Oxidation-reduction Reprocessing of Uranium Carbide Reactor Fuel

Oxidation-reduction Reprocessing of Uranium Carbide Reactor Fuel
Title Oxidation-reduction Reprocessing of Uranium Carbide Reactor Fuel PDF eBook
Author W. G. Smiley
Publisher
Pages 30
Release 1962
Genre Nuclear fuels
ISBN

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Oxidation-Reduction Reprocessing of Uranium Carbide Reactor Fuel. I. Carbothermic Reduction of UO$sub 2$

Oxidation-Reduction Reprocessing of Uranium Carbide Reactor Fuel. I. Carbothermic Reduction of UO$sub 2$
Title Oxidation-Reduction Reprocessing of Uranium Carbide Reactor Fuel. I. Carbothermic Reduction of UO$sub 2$ PDF eBook
Author
Publisher
Pages
Release 1962
Genre
ISBN

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Gram-scale experiments on the carbothermic reduction of UO/sub 2/ were carried out as part of an investigation of oxidation-reduction reprocessing of UC. UO/sub 2/, from air oxidation of UC, was mixed with graphite powder and heated in vacuum at 1300 to 1700 deg C, both as loose powder and as pellets. The best container material was carbide-coated graphite; molybdenum was satisfactory with pellets. Information on reaction rates was obtained by measuring the evolved carbon monoxide with a gas meter. In the powder experiments, the carbon content of the products agreed with predicted values, with a standard deviation of 0.069 wt%. The carbon content of products from pellets was low by 0.25 wt%, with a standard deviation of 0.076 wt%. This is believed to be an effect of the acrylic plastic binder. Reaction rates followed a second-order rate equation, except that thc rate constant often decreased abruptly at about 90% completion. Correlation between rate and temperature was poor; for 32 values of the rate constant, K (reciprocal hours), the least squares equation was: log K = 9.8216,080/T, with a standard error of 0.20 in log K. The data also agree fairly well (standard error, 0.22) with the hypothesis that the activation energy is equal to the heat of the endothermic reaction. Because of variations in the rate, it is recommended that the reaction of each batch should be followed with a gas meter, in order to obtain a desired degree of completion. (auth).

Reprocessing Studies on Irradiated Uranium Carbide Reactor Fuel

Reprocessing Studies on Irradiated Uranium Carbide Reactor Fuel
Title Reprocessing Studies on Irradiated Uranium Carbide Reactor Fuel PDF eBook
Author J. E. Bodine
Publisher
Pages 22
Release 1962
Genre Carbides
ISBN

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Oxidation-reduction Reprocessing of Uranium Carbide Reactor Fuel

Oxidation-reduction Reprocessing of Uranium Carbide Reactor Fuel
Title Oxidation-reduction Reprocessing of Uranium Carbide Reactor Fuel PDF eBook
Author W. G. Smiley
Publisher
Pages 38
Release 1965
Genre Fission products
ISBN

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Processing of Uranium Carbide Reactor Fuels

Processing of Uranium Carbide Reactor Fuels
Title Processing of Uranium Carbide Reactor Fuels PDF eBook
Author M. J. Bradley
Publisher
Pages 26
Release 1961
Genre Carbides
ISBN

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Low Decontamination Reprocessing Studies on Irradiated Uranium Oxide Reactor Fuel

Low Decontamination Reprocessing Studies on Irradiated Uranium Oxide Reactor Fuel
Title Low Decontamination Reprocessing Studies on Irradiated Uranium Oxide Reactor Fuel PDF eBook
Author J. Guon
Publisher
Pages 44
Release 1962
Genre Reactor fuel reprocessing
ISBN

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Symposium on Reprocessing of Nuclear Fuels

Symposium on Reprocessing of Nuclear Fuels
Title Symposium on Reprocessing of Nuclear Fuels PDF eBook
Author P. Chiotti
Publisher
Pages 772
Release 1969
Genre Nuclear fuels
ISBN

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