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Development Of A Treatment Technology For Diluting Highly Enriched Al Based Doe Spent Nuclear Fuel
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Book Synopsis Development of a Treatment Technology for Diluting Highly Enriched Al-Based DOE Spent Nuclear Fuel by :
Download or read book Development of a Treatment Technology for Diluting Highly Enriched Al-Based DOE Spent Nuclear Fuel written by and published by . This book was released on 2001 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Savannah River Site is the U.S. Department of Energy's preferred site for return and treatment of all aluminum-base, spent, research and test reactor fuel assemblies. A pilot-scale L-Area Experimental Facility (LEF) is planned to validate induction furnace operations, remote handling, and the off gas system for trapping volatile elements under plant operating conditions.
Book Synopsis The Melt-Dilute Treatment of Al-Base Highly Enriched DOE Spent Nuclear Fuels by :
Download or read book The Melt-Dilute Treatment of Al-Base Highly Enriched DOE Spent Nuclear Fuels written by and published by . This book was released on 1998 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The melt-dilute treatment technology program is focused on the development and implementation of a treatment technology for diluting highly enriched (>20 percent 235U) aluminum spent nuclear fuel to low enriched levels (
Book Synopsis Research Reactor Aluminum Spent Fuel by : National Research Council
Download or read book Research Reactor Aluminum Spent Fuel written by National Research Council and published by National Academies Press. This book was released on 1998-05-06 with total page 239 pages. Available in PDF, EPUB and Kindle. Book excerpt: The U.S. Department of Energy (DOE) is preparing an environmental impact statement (EIS) for management of aluminum spent fuel from foreign and domestic research reactors, much of which is highly enriched in uranium-235. This EIS will assess the need for additional treatment and storage facilities at the Savannah River Site to accommodate the receipt of this fuel, and it also will assess and select a treatment technology to prepare this fuel for interim storage and eventual shipment to a repository for disposal. This National Research Council book, which was prepared at the request of DOE's Savannah River Office, provides a technical assessment of the technologies, costs, and schedules developed by DOE for eight alternative treatment options and the baseline reprocessing option. It also provides comments on DOE's aluminum spent fuel disposal program, a program that is slated to last for about 40 years and cost in excess of $2 billion.
Book Synopsis Fission Product Volatilization and Off-Gas System Development in the Melt-Dilute Treatment Technology Program for Al-Based DOE Spent Nuclear Fuel by :
Download or read book Fission Product Volatilization and Off-Gas System Development in the Melt-Dilute Treatment Technology Program for Al-Based DOE Spent Nuclear Fuel written by and published by . This book was released on 1999 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: The melt-dilute treatment technology program is focused on the development and implementation of a treatment technology for diluting highly enriched (approximately 20 percent 235U) aluminum spent nuclear fuel to low enriched levels (less than 20 percent) 235U and qualifying the LEU Al-SNF form for geologic repository storage. Typically, many domestic and foreign research reactor fuel assemblies were manufactured using highly enriched uranium-aluminum alloys. These assemblies have been irradiated and the burn-up levels range from 30-70 percent. In order to reduce the enrichment of these assemblies prior to ultimate geologic repository disposal, the melt-dilute technology proposes to melt these SNF assemblies and then dilute with additions of depleted uranium. Dilution levels of less than 20 percent are desired. Benefits accrued from this process when compared to the direct disposal option include the potential for significant volume reduction, reduced criticality potential, and the potential for enhanced SNF form characteristics.
Book Synopsis Proceedings of the Embedded Topical Meeting on DOE Spent Nuclear Fuel and Fissile Material Management, San Diego, California, June 4-8, 2000 by :
Download or read book Proceedings of the Embedded Topical Meeting on DOE Spent Nuclear Fuel and Fissile Material Management, San Diego, California, June 4-8, 2000 written by and published by . This book was released on 2000 with total page 556 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis The Case of the Lieutenants of His Majesty's Navy. Humbly to the Consideration of Both Houses of Parliament by :
Download or read book The Case of the Lieutenants of His Majesty's Navy. Humbly to the Consideration of Both Houses of Parliament written by and published by . This book was released on 1750* with total page 2 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Spent Nuclear Fuel Management written by and published by . This book was released on 2000 with total page 592 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Melt-Dilute Treatment Technology for Aluminum Based Research Reactor Spent Fuel by :
Download or read book Melt-Dilute Treatment Technology for Aluminum Based Research Reactor Spent Fuel written by and published by . This book was released on 1999 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: The United States Department of Energy has selected the Savannah River Site (SRS) as the location to consolidate and store Aluminum Spent Nuclear Fuel (SNF), originating in the United States, from Foreign Research Reactor (FRR) and Domestic Research Reactor (DRR) through the Environmental Impact Statement (EIS) process. These SNF are either in service, being stored in water basins or in dry storage casks at the reactor sites, or have been transferred to SRS and stored in water basins. A portion of this inventory contains HEU. Since the fuel receipts would continue for several decades beyond projected SRS canyon operations, it is anticipated that it will be necessary to develop disposal technologies that do not rely on reprocessing. The Research Reactor Spent Nuclear Fuel Task Team, appointed by the Office of Spent Fuel Management of DOE, assessed and identified the most promising technology options for the alternative disposition of aluminum based domestic and foreign research reactor SNF in a geologic repository. The most promising options identified by the task team were direct/ co-disposal and melt-dilute technologies. The DOE through the SRS has evaluated the two options and has identified Melt-Dilute Treatment Technology as the preferred alternative in the Draft Environmental Impact Statement for the ultimate disposal of Al-SNF in the Mined Geologic Disposal System.
Book Synopsis Onkel Toms stuga by : Harriet Beecher Stowe
Download or read book Onkel Toms stuga written by Harriet Beecher Stowe and published by . This book was released on 1911 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :North Atlantic Treaty Organization. Public Diplomacy Division Publisher :Springer Science & Business Media ISBN 13 :1402059019 Total Pages :357 pages Book Rating :4.4/5 (2 download)
Book Synopsis Safety Related Issues of Spent Nuclear Fuel Storage by : North Atlantic Treaty Organization. Public Diplomacy Division
Download or read book Safety Related Issues of Spent Nuclear Fuel Storage written by North Atlantic Treaty Organization. Public Diplomacy Division and published by Springer Science & Business Media. This book was released on 2007-05-09 with total page 357 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book contains papers from a NATO-sponsored workshop in Almaty in September 2005, which discussed safety-related issues of storing spent nuclear fuel. Fifteen papers cover aluminum-clad fuel discharged from research reactors worldwide, while five papers examine stainless steel-clad fuel from fast reactors, and two Zircaloy-clad fuel from commercial light-water reactors.
Book Synopsis Assessment of Technologies Supported by the Office of Science and Technology, Department of Energy by :
Download or read book Assessment of Technologies Supported by the Office of Science and Technology, Department of Energy written by and published by Institute of Electrical & Electronics Engineers(IEEE). This book was released on 2001 with total page 1056 pages. Available in PDF, EPUB and Kindle. Book excerpt: This is the fifth volume containing the results of the peer reviews performed jointly by ASME and the Institute for Regulatory Science (RSI) for the Office of Science and Technology of the U.S. Department of Energy. It covers the fiscal year 2001 starting October 1, 2000 to September 30, 2001.
Author :United States. Congress. House. Committee on Science. Subcommittee on Energy and Environment Publisher : ISBN 13 : Total Pages :1852 pages Book Rating :4.0/5 ( download)
Book Synopsis Fiscal Year 2000 Department of Energy Budget Authorization Request, Parts I and II by : United States. Congress. House. Committee on Science. Subcommittee on Energy and Environment
Download or read book Fiscal Year 2000 Department of Energy Budget Authorization Request, Parts I and II written by United States. Congress. House. Committee on Science. Subcommittee on Energy and Environment and published by . This book was released on 2000 with total page 1852 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Scientific Basis for Nuclear Waste Management XXIII: Volume 608 by : Robert W. Smith
Download or read book Scientific Basis for Nuclear Waste Management XXIII: Volume 608 written by Robert W. Smith and published by . This book was released on 2000-10-09 with total page 800 pages. Available in PDF, EPUB and Kindle. Book excerpt: This long-standing symposia series has become the premier, international forum for scientific and engineering issues related to all levels and types of radioactive wastes and their management. Topics include: fuel cladding and spent nuclear fuel; container fabrication and corrosion; performance assessment; repository performance; radionuclide sorption and transport; cement-based materials and waste containment; corrosion of ceramic wasteforms; structure and characterization of ceramics; radiation effects; natural analogs; wasteform characterization and processing; and corrosion and characterization of glass wasteforms.
Author :United States. Congress. House. Committee on Science. Subcommittee on Energy and Environment Publisher : ISBN 13 : Total Pages :2172 pages Book Rating :4.0/5 ( download)
Book Synopsis Fiscal Year 2001 Budget Authorization Request by : United States. Congress. House. Committee on Science. Subcommittee on Energy and Environment
Download or read book Fiscal Year 2001 Budget Authorization Request written by United States. Congress. House. Committee on Science. Subcommittee on Energy and Environment and published by . This book was released on 2001 with total page 2172 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Proceedings of the Third Topical Meeting on DOE Spent Nuclear Fuel and Fissile Materials Management by : American Nuclear Society
Download or read book Proceedings of the Third Topical Meeting on DOE Spent Nuclear Fuel and Fissile Materials Management written by American Nuclear Society and published by . This book was released on 1998 with total page 454 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Nuclear Wastes by : National Research Council
Download or read book Nuclear Wastes written by National Research Council and published by National Academies Press. This book was released on 1996-02-23 with total page 590 pages. Available in PDF, EPUB and Kindle. Book excerpt: Disposal of radioactive waste from nuclear weapons production and power generation has caused public outcry and political consternation. Nuclear Wastes presents a critical review of some waste management and disposal alternatives to the current national policy of direct disposal of light water reactor spent fuel. The book offers clearcut conclusions for what the nation should do today and what solutions should be explored for tomorrow. The committee examines the currently used "once-through" fuel cycle versus different alternatives of separations and transmutation technology systems, by which hazardous radionuclides are converted to nuclides that are either stable or radioactive with short half-lives. The volume provides detailed findings and conclusions about the status and feasibility of plutonium extraction and more advanced separations technologies, as well as three principal transmutation concepts for commercial reactor spent fuel. The book discusses nuclear proliferation; the U.S. nuclear regulatory structure; issues of health, safety and transportation; the proposed sale of electrical energy as a means of paying for the transmutation system; and other key issues.
Book Synopsis Medical Isotope Production Without Highly Enriched Uranium by : National Research Council
Download or read book Medical Isotope Production Without Highly Enriched Uranium written by National Research Council and published by National Academies Press. This book was released on 2009-06-27 with total page 220 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book is the product of a congressionally mandated study to examine the feasibility of eliminating the use of highly enriched uranium (HEU2) in reactor fuel, reactor targets, and medical isotope production facilities. The book focuses primarily on the use of HEU for the production of the medical isotope molybdenum-99 (Mo-99), whose decay product, technetium-99m3 (Tc-99m), is used in the majority of medical diagnostic imaging procedures in the United States, and secondarily on the use of HEU for research and test reactor fuel. The supply of Mo-99 in the U.S. is likely to be unreliable until newer production sources come online. The reliability of the current supply system is an important medical isotope concern; this book concludes that achieving a cost difference of less than 10 percent in facilities that will need to convert from HEU- to LEU-based Mo-99 production is much less important than is reliability of supply.