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SIGMA PLUG WELDING OF SPUN-OVER FUEL CANS

Description: Efforts made to employ the sigma welding process for plug welding Closures in spun-over fuel cans were unsuccessful. No combination of welding conditions was found which would produce satisfactory, leak-tight, plug welds in aluminum. (auth)
Date: December 1, 1952
Creator: Winsor, F.J.
Partner: UNT Libraries Government Documents Department

LOW ENERGY CROSS SECTIONS FOR THE D-D AND D-T REACTIONS

Description: Previous computations of cross sections for the D-D and D-T reactions were dependent on the knowledge of the energy loss of deuterons and tritons in D{sub 2}O ice targets. Recent Published experimental data on the energy loss dE/dx of protons in H{sub 2} and O{sub 2} have been sufficiently consistent to correct the results of the measurements of Bretscher, French and Sidel (Phys. Rev. 73, 815 (1948) and 75, 1154 (1949). Without describing the methods used to obtain the new data, the author uses the results of the dE/dx measurements to correct the cross sections of Bretscher et al. A simple correction factor is given, and the corrected values are tabulated for the D-D and D-T reactions. The Gamow formula, modified by a resonance factor, is applied to the revised data, and a good fit to the theoretical slope is obtained.
Date: January 1, 1952
Creator: Cook, C.J.; Jones, E. & Jorgensen, T.
Partner: UNT Libraries Government Documents Department

METALLURGY DIVISION QUARTERLY PROGRESS REPORT FOR PERIOD ENDING APRIL 30, 1952

Description: Thorium Research. The effect of quenching temperature on the hardness of Th--C alloys is described. The effect of quenching temperature and oxygen content on the hardness of Th--O, alloys is discussed. The effects of Be, Cr, and C additions on the properties of pure Th are described. The mechanical properties, recrystallization, and fabrication of Th are given. Preferred Orientation of Uranium. Fabricating conditions, preferred orientation, and examination of alpha-extruded U rods are given. The creep rate of beta-treated normal U and of extruded Th is given. Properties of some high-temperature brazing alloys are given. Welding conditions are given for cone-arc welding of stainless steel tube-to-header joints. Homogeneous Reactor Program. Analysis of various compacts containing B/sub 4/C are given. Preliminary work on the variables involved in welding Ti was started. Experimental work to determine the effects of various impurity elements on the impact properties of Ti and Zr was started. A metallographic examination of Ames Th cold worked and annealed for 60 minutes is presented. Experimental Plate-Cladding Program. The cladding of Th and U with Zr is discussed at length. The cladding of Th with Al is described. Experiments on welding of Th, U, and Zr plates are presented. (W.L.H.)
Date: September 22, 1952
Creator: Bridges, W.H. ed.
Partner: UNT Libraries Government Documents Department

METALLURGY DIVISION QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JANUARY 31, 1952

Description: Progress is reported on the following projects: Th alloy development, mechanical properties of Th, tensile properties and preferred orientation of Th, triple-dip slug canning, texture studies, fundumental studies of alloying, static cerrosion tests with low melting point alloys, dynamic corrosion testing of fluoride materials, mass transfer, structures of liquid Pb and liquid Bi, fabrication of tubular laminates for fuel elements, creep of Th, cone-arc welding, Homogeneous Reactor Experiment metallurgy, a low-temperature specimen holder for use with the highangle x-ray spectrometers, metallography of Zr and its alloys, automatic polishing machine, a fuel element manufacturing process for the direct-cycle aircraft reactor, and fabrication of fuel and control rod elements for the MTR. (L.T.W.)
Date: August 28, 1952
Creator: Bridges, W.H. ed.
Partner: UNT Libraries Government Documents Department

METALLURGY DIVISION QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JULY 31, 1952

Description: The effect of strain rate on the tensile properties of thorium is being investigated. It was found that the yield strength increases slightly with increasing strain rate, and that tensile strength increases but to a lesser extent. The shear modulus was determined to be 4.26 x 10/sup 6/ psi. A preprocess thorium was made, giving a value of 5.0871 plus or minus 0.0002 A. Studies on the fabrication of thorium by extrusion and drawing were continued, as were studies on the extrusion cladding of thorium and uranium with zirconium. In order to determine whether or not the type of preferred orientation developed in alpha -extruded uranium rod was dependent on the actual extrusion temperature, x- raydiffraction studies were made of completely recrystallized and unrecrystallized extruded uranium. The results show that the texture developed upon deformation is not always retained upon recrystallization. The corrosion testing of various metals and alloys in liquid sodium, lead, and lithium and in molten fluorides and hydroxides was continued. The interaction of sodium with 316 stainless steel appears negligible during static testing. The testing of the molten media in thermal convection loops continues to be plagged by failures other than corrosion. The investigation of means of fabrication of solid fuel elements by powder metallurgy techniques has progressed. Only minor segregation of U0/sub 2/ in an iron matrix was noted after hot rolling. Stainless steel matrices, on the other hand, displayed considerable segregation. Rubberstatic pressing was added as a technique for the fabrication of fuel elements and control rods. The Creep Laboratory is essentially complete. The stady of thermocouple stability in vacuum has shown that chromel-alumel couples give consistent checks with control and reference temperatures, whereas iron- constantan and platinum- 10% rhodium couples gave erratic results. Some preliminary results were obtained on uranium, thorium, 316 stainless steel, ...
Date: February 1, 1952
Creator: Miller, E.C. & Bridges, W.H. eds.
Partner: UNT Libraries Government Documents Department

METALLURGY DIVISION QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JULY 31, 1952

Description: Physicsl Metsllurgy of Reactor Materials. Mechanical properties of a series of Th--C alloys ranging in C content from 0.02 to 0.22% wcre determined. The effect of quenching temperature on the hardness of pure Th was investigated. The effcct of aging temperature on the hardness of Th-- Cr alloys was determined. The effect of quenching temperature on the hardness of Th--Cr--C alloys is given. Data are given on the mechanical properties of Ames Th. The effect of cold work on the recrystallization of Th is described. Reactor Component Fabrication. A picture frame method of Zr cladding of U is described. A method of sealing the sheared edge of Zr clad U plate by edge welding is presented. Zirconium cladding of Th is described. Fundamental Physico-Metallurgical Research. A tentative phase diagram of the Ag--Zr system is prescnted. The preparation of In -- Zr alloys by arc-melting methods is described. (W.L.H.)
Date: December 1, 1952
Creator: Bridges, W.H. ed.
Partner: UNT Libraries Government Documents Department