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Cascade design considerations for cascades composed of stages with large separation factors

Description: The unit cost of product from ideal and nonideal cascades are calculated and compared for a given separation task, that of producing reactor grade uranium containing 3.2% U-235 from normal feed containing 0.72% U-235, under the assumption that the total cascade costs are directly proportional to the total inter-stage flow of the cascade. For the examples chosen, in which the stage separation factors are in the range 2 < ..cap alpha.. < 5 and the resulting cascades contain from four to six stage… more
Date: February 1, 1978
Creator: Von Halle, E.
Partner: UNT Libraries Government Documents Department
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Enrichment supply and technology outside the United States

Description: This is a review of foreign uranium enrichment capacity and uranium isotope separation technology, based on news items and articles in the public literature. Tables are included presenting capacity plans, growth, sales, research and development, etc. (DLC)
Date: January 13, 1977
Creator: Levin, S. A. & Blumkin, S.
Partner: UNT Libraries Government Documents Department
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Calculation of multicomponent flows in the aerodynamic separation of uranium isotopes

Description: Equations governing gas flow containing uranium hexafluoride and an inert carrier have been developed for mixtures typical of those used in aerodynamic isotope separation. In this report these equations are solved for a simple separation device (two-dimensional channel with external force). The numerical solutions are compared with the results obtained from direct simulation.
Date: March 1, 1976
Creator: Eaton, R. R. & Fox, R. L.
Partner: UNT Libraries Government Documents Department
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Isotope separation in crossed-jet systems

Description: The separation of isotopes in crossed-jet systems was investigated with Monte Carlo calculations of the separation effects for jets of Ne/Ar and /sup 235/UF/sub 6///sup 238/UF/sub 6/ mixtures entering a hydrogen stream. For the ideal condition of uniform stream velocities at zero temperature, the separation factor ..cap alpha.. was found to be 16.0 for Ne/Ar and 1.17 for /sup 235/UF/sub 6///sup 238/UF/sub 6/. For less ideal but more practical conditions, Monte Carlo calculations of the complete… more
Date: November 1, 1978
Creator: Gallagher, R. J. & Anderson, J. B.
Partner: UNT Libraries Government Documents Department
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Alternative technologies for meeting uranium enrichment demands

Description: The current U.S. program to expand the capacity of gaseous diffusion plants is described and the status of the CIP/CUP programs summarized. Work being conducted on the design of an 8.75-million SWU/y add-on plant to the Portsmouth diffusion cascade is also reported. The status of the U.S. government gas centrifuge program is reported on. Other processes being under evaluation include laser isotope separation and aerodynamic separation. 13 figures (DLC)
Date: January 1, 1976
Creator: Vanstrum, P. R. & Wilcox, W. J., Jr.
Partner: UNT Libraries Government Documents Department
open access

Materials technology for accelerator production of fissile isotopes

Description: The materials used for the accelerator production of fissile isotopes must enable the facility to achieve maximum fuel production at a minimum cost. Neutron production in the target would be maximized by use of thorium cooled with Pb--56 percent Bi or with sodium. The thorium should be ion-plated with approximately 1 mil of nickel or stainless steel for retention of fission products. The target container will have to be replaced at frequent intervals because of the copious quantities of neutron… more
Date: February 1, 1978
Creator: Horak, J.A.
Partner: UNT Libraries Government Documents Department
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