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Two And Three Dimensional Thermal Analyses Of Uranium Molybdenum Dispersion Fuel Microstructures
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Book Synopsis Two- and Three-dimensional Thermal Analyses of Uranium/molybdenum Dispersion Fuel Microstructures by : Brianna Coulson
Download or read book Two- and Three-dimensional Thermal Analyses of Uranium/molybdenum Dispersion Fuel Microstructures written by Brianna Coulson and published by . This book was released on 2012 with total page 76 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Analysis of Irradiated U-7wt%Mo Dispersion Fuel Microstructures Using Automated Image Processing by :
Download or read book Analysis of Irradiated U-7wt%Mo Dispersion Fuel Microstructures Using Automated Image Processing written by and published by . This book was released on 2016 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: The High Performance Research Reactor Fuel Development (HPPRFD) program is responsible for developing low enriched uranium (LEU) fuel substitutes for high performance reactors fueled with highly enriched uranium (HEU) that have not yet been converted to LEU. The uranium-molybdenum (U-Mo) fuel system was selected for this effort. In this study, fission gas pore segmentation was performed on U-7wt%Mo dispersion fuel samples at three separate fission densities using an automated image processing interface developed in MATLAB. Pore size distributions were attained that showed both expected and unexpected fission gas behavior. In general, it proved challenging to identify any dominant trends when comparing fission bubble data across samples from different fuel plates due to varying compositions and fabrication techniques. Here, the results exhibited fair agreement with the fission density vs. porosity correlation developed by the Russian reactor conversion program.
Book Synopsis Irradiation of U-Mo Base Alloys by : M. P. Johnson
Download or read book Irradiation of U-Mo Base Alloys written by M. P. Johnson and published by . This book was released on 1964 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of experiments was designed to assess the suitability of uranium-molybdenum alloys as high-temperature, high-burnup fuels for advanced sodium cooled reactors. Specimens with molybdenum contents between 3 and 10% were subjected to capsule irradiation tests in the Materials Testing Reactor, to burnups up to 10,000 Mwd/MTU at temperatures between 800 and 1500 deg F. The results indicated that molybdenum has a considerable effect in reducing the swelling due to irradiation. For example. 3% molybdemum reduces the swelling from 25%, for pure uranium. to 7% at approximates 3,000 Mwd/MTU at 1270 deg F. Further swelling resistance can be gained by increasing the molybdenum content, but the amount gained becomes successively smaller. At higher irradiation levels, the amount of swelling rapidly becomes greater, and larger amounts of molybdenum are required to provide similar resistance. A limit of 7% swelling, at 900 deg F and an irradiation of 7,230 Mwd/ MTU, requires the use of 10% Nonemolybdenum in the alloy. The burnup rates were in the range of 2.0 to 4.0 x 10p13s fissiom/cc-sec. Small ternary additions of silicon and aluminum were shown to have a noticeable effect in reducing swelling when added to a U-3% Mo alloy base. Under the conditions of the present experiment, 0.26% silicon or 0.38% aluminum were equivalent to 1 to 1 1/2% molybdenum. The Advanced Sodium Cooled Reactor requires a fuel capable of being irradiated to 20,000 Mwd/MTU at temperatures up to 1500 deg C in metal fuel, or equivalent in ceramic fuel. It is concluded that even the highest molybdenum contents considered did not produce a fuel capable of operating satisfactorily under these conditions. The alloys would be useful, however, for less exacting conditions. The U-3% Mo alloy is capable of use up to 3,000 Mwd/MTU at temperatures of 1300 deg F before swelling becomes excessive. The addition of silicon and aluminum would increase this limit to at least 3,000 Mwd/MTU, and possibly more if the
Book Synopsis Material Properties of Unirradiated Uranium-Molybdenum (U-Mo) Fuel for Research Reactors by : International Atomic Energy Agency
Download or read book Material Properties of Unirradiated Uranium-Molybdenum (U-Mo) Fuel for Research Reactors written by International Atomic Energy Agency and published by . This book was released on 2020-10-12 with total page 144 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication presents the material properties of all unirradiated Uranium-Molybdenum (U-Mo) fuel constituents that are essential for fuel designers and reactor operators to evaluate the fuel's performance and safety for research reactors. Many significant advances in the understanding and development of low enriched uranium U-Mo fuels have been made since 2004, stimulated by the need to understand irradiation behavior and early fuel failures during testing. The publication presents a comprehensive overview of mechanical and physical property data from U-Mo fuel research
Book Synopsis Microstructural Studies of Uranium-7wt%molybdenum/aluminum-2wt%silicon Dispersion Fuel by : Brandon D. Miller
Download or read book Microstructural Studies of Uranium-7wt%molybdenum/aluminum-2wt%silicon Dispersion Fuel written by Brandon D. Miller and published by . This book was released on 2010 with total page 317 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Scientific and Technical Aerospace Reports by :
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1995 with total page 692 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:
Book Synopsis Thermal-mechanical Analysis of Targets for High Volume Production of Molybdenum-99 Using Low-enriched Uranium by : Kyler K. Turner
Download or read book Thermal-mechanical Analysis of Targets for High Volume Production of Molybdenum-99 Using Low-enriched Uranium written by Kyler K. Turner and published by . This book was released on 2009 with total page 110 pages. Available in PDF, EPUB and Kindle. Book excerpt: Techenetium-99m is diagnostic radioactive medical isotope that is currently used 30,000 times a day in the United States. All supplies of techenetium-99m's parent isotope molybdenum-99 currently originate from nuclear reactor facilities located in foreign countries and use highly enriched uranium (HEU). The University of Missouri Research Reactor (MURR) is exploring the feasibility of high volume molybdenum-99 production at its facility. Current molybdenum-99 production uses HEU in a powder dispersion target. The powder dispersion method, conventionally used for fuel rods and plates, combines fine particles of aluminum and HEU that are bonded into a rigid plate during irradiation. In accordance with the Global Threat Reduction Initiative all uranium used in future molybdenum-99 production will use low enriched uranium (LEU). Unfortunately LEU has a much low fissionable density then HEU which makes the dispersion process economically unviable. A design approach to increase the LEU density is to use a target that is based on LEU foil. The foil design places a LEU foil between either two concentric annular aluminum cylinders or two aluminum plates which are pressed and welded together to produce a structure that allows for easy removal and processing. The drawback of these designs is the thermal contact resistance between the LEU and aluminum cladding during irradiative heating is very sensitive to the target design, manufacture, and irradiation holder. This thesis explores those thermal-mechanical design issues for both the cylindrical target design and the plate target design. Analytical, numerical and experimental studies are used to assess the mechanical deformation for these structures and its effect on the target's thermal contact resistance.
Book Synopsis Comprehensive Nuclear Materials by :
Download or read book Comprehensive Nuclear Materials written by and published by Elsevier. This book was released on 2020-07-22 with total page 4871 pages. Available in PDF, EPUB and Kindle. Book excerpt: Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials, Second Edition, Seven Volume Set provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field
Book Synopsis Automated Characterization of Uranium-molybdenum Fuel Microstructures by : Ryan A. Collette
Download or read book Automated Characterization of Uranium-molybdenum Fuel Microstructures written by Ryan A. Collette and published by . This book was released on 2015 with total page 133 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Thermal Conductivities of U3Si and U3Si2-Al Dispersion Fuels by :
Download or read book Thermal Conductivities of U3Si and U3Si2-Al Dispersion Fuels written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Two high density uranium silicides are being evaluated as replacements for the research reactor fuels currently in use. Employing these compounds permits a major reduction in uranium enrichment, and tests have shown that the silicide fuels perform well under irradiation. Thermal conductivity data are required for analysis of these results and for safety calculations. The data show that silicide-Al dispersion fuels have somewhat better thermal conductivities than U3O-Al dispersions, but their principal advantage is in their increased uranium content. The differences between the thermal conductivities of U3Si and U3Si2 dispersions are small, but the microstructure of the dispersion was found to have a major influence on thermal conductivity. This seems to be associated with the formation of planar porosity defects during the roll bonding process, and differences as large as a factor of four (59 vs. 14 W/m . K) were noted for the samples having equal U3Si2 contents (46 v/o).
Book Synopsis Publications, Reports, and Papers for 1968 from Oak Ridge National Laboratory by : F. M. O'Hara
Download or read book Publications, Reports, and Papers for 1968 from Oak Ridge National Laboratory written by F. M. O'Hara and published by . This book was released on 1969 with total page 340 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Risø Report written by and published by . This book was released on 1964 with total page 86 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Maternidad no deseada! written by and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis U.S. Government Research Reports by :
Download or read book U.S. Government Research Reports written by and published by . This book was released on 1962 with total page 614 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Introduction to Surface Engineering by : P. A. Dearnley
Download or read book Introduction to Surface Engineering written by P. A. Dearnley and published by Cambridge University Press. This book was released on 2017-01-16 with total page 798 pages. Available in PDF, EPUB and Kindle. Book excerpt: This highly illustrated reference work covers the three principal types of surface technologies that best protect engineering devices and products: diffusion technologies, deposition technologies, and other less commonly acknowledged surface engineering (SE) techniques. Various applications are noted throughout the text and additionally whole chapters are devoted to specific SE applications across the automotive, gas turbine engine (GTE), metal machining, and biomedical implant sectors. Along with the benefits of SE, this volume also critically examines SE's limitations. Materials degradation pathways - those which can and those which cannot be mitigated by SE - are rigorously explained. Written from a scientific, materials engineering perspective, this concise text is supported by high-quality images and photo-micrographs which show how surfaces can be engineered to overcome the limits of conventionally produced materials, even in complex or hostile operating environments. This book is a useful resource for undergraduate and postgraduate students as well as professional engineers.
Book Synopsis Microstructural Analysis of Irradiated U-Mo Fuel Plates by :
Download or read book Microstructural Analysis of Irradiated U-Mo Fuel Plates written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Microstructural characterization of irradiated dispersion and monolithic RERTR fuel plates using scanning electron microscopy (SEM) is being performed in the Electron Microscopy Laboratory at the Idaho National Laboratory. The SEM analysis of samples from U-Mo dispersion fuel plates focuses primarily on the behavior of the Si that has been added to the Al matrix to improve the irradiation performance of the fuel plate and on the overall behavior of fission gases (e.g., Xe and Kr) that develop as bubbles in the fuel microstructure. For monolithic fuel plates, microstructural features of interest, include those found in the U-Mo foil and at the U-Mo/Zr and Zr/6061 Al cladding interfaces. For both dispersion and monolithic fuel plates, samples have been produced using an SEM equipped with a Focused Ion Beam (FIB). These samples are of very high quality and can be used to uncover some very unique microstructural features that are typically not observed when characterizing samples produced using more conventional techniques. Overall, for the dispersion fuel plates with matrices that contained Si, narrower fuel/matrix interaction layers are typically observed compared to the fuel plates with pure Al matrix, and for the monolithic fuel plates microstructural features have been observed in the U-10Mo foil that are similar to what have been observed in the fuel particles found in U-Mo dispersion fuels. Most recently, more prototypic monolithic fuel samples have been characterized and this paper describes the microstructures that have been observed in these samples.
