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Estimation of Small Quantities of Uranium in Thorium

Description: Abstract: "Estimation of the intensity of the uranyl fluorescence furnishes a method for the determination of quantities of uranium as low as one-half microgram of uranium in one-half illilitor of glassy phosphoric acid. The test has been used to detect directly three parts of uranium in one million parts of thorium" (p. 1).
Date: 1946
Creator: Weissman, S. I. & Duffield, R. B.
Partner: UNT Libraries Government Documents Department

Report on a Magnetic Drive Design for the Fercleve Coporation

Description: This report discusses the development of a design for a "permanent magnet drive to couple a motor shaft with a pump impeller through a thick metallic diaphragm of small diameter. [...] The following report presents the procedures and results of the magnetic drive development up to date of cancellation and includes the general features of the design which would have been recommended if the contract had not been cancelled" (p. 1).
Date: 1946?
Creator: Williams, W. D.
Partner: UNT Libraries Government Documents Department

Treatment of Torbernite

Description: Production of black oxide from torbernite was studied on a laboratory scale from the standpoint of uranium extraction, reagent requirements, and removal of impurities. A small portion of the material was examined for its mineral constituents, using optical properties, X-ray diffraction patterns, and chemical analysis for identification. About 50% of the material was quartz; 30% green crystals of a copper-uranium phosphate; 10% of a black mineral, which was not identified, but which appeared to be an oxide mixture of nickel, cobalt, copper, and molybdenum; and small amounts of gibbsite, laterite and feldspar. There were no lower oxides of uranium in the sample.
Date: January 21, 1946
Creator: Brimm, E. O., Dr.
Partner: UNT Libraries Government Documents Department

A Study of the Distribution of Impurities in the Extraction of Uranyl Nitrate with Ether from Aqueous Solutions

Description: Early in 1942 it had been found on a laboratory scale that certain impurities such as the Rare Earths were removed by small water washes from an ether solution of Uranyl Nitrate. It was hoped that in the large production units to be constructed that the water soluble impurities would all be washed out by the time the radioactive Thorium had been removed, so that the decrease in radioactivity could be used as an index of the amount of all kinds of impurity remaining in the ether layer. Experience has taught both the production and the laboratory chemist to view with suspicion a process which claims to separate one element from all others in the periodic system with a simple set of manipulations such as an extraction. Furthermore, there is the familiar example of iodide ion which anyone would expect to be oxidized to iodine and then be transferred almost quantitatively to the ether layer from which it would not wash out. It seemed reasonable that other elements or ions would be found which would fail to wash out of the ether layer. Since the objective was the removal of the neutron absorbers whether their danger coefficients were especially high or not, it became important that every possible check on the effectiveness of the extraction method was investigated. Furthemore there was a probability that the concentration of any individual impurity in different batches of raw material would vary over a wide range. The question was raised whether a large increase in the concentration of some ions would either make the washing of the ether layer unsuccessful or uneconomical.
Date: April 1, 1946
Creator: Conard, C. R.
Partner: UNT Libraries Government Documents Department

Comparison of Normal Process and Single Process (XC) Uranium

Description: Certain difficulties have been encountered in attempts to substitute a 'one-step' casting process, developed at Iowa State College, for the 'normal' process generally used for the production of extrusion billets. In the 'one-step' process molten metal is delivered from the reduction bomb to the billet mold instead of allowing the metal to solidify in the bomb with subsequent vacuum remelting of the biscuit metal before casting in the billet mold. Routine analyses had failed to establish significant differences in the composition of normal and one-step metal. The one-step billets had been extruded satisfactorily, and finished slugs were prepared and subjected to the usual canning operation. In subsequent tests however, it was found that a large percentage of the canned slugs were badly defective. An investigation was requested to determine the differences in composition or structure of the X-C and normal metal which would account for the failure of the X-C slugs. Samples of the failed slugs and of metal from various stages of both the one-step and normal processes were supplied by Madison Square Area, for comparison on the basis of analyses, microstructure, or such other tests as seemed desirable.
Date: October 7, 1946
Creator: Cleaves, H. E.
Partner: UNT Libraries Government Documents Department

Supplemental and Summary Report on Western Carrizo Uplift and Chuska Mountains Areas of Northern Navajo Indian Reservation Northeastern Arizona

Description: General purpose of survey: During the period 1943 and 1944, the primary purpose was to locate, describe, sample, and generally evaluate the SOM-vanadium mineralization in the western Carrizo Uplift and Chuska Mountains Areas. To this end, the areal geology of the areas, with emphasis on the Salt Wash member of the Morrison formation, was mapped. The triangulation and the laying out of leased plots were supplemental parts of this work. The field work in 1945 was for the purpose of collecting additional and supplemental geological data in order to complete the record and to calculate the ore reserves of the areas.
Date: April 1946
Creator: Harshbarger, J. W.
Partner: UNT Libraries Government Documents Department

Geology and Ore Resources of the Uranium-Vanadium Depositional Province of the Colorado Plateau Region

Description: From introduction and acknowledgements: This report is written to supplement and complete the record contained in some fifty district and special reports already submitted, and duplication of material in district reports has been studiously avoided. The data herein contained are largely of a regional type, inclusion of which was not wholly appropriate to the district reports.
Date: 1946
Creator: Webber, Benjamin N.
Partner: UNT Libraries Government Documents Department

Neutron Diffusion in a Space Lattice of Fissionable and Absorbing Materials

Description: Methods are developed for estimating the effect on a critical assembly of fabricating it as a lattice rather than in the more simply interpreted homogeneous manner. An idealized case is discussed supposing an infinite medium in which fission, elastic scattering and absorption can occur, neutrons of only one velocity present, and the neutron m.f.p. independent of position and equal to unity with the unit of length use. (auth)
Date: August 27, 1946
Creator: Welton, T. A. & Feynman, R. P.
Partner: UNT Libraries Government Documents Department

Method for Measuring Fast Decay of a Near Critical Assembly

Description: This paper contains a description of the apparatus and theories of the methods successfully used for determining the fast decay periods of near-critical assemblies. The methods described are: (1) the modulation method and (2) the delayed coincidence or Rossi method
Date: July 14, 1946
Creator: Woodward, W.
Partner: UNT Libraries Government Documents Department


Description: The effects of temperature, time and other variables on the rate and extent of reaction between UF/sub 6/ and various types, grades and particle sizes of commercial activated carbon have been studied experimentally. It is shown that both hydrolysis and reduction of the UF/sub 6/ occur, the latter more slowly than the former. Reduction leads to the formation of a mixture of fluorocarbons ranging from CF/sub 4/ to a wax-like maternial volatile only above 250 deg C. There is also evidence for the adsorption of UF/sub 6/ on an undetermined substrate. (auth)
Date: April 12, 1946
Creator: Wilson, T.P.; Schuman, S.C. & Simons, E.L.
Partner: UNT Libraries Government Documents Department


Description: The favorible attention being given graphite as a fuel rod material calls attention to the need for preventing diffusion of fission products from the fuel rods. The methods of prevention include painting the surface of the rod with an impermeable organic synthetic composition, enclosing the rods in metal cans, electroplating the rods with a suitable metal, or covering the surface with some type of inorganic ceranmic glaze. Each of these methods is evaluated as to feasibility. (M.H.R.)
Date: October 22, 1946
Creator: Wilson, J.E.
Partner: UNT Libraries Government Documents Department


Description: Thermal reactors that have a significant fraction of fissioning occurring just above thermal energies are studied. First, the thermal neutron diffusion equation is corrected for fast fission effects. The resulting diffusion equation is shown to be equivalent to the Fermi Age equation corresponding to the same physical assumptions. Next, the one delayed neutron group kinetic equations for the corrected thermal flux are given, and the life time of the thermal neutron is corrected by the average slowing down time. (auth)
Date: August 23, 1946
Creator: Daniels, F.
Partner: UNT Libraries Government Documents Department