Off-Gas System Development for the Melt-Dilute Treatment of Aluminum-Based Spent Nuclear Fuel

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ISBN 13 :
Total Pages : 5 pages
Book Rating : 4.:/5 (684 download)

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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.

Fission Product Volatilization and Off-Gas System Development in the Melt-Dilute Treatment Technology Program for Al-Based DOE Spent Nuclear Fuel

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ISBN 13 :
Total Pages : 5 pages
Book Rating : 4.:/5 (683 download)

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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.

Onkel Toms stuga

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (186 download)

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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:

Melt-Dilute Treatment of Spent Nuclear Fuel Assemblies from Research and Test Reactors

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ISBN 13 :
Total Pages : 5 pages
Book Rating : 4.:/5 (683 download)

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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.

Melt-Dilute Treatment Technology for Aluminum Based Research Reactor Spent Fuel

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ISBN 13 :
Total Pages : 5 pages
Book Rating : 4.:/5 (683 download)

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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.

Philadelphia and vicinity

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ISBN 13 :
Total Pages : 72 pages
Book Rating : 4.:/5 (462 download)

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Book Synopsis Philadelphia and vicinity by :

Download or read book Philadelphia and vicinity written by and published by . This book was released on 1911 with total page 72 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Spent Nuclear Fuel Management

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ISBN 13 :
Total Pages : 592 pages
Book Rating : 4.3/5 (555 download)

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Book Synopsis Spent Nuclear Fuel Management by :

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:

Proceedings of the Embedded Topical Meeting on DOE Spent Nuclear Fuel and Fissile Material Management, San Diego, California, June 4-8, 2000

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ISBN 13 :
Total Pages : 556 pages
Book Rating : 4.3/5 (91 download)

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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:

Development of a Treatment Technology for Diluting Highly Enriched Al-Based DOE Spent Nuclear Fuel

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ISBN 13 :
Total Pages : 5 pages
Book Rating : 4.:/5 (684 download)

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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.

The Case of the Lieutenants of His Majesty's Navy. Humbly to the Consideration of Both Houses of Parliament

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ISBN 13 :
Total Pages : 2 pages
Book Rating : 4.:/5 (316 download)

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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:

Treatment and Management of Sodium-bonded Spent Nuclear Fuel

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ISBN 13 :
Total Pages : 284 pages
Book Rating : 4.3/5 (555 download)

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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:

The Melt-dilute Disposition Option for U-233

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ISBN 13 :
Total Pages : 5 pages
Book Rating : 4.:/5 (684 download)

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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.

Proceedings of the Third Topical Meeting on DOE Spent Nuclear Fuel and Fissile Materials Management

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ISBN 13 : 9780894486388
Total Pages : 454 pages
Book Rating : 4.4/5 (863 download)

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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:

The Melt-Dilute Treatment Disposition Option for 233U.

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ISBN 13 :
Total Pages : 5 pages
Book Rating : 4.:/5 (683 download)

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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.

Research Reactor Aluminum Spent Fuel

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Publisher : National Academies Press
ISBN 13 : 0309174104
Total Pages : 239 pages
Book Rating : 4.3/5 (91 download)

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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.

Energy and Water Development Appropriations for 1999

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ISBN 13 :
Total Pages : 3250 pages
Book Rating : 4.F/5 ( download)

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Book Synopsis Energy and Water Development Appropriations for 1999 by : United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development

Download or read book Energy and Water Development Appropriations for 1999 written by United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development and published by . This book was released on 1998 with total page 3250 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Energy and Water Development Appropriations for 1999: Department of Energy fiscal year 1999 budget justifications

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ISBN 13 :
Total Pages : 3256 pages
Book Rating : 4.3/5 (121 download)

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Book Synopsis Energy and Water Development Appropriations for 1999: Department of Energy fiscal year 1999 budget justifications by : United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development

Download or read book Energy and Water Development Appropriations for 1999: Department of Energy fiscal year 1999 budget justifications written by United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development and published by . This book was released on 1998 with total page 3256 pages. Available in PDF, EPUB and Kindle. Book excerpt: