 and 1800 F

Description: Abstract:"The creep resistance of various uranium binary alloys was investigated at 1500 and 1800 F in vacuum. Tests were made on alloys of uranium with beryllium, columbium, molybdenum, tantalum, titanium, and zirconium and on molybdenum-UO2 composites. Of the alloys examined, those of the uranium-molybdenum system exhibited the best creep resistance. At 1500 F, creep rates of about 0.005%/hr were produced in uranium-molybdenum alloys by a stress of 2500 psi and, at 1800 F, similar creep rates… more
Date: May 28, 1953
Creator: Saller, Henry A.; Stacy, J. T.; Eddy, N. S. & Klebanow, H. L.
Partner: UNT Libraries Government Documents Department
open access

Electroplated Metals on Uranium for Aluminum Cladding

Description: Abstract: "Aluminum-clad nickel-plated uranium is corrosion resistant in boiling water. Samples with intentional defects in the aluminum-nickel clodding layers, after testing for more than 300 hr. showed no sign of rapid failure. The study of electroplated metals on uranium for aluminum cladding has defined the effects of several processing variables on the corrosion resistance. The quality of the uranium and the quality of the aluminum-nickel bond were important. Heat treatment and vacuum outg… more
Date: May 4, 1955
Creator: Beach, John G.; Schickner, William C.; Hopkinson, Dolores. & Faust, Charles L.
Partner: UNT Libraries Government Documents Department
open access

Grain Refinement of the As-Cast Uranium-5 w/o Chromium Alloy by Heat Treatment

Description: Introduction: "The uranium-5 w/o chromium alloy has been intensively investigated for use in a power reactor in the as-cast condition. However, when cast sample fuel elements were subjected to irradiation, their stability was found to be unsatisfactory. In order to improve the behavior of the alloy, a program of grain refinement by heat treatment was begun. The effect of chill casting on the heat-treated grain size was also investigated."
Date: May 13, 1955
Creator: Saller, Henry A.; Rough, Frank A. & Bauer, Arthur A.
Partner: UNT Libraries Government Documents Department
open access

Low-Melting Alloys for Cast Fuel Elements

Description: The following report follows an investigation made to determine the composition of uranium-rich ternary eutectic alloys most suitable for reactor application in the as-cast condition. These determinations were made based metallographic examination and thermal analysis of as-cast alloys.
Date: May 19, 1955
Creator: Saller, Henry A.; Rough, Frank A. & Bauer, Arthur A.
Partner: UNT Libraries Government Documents Department
open access

Engineering Properties of High-Density Concretes

Description: From summary: "Methods were developed for measuring various engineering properties of high-density concretes. Data are presented on selected thermal properties of a limonite-iron concrete and the mechanical properties of the limonite-iron concrete, a magnesium oxychloride concrete, and a Portland cement concrete containing steel punchings and shot (no limonite)."
Date: May 1951
Creator: Snyder, M. Jack; Burkart, C. A. & Clegg, John W.
Partner: UNT Libraries Government Documents Department
open access

The Determination of Rare Earths in Thorium

Description: Abstract: "A quantitative method for the determination of individual rare earths in thorium down to a level of 0.05 ppm, is described. The procedure consists of a chromatographic cellulose-columns separation followed by a solution-type spectrographic determination. Values are given for the recovery of a number of rare earths using this combined procedure."
Date: May 15, 1952
Creator: Center, E. J.; Henry, W. M. & Householder, R. D.
Partner: UNT Libraries Government Documents Department
open access

Identification of Reaction Products Formed During Magnesium Reduction of Uranium Tetrafluoride: Report

Description: Abstract: "This report describes the results of X-ray diffraction examination of reaction products from a series of experiments performed by Mallinckrodt Chemical Works as an acid in understanding the process of bomb reduction of UF4. UF4 is initially reduced to UF3 by magnesium at 560 C., and subsequently to metal at 600 C. MgF2 from the initial reaction forms a coating on the magnesium which retards the final spontaneous reaction."
Date: May 15, 1953
Creator: Schwartz, C. M. & Vaughan, D. A.
Partner: UNT Libraries Government Documents Department
open access

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
open access

Properties of Stainless Steel-Uranium Dioxide Fuel Plates

Description: From abstract: "A method for fabricating 30-in.-long stainless steel - uranium dioxide sheet was developed and the properties of the fabricated sheet were investigated."
Date: May 11, 1954
Creator: Keeler, J. R. & Cuddy, L. J.
Partner: UNT Libraries Government Documents Department
open access

Investigation of Methods for End Capping Stainless Steel Pins

Description: This report follows investigations of methods for sealing the ends of stainless steel-uranium oxide fuel pins with the objective to develop an end-capping method that would give consistently good-quality closures in production.
Date: May 18, 1956
Creator: Vagi, Julius J.; Thompson, Harold B. & Martin, David C.
Partner: UNT Libraries Government Documents Department
open access

The Stability and Existence Range of the Zirconium-Uranium Epsilon Phase

Description: Report discussing studies regarding properties of the zirconium-uranium epsilon phase related to stability and existence range. Data showing this phase's thermodynamic stability is presented as well as the zirconium-uranium constitutional diagram. Oxygen and nitrogen effects on zirconium-uranium alloys and epsilon-phase alloys is included as well as ternary zirconium-uranium-oxygen diagrams.
Date: May 28, 1956
Creator: Rough, Frank A.; Austin, Alfred E.; Bauer, Arthur A. & Doig, J. Robert
Partner: UNT Libraries Government Documents Department
open access

Fabrication of Dispersed Uranium Fuel Elements Using Powder-Metallurgy Techniques

Description: Abstract: "Fabrication techniques for producing dispersion fuel elements with cores of 30 volume per cost of UC, U2Tl, U3Si, or U6Ni dispersed in Zircology 2 and 30 volume per cent of UC or UN dispersed in Type 18-8 stainless steel have been investigated. Roll-clad plate-type elements of all these compositions may be fabricated by powder-metallurgy methods in such a manner that good core-to-cladding bonds and cores with uniform dispersions of discrete uranium-composed particles are obtained. Fr… more
Date: May 6, 1957
Creator: Paprocki, Stan J.; Keller, Donald L. & Cunningham, G. W.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen