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Non-Core Dry Hole Drilling at Cove Mesa, Arizona

Description: Abstract: A drilling program was conducted by the Atomic Energy Commission on Cove Mesa, Arizona to further develop uranium and vanadium ore reserves that are vital to the National Defense. The drilling was performed by the Minerals Engineering Company of Grand Junction, Colorado. Uranium and vanadium ore horizons are found in the Salt Wash member of the Morrison formation on Cove Mesa.
Date: June 16, 1952
Creator: Garcia, Raymond J.
Partner: UNT Libraries Government Documents Department
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The Distribution of Uranium-Vanadium Deposits in the Colorado Plateau Relative to Tertiary Intrusive Masses

Description: Introduction: Studies of uranium-vanadium occurrences in the Four Corners region show that, with the exception of the Lukachuai area, all of the major deposits in the Morrison formation are grouped around the various igneous masses which are scattered irregularly throughout the Colorado Plateau. The pattern of deposition varies from mountain group to mountain group and each will be described separately. Maps accompany this report to supplement the descriptions of ore occurrences in the vicinity… more
Date: June 11, 1952
Creator: Reinhardt, Elmer V.
Partner: UNT Libraries Government Documents Department
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Uranium in the Dirty Devil Shimarump Channel Deposit

Description: From abstract: Uranium ores occur in a river channel deposit of composite type. Uranium and its daughter elements segregate during migration and each has its own accumulator. The entire deposit stays close to radioactive equilibrium but individual mineral components have departures up to 1000 fold.
Date: June 1952
Creator: Bain, George W.
Partner: UNT Libraries Government Documents Department
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Reaction of Graphic with Sodium

Description: Most of the publications in the open literature available to us agree that sodium does not readily react with graphite, though potassium, rubidium, and cesium readily enter between the planes of the graphite lattice. In view of the conflicting evidence available, it seems inadvisable without very extensive further study to consider the use of graphite in direct contact with liquid sodium, except under very mild conditions of temperature and irradiation, and then only with very pure sodium and c… more
Date: June 19, 1952
Creator: Montet, G. L.
Partner: UNT Libraries Government Documents Department
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Some Comments on the Fission to Capture Cross Section Ratio

Description: Abstract: An attempt is made to correlate the thermal neutron fission cross sections of various nuclides. An empirical relationship is observed when the logs of the ratios [thermal neutron fission cross section of (Z,A)/thermal neutron capture cross section of (Z,A)] for several nuclides are plotted against their neutron binding energies [binding energy of a neutron to (Z,A)]. The log of the σf/σc ratio decreases markedly with decreasing neutron binding energy."
Date: June 1952
Creator: Huizenga, John R.
Partner: UNT Libraries Government Documents Department
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Effect of Fluoride on the Gravimetric Determination of Zirconium in Zirconium Fluoride

Description: Abstract: "The results of this investigation that it is necessary to remove fluoride prior to precipitation zirconium with mandelic acid or phenyl arsonic acid. Fluoride, however, has little effect on the cupferron method of precipitation. The discovery that zirconium fluoride is soluble in a mixture of aqua regia and sulfuric acid made it possible to dissolve the material without the addition of fluoride from hydrofluoric acid."
Date: June 3, 1952
Creator: McCutchen, R. L. & Susano, C. D.
Partner: UNT Libraries Government Documents Department
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Flux Distributions and Critical k [infinity] Values for Cylindrical Reactors Simulation the MTR

Description: From summary: "In order to estimate the effect of placing bismuth and thorium layers near the MTR core, radial flux distributions and k[infinity] values were calculated for cylindrical reactors having cylindrical layers of these materials of the same height as the core and beryllium reflector and placed either next to the core or embedded in the beryllium reflector."
Date: June 25, 1952
Creator: Bray, D. T. & McMurry, Henry Lewis, {}
Partner: UNT Libraries Government Documents Department
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Optimum Water Velocity for the Converter Reactor

Description: Abstract: "Two cases are considered. In Case I, the reactor water velocity is optimized to obtain a minimum annual cost (including amortization and operating costs) for the cooling system along. The optimum velocity for a 310 megawatt reactor is calculated to be ~25 feet per second, compared to the present design value of 30 feet per second. In Case II, the velocity which will give the minimum cost of product under the assumptions of varying power and production rate is found to be in the range… more
Date: June 18, 1952
Creator: Cooley, William C.
Partner: UNT Libraries Government Documents Department
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Bismuth Casting and Canning : (Information Report)

Description: Introduction: The experimental work at Mound Laboratory on bismuth casting and the sealing of aluminum irradiation containers is an outgrowth of the bismuth recovery project. Since the recovered bismuth contains residual activity it is necessary that the bismuth be processed to the point that no contamination will result from shipment or any subsequent operations required to prepare the bismuth for irradiation. In order to satisfy these requirements the work here has consisted of investigating … more
Date: June 16, 1952
Creator: Engle, Paul
Partner: UNT Libraries Government Documents Department
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Single Bend Tests on Welded Zirconium and Zirconium-Tin Alloys

Description: Introduction: "Since it has been found that zirconium and zirconium-tin alloys may be embrittled by certain heat treatments, it was decided to determine if welding of these materials affects their ductility in any way. A single bend test in both the longitudinal and transverse directions was used for evaluation of the variables considered."
Date: June 4, 1952
Creator: Hoge, H. R.
Partner: UNT Libraries Government Documents Department
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The Variation in Maximum Power Density and Maximum Heat Flux of the Core and Blanket Thorium Plates in the Converter Reactor with Irradiation Time

Description: This report describes how to achieve the variation in maximum power density and maximum heat flux of the core and blanket thorium plates in the converter reactor with irradiation time.
Date: June 23, 1952
Creator: Sletten, H. L.
Partner: UNT Libraries Government Documents Department
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Drift Tube Model Magnet Report

Description: Early in the design of the Mark I accelerator it was decided to install magnetic lenses in the drift tubes. A number of model magnets were constructed and tested to determine the best design for these lenses. This report includes only the results of the tests on the final models of the magnets that are designed for Mark I.
Date: June 27, 1952
Creator: Sewell, D. & Parmentier, H.
Partner: UNT Libraries Government Documents Department
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An Investigation of the Isotopes of Americium and Curium

Description: Isotopes of americium and curium with mass numbers less than 242 have been produced by cyclotron bombardment techniques, and several of their nuclear properties have been investigated. The partial alpha half-lives of Am(239), Cm(241), and Cm(240) and the partial half-life for spontaneous fission of Cm(240) were measured. The alpha decay daughter of Cm(238) was found and evidence for the discovery of Am(237) (an -1 hour electron capture activity) and Cm(239) (an -10 hour electron capture activ… more
Date: June 1952
Creator: Higgins, Gary Hoyt
Partner: UNT Libraries Government Documents Department
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Neutron Streaming in a Cylindrical Cavity

Description: The free streaming of neutrons in a cylindrical cavity is investigated. Using experimental data for the flux distribution along the walls, the direct beam hole loss and leakage into the target from the lattice is estimated for the MTA system.
Date: June 4, 1952
Creator: LeLevier, R.
Partner: UNT Libraries Government Documents Department
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Three Group Equations for a Multiplying Medium

Description: In the past it was felt that the easiest way to treat a three group equation for a MTA lattice was to solve it without certain terms. This iterative procedure converged rapidly for a medium with depleted uranium fuel, and in fact, a second iteration was not needed.
Date: June 11, 1952
Creator: Adelman, F. L.
Partner: UNT Libraries Government Documents Department
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Preliminary Leaching Investigation of Ores From Radium Hill, South Australia

Description: Leaching tests indicated high recoveries could be obtained by use of large quantities of sulfuric acid and boiling for relatively long periods. Filtration rates were satisfactory but large settling areas would be required to wash and thicken before filtering.
Date: June 30, 1952
Creator: Hollis, R. F.; Breymann, J. B. & Lynch, J. T.
Partner: UNT Libraries Government Documents Department
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