Vitrification of Savannah River Plant Radioactive Waste

Vitrification of Savannah River Plant Radioactive Waste

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Published: 1979

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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.


Vitrification Studies for Savannah River Plant Radioactive Wastes

Vitrification Studies for Savannah River Plant Radioactive Wastes

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Published: 1977

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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.


High Level Waste Vitrification at the SRP (Savannah River Plant) (DWPF (Defense Waste Processing Facility) Summary).

High Level Waste Vitrification at the SRP (Savannah River Plant) (DWPF (Defense Waste Processing Facility) Summary).

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Published: 1988

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The Savannah River Plant has been operating a nuclear fuel cycle since the early 1950's. Fuel and target elements are fabricated and irradiated to produce nuclear materials. After removal from the reactors, the fuel elements are processed to extract the products, and waste is stored. During the thirty years of operation including evaporation, about 30 million gallons of high level radioactive waste has accumulated. The Defense Waste Processing Facility (DWPF) under construction at Savannah River will process this waste into a borosilicate glass for long-term geologic disposal. The construction of the DWPF is about 70% complete; this paper will describe the status of the project, including design demonstrations, with an emphasis on the melter system. 9 figs.


High-Level Radioactive Insoluble Waste Preparation for Vitrification

High-Level Radioactive Insoluble Waste Preparation for Vitrification

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Published: 1984

Total Pages: 5

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At the Savannah River Plant a process has been developed for immobilizing high-level radioactive waste in a borosilicate glass. The waste is currently stored as soluble salts and insoluble solids. Insoluble waste as stored requires further processing before vitrification is possible. The processed required have been developed and demonstrated with actual waste. They include removal of aluminum in some waste, washing soluble salts out of the insoluble waste, and mercury stripping. Each of the processes and the results with actual SRP waste will be discussed. The benefits of each step will also be included.