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Mechanical Properties at Room Temperature of Four Cermets of Tungsten Carbide with Cobalt Binder

Description: "Room-temperature stress-strain curves are presented for compression, tension, and shear loadings on four compositions of tungsten carbide with cobalt binder. Values of modulus of elasticity, modulus of rigidity, Poisson's ratio in the elastic region, ultimate strength, density, and hardness for the four materials are tabulated" (p. 1).
Date: December 1954
Creator: Johnson, Aldie E., Jr.
Partner: UNT Libraries Government Documents Department
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Friction of possible solid lubricants with various crystal structures

Description: Report presenting a number of possible solid lubricants with various crystal structures tested in a low-speed, high-load, friction apparatus under conditions of continuous sliding. None of the solids tested were as effective as MoS2 but were at least as effective as zinc stearate and graphite in these tests. Results regarding common lubricants, layer-lattice structure, and low-shear-strength solids without layer-lattice structure are provided.
Date: December 1954
Creator: Peterson, Marshall B. & Johnson, Robert L.
Partner: UNT Libraries Government Documents Department
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Sodium Graphite Reactor Quarterly Progress Report for July-September, 1954

Description: Reactivity calculations have been performed for the steady-state Pu feedback technique outlined in the previous progress report. A full-scale power plant study was initiated, based on sodium-graprite technology. A twin-core power plant is now considered to be the most promising configuration. Several design drawings are given of such a reactor, using slightly enriched U to produce Pu amd electrical power. The thermal neutron flux distribution in a cluster of 6 U rods was measured, and the resul… more
Date: December 1, 1954
Creator: Siegel, S. & Inman, G. M.
Partner: UNT Libraries Government Documents Department
open access

Sodium Graphite Reactor. Quarterly Progress Report, July-September 1954

Description: Technology of the Sodium Graphite Reactor. Reactivity calculations were made to study the application of steadystate plutonium feedback techniques to the use of diffusion plant tails for reactor fuel feed material. The performance and design of a twin core SGR power plant are given. Thermal neutron flux distribution measurements are reported for a six-rod fuel cluster and for a hollow uranium rod. A power cost calculation was made for a 1000-Mw SGR Th-U/sup 233/ breeder reactor which starts up … more
Date: December 1, 1954
Creator: Siegel, S. & Inman, G.M. eds.
Partner: UNT Libraries Government Documents Department
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