Download or read book Uranium Dioxide Fuel Materials with Improved Thermal Conductivity written by H. Shapiro and published by . This book was released on 1959 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Uranium Dioxide written by J. Belle and published by . This book was released on 1961 with total page 750 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide written by Masato Kato and published by CRC Press. This book was released on 2022-10-17 with total page 183 pages. Available in PDF, EPUB and Kindle. Book excerpt: Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide offers a deep understanding of MOX properties for nuclear fuels that will be useful for performance evaluation. It also reviews fuel property simulation technology and an irradiation behavior model required for performance evaluation. Based on research findings, the book investigates various physical property data in order to develop MOX fuel for sodium-cooled fast reactors. It discusses a database of MOX properties, including oxygen potential, melting temperature, the lattice parameter, sound speeds, thermal expansion, thermal diffusivity, oxygen self-diffusion, and chemical diffusion coefficients, that was used to derive a science-based model of MOX properties (Sci-M Pro) for fuel-performance code development. Features: Concisely covers the essential aspects of MOX nuclear fuels. Explores MOX nuclear fuels by systematically evaluating various physical property values using a behavior model. Presents fuel property simulation technology. Considers oxygen potential, the lattice parameter, sound speeds, and oxygen self-diffusion. Discusses melting temperature, thermal expansion, thermal diffusivity, and chemical diffusion coefficients. The book will be useful for researchers and engineers working in the field of nuclear fuels and nuclear materials.

Download or read book An Innovative High Thermal Conductivity Fuel Design written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Thermal conductivity of the fuel in today's Light Water Reactors, Uranium dioxide, can be improved by incorporating a uniformly distributed heat conducting network of a higher conductivity material, Silicon Carbide. The higher thermal conductivity of SiC along with its other prominent reactor-grade properties makes it a potential material to address some of the related issues when used in UO2 [97% TD]. This ongoing research, in collaboration with the University of Florida, aims to investigate the feasibility and develop a formal methodology of producing the resultant composite oxide fuel. Calculations of effective thermal conductivity of the new fuel as a function of %SiC for certain percentages and as a function of temperature are presented as a preliminary approach. The effective thermal conductivities are obtained at different temperatures from 600K to 1600K. The corresponding polynomial equations for the temperature-dependent thermal conductivities are given based on the simulation results. Heat transfer mechanism in this fuel is explained using a finite volume approach and validated against existing empirical models. FLUENT 6.1.22 was used for thermal conductivity calculations and to estimate reduction in centerline temperatures achievable within such a fuel rod. Later, computer codes COMBINE-PC and VENTURE-PC were deployed to estimate the fuel enrichment required, to maintain the same burnup levels, corresponding to a volume percent addition of SiC.

Download or read book Uranium Dioxide written by J. Belle and published by . This book was released on 1961 with total page 744 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Symposium on Powder Packed Uranium Dioxide Fuel Elements written by Combustion Engineering, inc. Nuclear Division and published by . This book was released on 1961 with total page 184 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Metal Oxides in Energy Technologies written by Yuping Wu and published by Elsevier. This book was released on 2018-10-05 with total page 452 pages. Available in PDF, EPUB and Kindle. Book excerpt: Metal Oxides in Energy Technologies provides, for the first time, a look at the wide range of energy applications of metal oxides. Topics covered include metal oxides materials and their applications in batteries, supercapacitors, fuel cells, solar cells, supercapacitors, and much more. The book is written by an experienced author of over 240 papers in peer-reviewed journals who was also been recognized as one of Thomson Reuter’s “World’s Most Influential Scientific Minds in 2015. This book presents a unique work that is ideal for academic researchers and engineers. Presents an authoritative overview on metal oxides in energy technologies as written by an expert author who has published extensively in the area Offers up-to-date coverage of a large, rapidly growing and complex literature Focuses on applications, making it an ideal resource for those who want to apply this knowledge in industry

Download or read book Evaluation of Non Oxide Fuel for Fission based Nuclear Reactors on Spacecraft written by Dakota J. Allen and published by . This book was released on 2018 with total page 206 pages. Available in PDF, EPUB and Kindle. Book excerpt: The goal of this project was to study the performance of atypical uranium-based fuels in a nuclear reactor capable of producing 1 megawatt of thermal power with a 15-year core life for space-based applications. Specifically, the project investigated the use of uranium-molybdenum (UMo), uranium nitride (UN), or uranium carbide (UC) and compared their performance to uranium oxide (UO2) which is the fuel form used in the vast majority of commercial nuclear reactor applications. These alternative fuels have improved thermal conductivity and higher uranium loading density as compared to UO2. Improved thermal conductivity of the fuel allows a design with lower peak core temperatures thereby reducing the chance of violating thermal limits of core materials. Fuel with higher uranium loading density can have more of the fissile uranium-235 isotope present per unit of volume. This allows a design with a smaller and potentially lighter core, which is a significant advantage. The results of this study indicate that use of both UC and UN may result in significant weight savings due to higher uranium loading density. UMo is an effective fuel for use with low fuel burnup and low power applications. This study indicates that, due to restrictive operational temperature limits and adverse response to fission product gas buildup, UMo is inappropriate for designs requiring operation at high temperature, high power, and long duration such as is specified for the design under consideration.

Download or read book Summaries of Fuels and Materials Development Programs written by and published by . This book was released on 1960 with total page 114 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Information Circular written by and published by . This book was released on 1961 with total page 918 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Properties of UO2 written by J. Belle and published by . This book was released on 1957 with total page 146 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Metallurgy of Nuclear Fuel written by V. S. Yemel'Yanov and published by Elsevier. This book was released on 2013-10-22 with total page 600 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Metallurgy of Nuclear Fuel: Properties and Principles of the Technology of Uranium, Thorium and Plutonium is a systematic analysis of the metallurgy of nuclear fuel, with emphasis on the physical, mechanical, and chemical properties as well as the technology of uranium, thorium, and plutonium, together with their alloys and compounds. The minerals and raw material sources of nuclear fuel are discussed, along with the principles of the technology of the raw material processing and the production of the principal compounds, and of the pure metals and alloys. Comprised of three parts, this volume begins with an introduction to the history of the discovery of uranium and its position in the periodic system; its use as a nuclear fuel; radioactivity and isotopic composition; alloys and compounds; and physical, mechanical, and chemical properties. The effect of mechanical and thermal treatment, thermal cycling and irradiation on the physicochemical properties of uranium is also examined. The next two sections are devoted to thorium and plutonium and includes chapters dealing with their uses, alloys and compounds, and methods of recovery and purification. This book is written for university students, but should also prove useful to young production engineers and scientific workers who are concerned with problems in the metallurgy of nuclear fuel.

Download or read book Thermal Conductivity of Uranium Dioxide and Armco Iron by an Improved Radial Heat Flow Technique written by and published by . This book was released on 1964 with total page 78 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Fuels and Materials Development written by and published by . This book was released on 1961 with total page 176 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Effect of Solid Solution Additions on the Thermal Conductivity of UO2 written by Richard M. Powers and published by . This book was released on 1960 with total page 134 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fabrication of Uranium Oxide Fuel Elements written by G. Rolland Cole and published by . This book was released on 1959 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt: Experimental fuel elements of UO2 clad in metallic sheaths were fabricated by swaging, rolling, and coextrusion. The effects of the type of UO2 and of the materials and dimensions of the sheath were investigated. Fused UO2 swaged in stainless steel tubing reached a maximum density of 93% of theoretical.

Download or read book Reactor Core Materials written by and published by . This book was released on 1959 with total page 244 pages. Available in PDF, EPUB and Kindle. Book excerpt: