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 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 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 Oxidation reduction Reprocessing of Uranium Carbide Reactor Fuel written by W. G. Smiley and published by . This book was released on 1965 with total page 38 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 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 Symposium on Reprocessing of Nuclear Fuels written by P. Chiotti and published by . This book was released on 1969 with total page 772 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book U Uranium written by and published by Springer Science & Business Media. This book was released on 2013-11-11 with total page 371 pages. Available in PDF, EPUB and Kindle. Book excerpt: The present volume A4 of the "Uranium" series of the Gmelin Handbook deals with two very important technological aspects of the nuclear fuel cycle: - the behavior of fuel elements during burnup in a nuclear reactor, and - the reprocessing of spent fuel to recover the non-fissioned uranium and newly created materials. The usefullifetime of a fuel element in a nuclear reactor depends strongly on the change of its chemical and physical properties during irradiation. Properties like thermal conductivity, swelling, creep, and oxygen-to-metal ratio are strongly affected by the intense neutron field and the energetic fission products. Furthermore, the high temperature gradient in a fuel element also produces alterations of the initial fuel. such as densification or U: Pu segregation. All of these effects are thoroughly discussed for the different kinds of fuels to be used in modern nuclear reactors today or in the future. The vast amount of very often Contradietory results in sometimes difficultly obtainable Iiterature has been summarized to create a compendium in this field with the two sections, on oxide and on carbide and nitride fuels, respectively. The chapters on reprocessing of spent fuels deal only with fuel elements of the uranium 235 thorium fuel cycle and with those containing fuel highly enriched in U. The treatment of U0 2 and (U,Pu)0 has already been given in the transuranic element series.

Download or read book Reactor Fuel Processing written by and published by . This book was released on 1963 with total page 726 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Comparative Cost Study of the Processing of Oxide Carbide and Metal Fast breeder reactor Fuels by Aqueous Volatility and Pyrochemical Methods written by M. Levenson and published by . This book was released on 1966 with total page 174 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Preparation and Processing of Particulate Nuclear Fuels written by and published by . This book was released on 1964 with total page 204 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 Status Report written by J. J. Reilly and published by . This book was released on 1961 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Progress in Carbide Fuels written by U.S. Atomic Energy Commission and published by . This book was released on 1960 with total page 100 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Reprocessing of Uranium carbide by a Nitrate carbide Cycle written by L. A. Hanson and published by . This book was released on 1963 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Reprocessing of Irradiated Fission Reactor Fuel and Breeding Materials written by and published by . This book was released on 1964 with total page 212 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Innovative Design of Uranium Startup Fast Reactors written by Tingzhou Fei and published by . This book was released on 2012 with total page 283 pages. Available in PDF, EPUB and Kindle. Book excerpt: Sodium Fast Reactors are one of the three candidates of GEN-IV fast reactors. Fast reactors play an important role in saving uranium resources and reducing nuclear wastes. Conventional fast reactors rely on transuranic fuels from reprocessing facilities, which are not available in the U.S. Thus, deployment of fast reactors requires decoupling from reprocessing facilities. This motivates the design and deployment of Uranium Startup sodium Fast Reactors (USFR) on a once-through fuel cycle in order to facilitate the transition to fast reactors by reducing their plant costs and increase capacity factor. Three different fuel types including uranium carbide (UC), metal (UZr) and uranium oxide (UO2) are investigated and analyzed using the ERANOS code for potential use in USFR designs. A key enabling factor is use of high-albedo MgO or Zr reflectors in place of fertile blankets to reduce uranium enrichment and improve non-proliferation resistance. The different compositions in different fuel types result in different neutronic performance. The softer spectrum and lower allowable fuel volume fractions of oxide fuel have shorter fuel cycle length due to reactivity constraints, whereas fast neutron fluence plays an important role in determining the fuel cycle length in metal cores due to the harder spectrum. Moderators are deliberately added in the metal fuels to lower the fast neutron fluence. Carbide cores have a slightly harder neutron spectrum than oxide cores and a larger achievable fuel volume fraction. USFRs using all three fuel types (UC, U0 2 and UZr) have lower fuel cycle cost (6.27, 6.09 and 5.77mills/kWhe) and comparable uranium consumption (0.50, 0.55, and 0.53kgNatU/MWde) compared with typical LWRs (6.39nills/kWhe and 0.53kgNatU/MWde). All USFR designs have maximum neutron fluence below 5E23n/cm2. All three USFR designs have pressure drop below 0.7MPa and maximum temperature below the limit for each fuel type. Both carbide and metal fuel have excellent passive safety performance. It is concluded that the USFR approach is a competitive way to accelerate fast reactor development.