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The Melt Dilute Treatment Of Al Base Highly Enriched Doe Spent Nuclear Fuels
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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 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:
Book Synopsis Melt-Dilute Treatment of Spent Nuclear Fuel Assemblies from Research and Test Reactors by :
Download or read book Melt-Dilute Treatment of Spent Nuclear Fuel Assemblies from Research and Test Reactors 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 Savannah River Site is the US Department of Energy''s preferred site for return and treatment of all aluminum-base, spent, research and test reactor fuel assemblies. There are over 20,000 spent fuel assemblies now stored in different countries around the world, and by 2035 many will be returned to SRS for treatment and interim storage, in preparation for disposal in a geologic repository. The early fuel assemblies for research and test reactors were made using aluminum clad plates that were fabricated from highly enriched (93 percent) uranium-aluminum alloy. Later, powder metallurgical fabrication methods were developed to produce plate fuels with higher uranium contents using either uranium aluminide, uranium oxide or uranium silicide powders mixed with aluminum. Silicide fuel elements generally are fabricated with low enriched uranium containing less than 20 percent 235U. Following irradiation, the spent fuel assemblies are discharged from the reactor, and most assemblies have been stored in under-water pools, some since the early 1950''s. A number of disposition options including direct/co-disposal and melt-dilute treatment were evaluated recently. The melt-dilute technique was identified as the preferred method for treatment of aluminum-base spent fuel. The technique consists of melting the spent fuel assembly and adding depleted uranium to the melt for isotopic dilution to less than 20 percent 235U. Aluminum is added, if necessary, to produce a predetermined alloy composition. Additionally, neutron poisons may be added to the melt where they form solid solution phases or compounds with uranium and/or aluminum. Lowering the enrichment reduces both criticality and proliferation concerns for storage. Consolidation by melting also reduces the number of storage canisters. Laboratory and small-scale process demonstration using irradiated fuel is underway. Tests of the off gas absorption system have been initiated using both surrogate and irradiated RERTR mini fuel plates. An experimental L-Area facility (LEF) is planned to validate induction furnace operations, remote handling, and the off gas system for trapping volatile elements under plant operating conditions. Results from laboratory tests and the small-scale process studies are discussed.
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 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:
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 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:
Book Synopsis Off-Gas System Development for the Melt-Dilute Treatment of Aluminum-Based Spent Nuclear Fuel by :
Download or read book Off-Gas System Development for the Melt-Dilute Treatment of Aluminum-Based Spent Nuclear Fuel written by and published by . This book was released on 2002 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: This effort will provide a technical basis to assure safe and efficient system operation of the melt-dilute process and have general applicability to off-gas streams.
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 Scientific Basis for Nuclear Waste Management by :
Download or read book Scientific Basis for Nuclear Waste Management written by and published by . This book was released on 1998 with total page 1368 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.
Book Synopsis Treatment and Management of Sodium-bonded Spent Nuclear Fuel by :
Download or read book Treatment and Management of Sodium-bonded Spent Nuclear Fuel written by and published by . This book was released on 2000 with total page 284 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Scientific Basis for Nuclear Waste Management XXII: Volume 556 by : David J. Wronkiewicz
Download or read book Scientific Basis for Nuclear Waste Management XXII: Volume 556 written by David J. Wronkiewicz and published by . This book was released on 1999-11-24 with total page 1370 pages. Available in PDF, EPUB and Kindle. Book excerpt: Safe and effective management of nuclear waste provides a broad range of challenges for materials science. Waste processing, waste form and engineered barrier properties, interactions between engineered and geological systems, radiation effects, chemistry and transport of waste species, and long-term predictions of repository performance are just some of the scientific problems facing modern society. This book, the 22nd in a very successful series from MRS, offers an international and inter-disciplinary perspective on the issues, and features developments in both fundamental and applied areas. Topics include: development and characterization of ceramic waste forms; ceramic waste form corrosion; glass waste form processing; glass formulation, properties and structure; glass waste form corrosion; spent nuclear fuel; performance assessment; repository backfill; flow and transport; natural analogues; container corrosion; metal waste form corrosion; radionuclide speciation and solubility; radionuclide sorption; microbial effects; radiation effects; cement waste forms and waste treatment.
Book Synopsis The Melt-Dilute Treatment Disposition Option for 233U. by :
Download or read book The Melt-Dilute Treatment Disposition Option for 233U. 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 U.S. Department of Energy has initiated a program for disposition of surplus weapons-usable fissile materials by making them inaccessible and unattractive for use in nuclear weapons. The program supports both the U.S. arms-control and nonproliferation policies of the government. Uranium-233 is a weapons-usable material like weapons-grade plutonium and high-enriched uranium. Oak Ridge has 233U stored in oxide form in stainless steel canisters, and they need to place the material in long-term safe storage that meets U.S. policies in a cost-effective manner. A proposed option for treatment of this material is the Melt-Dilute (MD) technology, now under developed at Savannah River Site for aluminum-base spent nuclear fuel. Using the MD process, unirradiated fissile material is first melted in an induction furnace and depleted uranium is added to dilute the 233U or 235U content to acceptable levels. Aluminum is added to control the alloy composition. After solidification the ingot is removed from the furnace and put into a storage canister for eventual shipment to a geologic repository.
Book Synopsis The Melt-dilute Disposition Option for U-233 by :
Download or read book The Melt-dilute Disposition Option for U-233 written by and published by . This book was released on 2000 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Melt-Dilute treatment technology is being developed by the Savannah River Technology Center (SRTC) for treatment of aluminum-base spent nuclear fuel. The MD technology has applicability for treatment of 233U oxide stored in either aluminum or stainless steel cans at Oak Ridge. This technology not only reduces the risk for criticality but also reduces proliferation concerns by diluting the fissile material to less the 12 percent 233U and less than 20 percent 235U. The resulting alloy is then dry stored temporarily in road-ready canisters until ultimate disposal in a geologic repository.
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 Improving the Scientific Basis for Managing DOE's Excess Nuclear Materials and Spent Nuclear Fuel by : National Research Council
Download or read book Improving the Scientific Basis for Managing DOE's Excess Nuclear Materials and Spent Nuclear Fuel written by National Research Council and published by National Academies Press. This book was released on 2003-06-09 with total page 124 pages. Available in PDF, EPUB and Kindle. Book excerpt: The production of nuclear materials for the national defense was an intense, nationwide effort that began with the Manhattan Project and continued throughout the Cold War. Now many of these product materials, by-products, and precursors, such as irradiated nuclear fuels and targets, have been declared as excess by the Department of Energy (DOE). Most of this excess inventory has been, or will be, turned over to DOE's Office of Environmental Management (EM), which is responsible for cleaning up the former production sites. Recognizing the scientific and technical challenges facing EM, Congress in 1995 established the EM Science Program (EMSP) to develop and fund directed, long-term research that could substantially enhance the knowledge base available for new cleanup technologies and decision making. The EMSP has previously asked the National Academies' National Research Council for advice for developing research agendas in subsurface contamination, facility deactivation and decommissioning, high-level waste, and mixed and transuranic waste. For this study the committee was tasked to provide recommendations for a research agenda to improve the scientific basis for DOE's management of its high-cost, high-volume, or high-risk excess nuclear materials and spent nuclear fuels. To address its task, the committee focused its attention on DOE's excess plutonium-239, spent nuclear fuels, cesium-137 and strontium-90 capsules, depleted uranium, and higher actinide isotopes.
