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Welding Thin-Walled Uranium Cylinders

Description: One of Its Monograph Series, The Industrial Atom.'' The development of a satisfactory process for the fusion welding of thin-walled uranium cylinders is discussed. Optimum results were obtained using the inert-gas shielded-arc method without the use of filler metal. The ductility of the welded joints, however, was lower than that of cast metal. Surface conditions and and the purity of the inert gas used affected the weld soundness. Straight polarity direct current was used for welding to achieve maximum penetration and to provide are stability. Welding must be done in the flat position. (auth)
Date: January 1, 1957
Creator: Brundige, E.L.; Taub, J.M.; Hanks, G.S. & Doll, D.T.
Partner: UNT Libraries Government Documents Department


Description: A study was made of the effect of the addition of V aad Si on the properties of Th; corrosion of stainless steel in uranyl sulfate; corrosion, brazing, and welding of stainless steel; properties of Ti; method of combining deuterium and O for return to the reactor; spot welding of fuel elements; fabrication of reactor fuel elements; mechanical testing of U, Th, and stainless steel; surface rearrangements on a single crystal of Cu in contact with a saturated solution of Cu in Bi; development of cermets for reactor components; fabrication of Th-U fuel elements and Al-U alloy componerts. (J.E.D.)
Date: April 1, 1953
Creator: Bridges, W.H. ed.
Partner: UNT Libraries Government Documents Department

FUNDAMENTALS OF SINTERING--II. Second Annual Progress Report, June 30, 1956 to June 30, 1957

Description: Rates of spheroidization and densification of gold and of nickel wire compacts were measured as a function of time, temperature, and wire size. The necks joining the sintered particles were found to grow proportionally to the one- fifth root of time. The value of the coefficient of self-difiusion calculated from the sintering rate is of the sane order of magnitude as that obtained by ordinary tracer techniques but with a somewhat higher activation energy. These results are entirely consistent with those predicted by the Kuczyrski diffusional theory of sintering, as is the effect of wire size on sintering rate. The experiments did not reveal a clear effect of grain boundaries on sintering rates. This may be due to a relatively slow densification of the nickel wire compacts at even 0.98 of the absolute melting point, which obscured the effect of grain growth on sintering rate. (auth)
Date: February 15, 1958
Creator: Pranatis, A.L.; Castleman, L.S. & Seigle, L.
Partner: UNT Libraries Government Documents Department


Description: The unclassified literature on the joining of beryllium was surveyed and is summarized. The fields covered are fusion welding, self-welding (diffusion- or pressure-welding), and brazing. The most successful attempts in each field are outlined and other work is referenced. (aauth)
Date: June 1, 1958
Creator: Brown, N.A.
Partner: UNT Libraries Government Documents Department


Description: The first group of Pu--Al MTR fuel elements fubricated were rejected for excessive dimensions and blistering. The fuel element constitution and fubrication was reviewed, and a new Pu--Al ratio and revised rolling techniques were suggested. (D.E.B.)
Date: August 1, 1956
Creator: Beaver, R.J.
Partner: UNT Libraries Government Documents Department


Description: >Progress is reported in the extrusion of Cu-clad Zr billets into tubing, welding of Zr strip into tubing using a roder resistance welding tube mill, piercing of Zr billets into a base tube, the casting and fabrication of U-- Nb alloys, the rolling of Zircaloy sheet, the roll-cladding of Zircaloy to U--Nb alloys, the fabrication of plate type reactor fuel elements of U--Hb alloys roll bonded with Zircaloy, fabrication of a complete U/sup 235/--Zr fuel slug for the EBR, the fabrication of U-- Zr alloy rod into EBR fuel blanket slugs, the thermal cycling of U-- Zr rods following heat treatment, the fubrication of enriched U reactor fuses, the preparation and dimensional stability of U single crystals, twinning in U crystals, diffusion in Cu- U couples, the fabrication of U billets from electrolytic crystals, the preparation of U-- Zr and Hb--U alloys, effects of radiation on U, the effects of radiation on U-- Zr alloys, the corrosion of Al, Zr, and Nb-U alloys, and the effects of heat treatments on Hb-- U alloys. (C.H.)
Date: September 30, 1953
Partner: UNT Libraries Government Documents Department

Atomization Method of Making Uranium Powder

Description: Atomized U powder was produced by forming an electric arc between two U electrodes in an inert atmosphere and sending a high velocity stream of inert gas through the arc. Uranium particles obtained by this method were of spherical shape; smaller particles contained mostly small grains, and larger particles wore characterizcd by larger grains. The particles were ductile and could be hotpressed to a compact of high density. The temporary equipment used for those preliminary tests on atomization was not adequate to control particle size. Suggestions for the production of atomized U powder of controllable quality are included. (arth)
Date: August 1, 1950
Creator: Hausner, H. H. & Mansfield, H.
Partner: UNT Libraries Government Documents Department


Description: The U--Zr phase diagram is presented. Melting points of B and other oxides ahove 2000 deg C were determined. The structure of Ca and Sr aluminates was refined, and Al/sub 2/)/sub 3/UO/sub 2/ bodies were fabricated. Techniques for impregnating leached unfired Vycor are being standardized. The effects of radiation on hardness of Vycor and on Pu-- U oxides have been obtained. (C.H.)
Date: October 31, 1958
Creator: Bruch, C.A. & Cashin, W.M.
Partner: UNT Libraries Government Documents Department

The System Zirconium-Iron-Tin. Status Report No. 4 for July 1, 1957- March 31, 1958

Description: A study of the solubility limits of iron and tin in alpha zirconium at temperatares below 500 deg C is in progress. Dilute alloys were prepared by arc- melting using the highest purity materials. Heat treatment of the alloys involves homogenizntion at 800 deg C followed by severe cold work prior to extended anneals at temperatures between 200 and 500 deg C in 50-degree intervals. Metallographic examination of annealed and quenched structures is the primary mode of investigation. Some magnetic susceptibility studies were also made. (auth)
Date: April 24, 1958
Creator: Tanner, L. E.
Partner: UNT Libraries Government Documents Department