Download or read book Oxidation Reduction Reprocessing of Uranium Carbide Reactor Fuel I Carbothermic Reduction of UO sub 2 written by and published by . This book was released on 1962 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: 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).
Download or read book Oxidation reduction Reprocessing of Uranium Carbide Reactor Fuel written by W. G. Smiley and published by . This book was released on 1962 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reprocessing Studies on Irradiated Uranium Carbide Reactor Fuel written by J. E. Bodine and published by . This book was released on 1962 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Processing of Uranium Carbide Reactor Fuels written by M. J. Bradley and published by . This book was released on 1961 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book THE CARBOTHERMIC REDUCTION OF URANIUM OXIDE written by and published by . This book was released on 1957 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Uranium oxide has been reduced by carbon under vacuum at 225O deg C, to yield a product consisting of dendritic uranium carbide in a matrix of uranium. Uranium sponge is obtained from this cermet by hydrolyzr-ng the interconnected UC. This is followed by pickling in dilute nitric acid to remove the residual hydrolysis product UO/sub 2/ x H/sub 2/O from the metal. As carried out on the 100-pound scale, the average over-all yield of uranium from 21 reductions was 31.2% per reduction cycle. The uranium is of high purity and is in a form that is well suited to direct arc melting with or without alloying, clad rolling, or powder metallurgical consolidation. (auth).
Download or read book Low Decontamination Reprocessing Studies on Irradiated Uranium Oxide Reactor Fuel written by J. Guon and published by . This book was released on 1962 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Preparation of Uranium Metal by Carbon Reduction written by W. G. Smiley and published by . This book was released on 1963 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Oxidation of Uranium Carbide by Carbon Dioxide written by E. W. Murbach and published by . This book was released on 1962 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976 with total page 612 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Pyrochemical Reprocessing of Uranium Carbide written by E. W. Murbach and published by . This book was released on 1965 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Oxidation of reactive Uranium Carbide written by E. W. Murbach and published by . This book was released on 1961 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reprocessing of Uranium Fuels by Selective Oxidation reduction Reactions in a Fused Salt liquid Metal System written by Sidney John Stephenson Parry and published by . This book was released on 1960 with total page 392 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reprocessing of Uranium Carbide by Molten Salt Electrolysis written by W. N. Hansen and published by . This book was released on 1963 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1973 with total page 1162 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reprocessing of Uranium Carbide by a Nitride carbide Cycle written by L. A. Hanson and published by . This book was released on 1964 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Uranium Dioxide Electrolysis written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This is a single stage process for treating spent nuclear fuel from light water reactors. The spent nuclear fuel, uranium oxide, UO.sub. 2, is added to a solution of UCl.sub. 4 dissolved in molten LiCl. A carbon anode and a metallic cathode is positioned in the molten salt bath. A power source is connected to the electrodes and a voltage greater than or equal to 1.3 volts is applied to the bath. At the anode, the carbon is oxidized to form carbon dioxide and uranium chloride. At the cathode, uranium is electroplated. The uranium chloride at the cathode reacts with more uranium oxide to continue the reaction. The process may also be used with other transuranic oxides and rare earth metal oxides.
Download or read book PROCESSING OF URANIUM CARBIDE REACTOR FUELS I REACTION WITH WATER AND HCL written by and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: High-purity uranium monocarbide reacted with water at 80 deg C to produce a finely divided, brown U(IV) compound, and 92 nfl (STP) of gas per gram consisting of 11 vol% hydrogen, 86 vol% methane, 2 vol% ethame, and 0.6 vol% propane. At 90 deg C, the products were the same, but the reaction rate was higher. Reaction with 5.6 M HCl was slower than with water, but the gaseous products were essentially the same. In preliminary experiments at 80 deg C with UC-UC2 mixtures containing less than 2 wt.% free carbon, the volume of gas evolved per gram of sample hydrolyzed decreased from 92 to 32 ml (STP) and the methane concentration from 86 to 14 vol% as the UC2 concentration in the mixture increased from 0 to about 63 wt.%. An attendant increase in the hydrogen and ethane concentrations to 23 and 38 vol%, respectively, also occurred. (anth).
