Download or read book Some Properties of Uranium molybdenum Alloy Fuels for Organic Moderated Reactors written by W. H. Friske and published by . This book was released on 1960 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Dispersion Fuels for Advanced Organic Moderated Reactor written by J. Kroehler and published by . This book was released on 1960 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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
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
Download or read book Reactor Core Materials written by and published by . This book was released on 1958 with total page 938 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Compilation of Uranium 10 W o Molybdenum Fuels Alloy Properties Technical Memorandum written by and published by . This book was released on 1957 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The mechanical and physical properties of U --10 wt.% Mo before and after irradiation have been studied. The pre-irradiation properties and some of the post-irradiation physical properties are presented in graphical and tabular form. (J.S.R.).
Download or read book Comprehensive Nuclear Materials written by Todd R Allen and published by Elsevier. This book was released on 2011-05-12 with total page 3552 pages. Available in PDF, EPUB and Kindle. Book excerpt: Comprehensive Nuclear Materials, Five Volume Set discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerators, and for diverse functions in fuels, cladding, moderator and control materials, structural, functional, and waste materials. The work addresses the full panorama of contemporary international research in nuclear materials, from Actinides to Zirconium alloys, from the worlds' leading scientists and engineers. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environment Fully integrated with F-elements.net, a proprietary database containing useful cross-referenced property data on the lanthanides and actinides Details contemporary developments in numerical simulation, modelling, experimentation, and computational analysis, for effective implementation in labs and plants
Download or read book The Production and Properties of Reactor Fuels written by W. Ermischer and published by . This book was released on 1968 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt: A review of existing and prespective fuels for nuclear reactors is given. Manufacturing processes for each type of fuel are described and their physical and chemical characteristics are given with respect to reactor application. Presented data show that uranium and plutonium compounds and alloys come into consideration as nuclear fuels. At present uranium dioxide and metallic uranium and its alloys are most commonly used. For advanced reactors, fuels with higher heat conductivity, mass density and thermal stability are being investigated; high stability towards reactor internal radiation is also required. The results of research confirm that uranium and plutonium carbides and nitrides meet these requirements. Their raw materials for reactor fuels involves a new manufacturing technology and processes coupled with requirements for increased protective measures against radiation and chemical hazards.
Download or read book Reactor Materials written by and published by . This book was released on 1961 with total page 1094 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 1080 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Technology written by Leonard E. Link and published by . This book was released on 1964 with total page 636 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Proceedings of the Organic Cooled Reactor Forum October 6 7 1960 written by and published by . This book was released on 1960 with total page 310 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Power Reactor Technology written by and published by . This book was released on 1959 with total page 770 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Study of Remote Military Power Applications written by and published by . This book was released on 1960 with total page 72 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book List written by and published by . This book was released on 1948 with total page 564 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1967 with total page 1388 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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:
