Vitrification Studies for Savannah River Plant Radioactive Wastes

Vitrification Studies for Savannah River Plant Radioactive Wastes

Author:

Publisher:

Published: 1977

Total Pages:

ISBN-13:

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Borosilicate glass is being studied as a possible matrix for solidification of Savannah River Plant radioactive waste. Glass compositions, radiation and thermal stabilities, radionuclide volatility, sulfate solubility, and glass dissolution were studied. Up to 40 wt. percent simulated or radioactive wastes have been vitrified at 1150°C.


Vitrification of Savannah River Plant Radioactive Waste

Vitrification of Savannah River Plant Radioactive Waste

Author:

Publisher:

Published: 1979

Total Pages:

ISBN-13:

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The reference process for disposal of radioactive waste from the Savannah River Plant is vitrification into borosilicate glass. The effects of frit composition and frit particle size, batch chemicals, soluble salts, charcoal, argon atmosphere, and viscosity on the melting process are discussed.


Improving the Characterization and Treatment of Radioactive Wastes for the Department of Energy's Accelerated Site Cleanup Program

Improving the Characterization and Treatment of Radioactive Wastes for the Department of Energy's Accelerated Site Cleanup Program

Author: National Research Council

Publisher: National Academies Press

Published: 2005-01-06

Total Pages: 84

ISBN-13: 0309181941

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The Department of Energy's Office of Environmental Management (EM) directs the massive cleanup of more than 100 sites that were involved in the production of nuclear weapons materials during the Manhattan Project and the Cold War. This report offers suggestions for more effectively characterizing and treating the orphan and special-case wastes that are part of EM's accelerated cleanup program. It identifies technical opportunities for EM to improve the program that will save time and money without compromising health and safety. The opportunities identified include: making more effective use of existing facilities and capabilities for waste characterization, treatment, or disposal; eliminating self-imposed requirements that have no clear technical or safety basis; and investing in new technologies to improve existing treatment and characterization capabilities. For example, the report suggests that EM work with DOE classification officers to declassify, to the extent possible, classified materials declared as wastes. The report also suggests a new approach for treating the wastes that EM will leave in place after cleanup.


Vitrification of High-level Radioactive Waste in a Small-scale Joule-heated Ceramic Melter

Vitrification of High-level Radioactive Waste in a Small-scale Joule-heated Ceramic Melter

Author:

Publisher:

Published: 1981

Total Pages:

ISBN-13:

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Vitrification is the reference process for the immobilization of radioactive waste from the production of defense materials at the Savannah River Plant (SRP). Since 1979, a small vitrification facility (1 lb/h) has been operated at the Savannah River Laboratory using actual SRP waste. In previous studies, dried waste was fed to this smaller melter. This report discusses direct feeding of actual liquid-waste slurries to the small melter. These liquid-feeding tests demonstrated that addition of premelted glass frit to the waste slurry reduces the amount of material volatilized. Results of these tests are in accord with results of large-scale tests with actual waste.