Read Books Online and Download eBooks, EPub, PDF, Mobi, Kindle, Text Full Free.
Influence Of Oxygen Metal Ratio On Mixed Oxide Fuel Performance
Download Influence Of Oxygen Metal Ratio On Mixed Oxide Fuel Performance full books in PDF, epub, and Kindle. Read online Influence Of Oxygen Metal Ratio On Mixed Oxide Fuel Performance ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!
Book Synopsis Influence of Oxygen-metal Ratio on Mixed-oxide Fuel Performance by :
Download or read book Influence of Oxygen-metal Ratio on Mixed-oxide Fuel Performance written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The fuel oxygen-to-metal ratio (O/M) is recognized as an important consideration for performance of uranium--plutonium oxide fuels. An overview of the effects of differing O/M's on the irradiation performance of reference design mixed-oxide fuel in the areas of chemical and mechanical behavior, thermal performance, and fission gas behavior is presented. The pellet fuel has a nominal composition of 75 wt% UO2 + 25 wt% PuO2 at a pellet density of approx. 90% TD. for nominal conditions this results in a smeared density of approx. 85%. The cladding in all cases is 20% CW type 316 stainless steel with an outer diameter of 5.84 to 6.35 mm. O/M has been found to significantly influence fuel pin chemistry, mainly FCCI and fission product and fuel migration. It has little effect on thermal performance and overall mechanical behavior or fission gas release. The effects of O/M (ranging from 1.938 to 1.984) in the areas of fuel pin chemistry, to date, have not resulted in any reduction in fuel pin performance capability to goal burnups of approx. 8 atom% or more.
Book Synopsis Effects of Stoichiometry on Cladding Reaction in Mixed-oxide Fuel by :
Download or read book Effects of Stoichiometry on Cladding Reaction in Mixed-oxide Fuel written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Initial fuel stoichiometry (oxygen-to-metal ratio, O/M) has been established as one of the major parameters influencing the character and extent of fuel-cladding chemical interaction (FCCI) in UO2--25 wt% PuO2 fuels clad with 20% cold worked type 316 stainless steel. How the character of the interaction changes with initial O/M and the O/M dependence that has been established for the depth of interaction are discussed. the data base for this analysis consists of 134 data sets from P-23 series fuel pins irradiated in EBR-II. As-fabricated O/M's ranged from 1.938 to 1.984 with the bulk of the data in the range 1.96 to 1.98. Fuel pins operated to 9.5 atom %, with local cladding inner surface temperatures to 725°C, for exposure times to 415 equivalent full power days at heat rates of approx. 400 W/cm.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1987 with total page 1284 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 1975 with total page 1070 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Oxygen-to-metal Ratio Control During Fabrication of Mixed Oxide Fast Breeder Reactor Fuel Pellets by :
Download or read book Oxygen-to-metal Ratio Control During Fabrication of Mixed Oxide Fast Breeder Reactor Fuel Pellets written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Oxygen-to-metal ratio (O/M) of mixed oxide fuel pellets can be controlled during fabrication by proper selection of binder (type and content) and sintering conditions. Sintering condition adjustments involved the passing of Ar--8% H2 sintering gas across a cryostat ice bath controlled to temperatures ranging from -5 to -60°C to control as-sintered pellet O/M ratio. As-sintered fuel pellet O/M decreased with increasing Sterotex binder and PuO2 concentrations, increasing sintering temperature, and decreasing sintering gas dew point. Approximate relationships between Sterotex binder level and O/M were established for PuO2--UO2 and PuO2--ThO2 fuels. O/M was relatively insensitive to Carbowax binder concentration. Several methods of increasing O/M using post-sintering pellet heat treatments were demonstrated, with the most reliable being a two-step process of first raising the O/M to 2.00 (stoichiometric) at 650°C in Ar--8% H2 bubbled through H2O, followed by hydrogen reduction to specification O/M in oxygen-gettered Ar-(% H2 at temperatures ranging from 1200 to 1690°C.
Book Synopsis Mixed Oxide Fuel (Mox) Exploitation and Destruction in Power Reactors by : E.R. Merz
Download or read book Mixed Oxide Fuel (Mox) Exploitation and Destruction in Power Reactors written by E.R. Merz and published by Springer Science & Business Media. This book was released on 2013-06-29 with total page 308 pages. Available in PDF, EPUB and Kindle. Book excerpt: MOX fuel, a mixture of weapon-grade plutonium and natural or depleted uranium, may be used to deplete a portion of the world's surplus of weapon-grade plutonium. A number of reactors currently operate in Europe with one-third MOX cores, and others are scheduled to begin using MOX fuels in both Europe and Japan in the near future. While Russia has laboratory-scale MOX fabrication facilities, the technology remains under study. No fuels containing plutonium are used in the U.S. The 25 presentations in this book give an impressive overview of MOX technology. The following issues are covered: an up to date report on the disposition of ex-weapons Pu in Russia; an analysis of safety features of MOX fuel configurations of different reactor concepts and their operating and control measures; an exchange of information on the status of MOX utilisation in existing power plants, the fabrication technology of various MOX fuels and their behaviour in practice; a discussion of the typical national approaches by Russia and the western countries to the utilisation of Pu as MOX fuel; an introduction to new ideas, enhancing the disposition option of MOX fuel exploitation and destruction in existing and future advanced reactor systems; and the identification of common research areas where defined tasks can be initiated in cooperative partnership.
Book Synopsis Government Reports Annual Index by :
Download or read book Government Reports Annual Index written by and published by . This book was released on 1984 with total page 1084 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 1972 with total page 628 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book INIS Atomindeks written by and published by . This book was released on 1981 with total page 1510 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 1972 with total page 272 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Government Reports Announcements & Index by :
Download or read book Government Reports Announcements & Index written by and published by . This book was released on 1996 with total page 740 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Safety written by and published by . This book was released on 1969 with total page 1204 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 Hearings and Reports on Atomic Energy by : United States. Congress. Joint Committee on Atomic Energy
Download or read book Hearings and Reports on Atomic Energy written by United States. Congress. Joint Committee on Atomic Energy and published by . This book was released on 1946 with total page 834 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis AEC Authorizing Legislation, Fiscal Year 1967 by : United States. Congress. Joint Committee on Atomic Energy
Download or read book AEC Authorizing Legislation, Fiscal Year 1967 written by United States. Congress. Joint Committee on Atomic Energy and published by . This book was released on 1966 with total page 608 pages. Available in PDF, EPUB and Kindle. Book excerpt: Reviews costs and benefits of nuclear programs involving Defense Dept and nuclear industries.
Book Synopsis Hearings, Reports and Prints of the Joint Committee on Atomic Energy by : United States. Congress. Joint Committee on Atomic Energy
Download or read book Hearings, Reports and Prints of the Joint Committee on Atomic Energy written by United States. Congress. Joint Committee on Atomic Energy and published by . This book was released on 1966 with total page 1822 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis AEC Authorizing Legislation by : United States. Congress. Joint Committee on Atomic Energy
Download or read book AEC Authorizing Legislation written by United States. Congress. Joint Committee on Atomic Energy and published by . This book was released on 1966 with total page 612 pages. Available in PDF, EPUB and Kindle. Book excerpt:
