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Book The Nature and Properties of the Carbides of Uranium

Download or read book The Nature and Properties of the Carbides of Uranium written by O. O. Gamba and published by . This book was released on 1965 with total page 64 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Properties of Uranium Monocarbide

Download or read book Properties of Uranium Monocarbide written by C. A. Smith and published by . This book was released on 1959 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Carbides in Nuclear Energy  Physical and chemical properties  phase diagrams   v  2  Preparation and fabrication  irradiation behaviour

Download or read book Carbides in Nuclear Energy Physical and chemical properties phase diagrams v 2 Preparation and fabrication irradiation behaviour written by Lewis Eric Russell and published by . This book was released on 1964 with total page 508 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The Chemical Reactivity of Uranium Carbide

Download or read book The Chemical Reactivity 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:

Book Processing of Uranium Carbide Reactor Fuels

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:

Book U Uranium

    Book Details:
  • Author : H. Holleck
  • Publisher : Springer Science & Business Media
  • Release : 2013-11-11
  • ISBN : 3662107163
  • Pages : 295 pages

Download or read book U Uranium written by H. Holleck and published by Springer Science & Business Media. This book was released on 2013-11-11 with total page 295 pages. Available in PDF, EPUB and Kindle. Book excerpt: The present volume Uranium C12 covers the binary and polynary carbides of uranium, including ternary carbides with nonmetals like the carbide oxides and carbide nitrides U(C,O) and U(C,N). The binary carbide UC and especially the mixed carbide (UO.80PUO.20)C are of special importance due to their potential as the fuel for advanced .. Fast Breeder Reactors" because of properties such as the short doubling time, the high fissionable material density, and the good thermal conductivity. On the other hand, the dicarbide UC is of interest for .. High 2 Temperature Reactors", especially in the form of the mixed carbide (U . Th . )C . For O80 o20 2 the first time, India used mixed uranium-plutonium carbide (U . PU .)C as the fuel for its O3 O7 own newly developed 15 MW Fast Breeder Reactor at Kalpakkam, south of Madras. el Because of the technological importance of the uranium carbides a lot of data were published only in reports. In most cases, it was the aim of these less-scientifically based studies to promote the carbide fuel development on an economical basis. The lack of analyti cal data on the purity of the samples, missing characterization of the present phases, etc., hQINever, does not allow the discussion of the results of such references in this handbook. Therefore, only reliable publications were cited. For the technical fabrication of uranium carbides and their irradiation behavior, see Volumes A3 and A4 of this Handbook.

Book Carbides in Nuclear Energy

Download or read book Carbides in Nuclear Energy written by and published by . This book was released on 1964 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Thermal Expansion of Uranium Monocarbide

Download or read book Thermal Expansion of Uranium Monocarbide written by R. Mendez-Peñalosa and published by . This book was released on 1963 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Oxidation of Uranium Carbide by Carbon Dioxide

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:

Book Uranium Carbides  Nitrides  and Silicides

Download or read book Uranium Carbides Nitrides and Silicides written by International Atomic Energy Agency and published by . This book was released on 1965 with total page 204 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nonequilibrium Uranium Carbide Phase Relationships

Download or read book Nonequilibrium Uranium Carbide Phase Relationships written by E. E. Ritchie and published by . This book was released on 1965 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Uranium Carbides  Nitrides  and Silicides

Download or read book Uranium Carbides Nitrides and Silicides written by and published by . This book was released on 1968 with total page 126 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Carbides

    Book Details:
  • Author : T. Y. Kosolapova
  • Publisher : Springer Science & Business Media
  • Release : 2012-12-06
  • ISBN : 1468480065
  • Pages : 311 pages

Download or read book Carbides written by T. Y. Kosolapova and published by Springer Science & Business Media. This book was released on 2012-12-06 with total page 311 pages. Available in PDF, EPUB and Kindle. Book excerpt: I The Structure and Physicochemical Properties of Carbides.- Structures.- Thermodynamic and thermophysical properties.- Electrophysical and magnetic properties.- Physicomechanical properties.- Chemical properties.- II Methods of Producing Carbides.- III Carbides of Metals of Group I.- Carbides of the alkali metals.- Carbides of metals of the copper subgroup.- IV Carbides of Metals of Group II.- Carbides of beryllium, magnesium, and the alkaline-earth metals.- Carbides of the zinc subgroup.- V Carbides of the Transition Metals.- Carbides of scandium, yttrium, and the lanthanides.- Carbides of t.

Book Fission Gas Bubble Behavior in Uranium Carbide

Download or read book Fission Gas Bubble Behavior in Uranium Carbide written by Christopher Matthews and published by . This book was released on 2015 with total page 183 pages. Available in PDF, EPUB and Kindle. Book excerpt: The need for cheap reliable energy, while simultaneously avoiding uranium supply constraints makes uranium carbide (UC) fueled Gas Fast Reactors offer an attractive nuclear reactor design. In order to qualify the fuel, an enhanced understanding of the behavior of uranium carbide during operation is paramount. Due to a reduced re-solution rate, uranium carbide suffers from a buildup of very large fission gas bubbles. While these bubbles serve to reduce total fission gas release through the trapping of diffusing gas atoms, they lead to high swelling and ultimately dominate the microstructure of the fuel. The bubble size distribution is determined by the competing absorption rate and the rate of knock-out, or re-solution. As a result of the enhanced thermal dissipative properties of uranium carbide fuel, the atom-by-atom knockout process was shown to be an accurate representation of re-solution in uranium carbide. Furthermore, the Binary Collision Approximation was shown to appropriately model the re-solution event, bypassing computationally expensive Molecular Dynamics simulations. The code 3DOT was developed as an off-shoot of the code 3DTrim, both of which utilize the TRIM algorithm to calculate the kinematics of ions traveling through a material. Benefiting from modern methods and enhanced computational power, the model created in 3DOT results in a more fundamental understanding of the re-solution process in uranium carbide. A re-solution parameter that was an order of magnitude lower than previously determined was cal- culated in 3DOT. A decrease in the re-solution parameter as a function of radius occurred for low bubble radii, with a nearly constant re-solution parameter for bubble radii above 50 nm. Through comparative studies on the re-solution parameter for various values of implantation energy and atomic density in the bubble, we found that while the re-solution parameter did change slightly, the overall shape did not. A new application, BUCK, was built using the MOOSE framework to simulate the fission gas bubble concentration distribution. In order to build a bare-bones foundation, the simplistic yet historically prevalent physics that can be used to model fission gas bubble nucleation, growth, and knock-out were implemented as stepping stones until more advanced models for each physical process can be created. As the first step towards models that are based on first-principles, the new re-solution parameter was included and tested within BUCK. BUCK was tested using different parameters and behaved normally. However, from studies using representative simulation parameters, it is clear that the currently implemented theory does not adequately identify the growth mechanism that leads to larger bubbles. While this currently limits the applicability of BUCK in a full fuel pin calculation, it provides the baseline structure in which new physics can be implemented, and represents an important step towards understanding the complex behavior of fission gas bubbles.

Book Uranium Carbides  Nitrides and Silicides  1963 1965

Download or read book Uranium Carbides Nitrides and Silicides 1963 1965 written by International Atomic Energy Agency and published by . This book was released on 1966 with total page 196 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Uranium Carbides  Nitrides and Silicides  1966 1967

Download or read book Uranium Carbides Nitrides and Silicides 1966 1967 written by International Atomic Energy Agency and published by . This book was released on 1968 with total page 126 pages. Available in PDF, EPUB and Kindle. Book excerpt: