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High-Level Radioactive Insoluble Waste Preparation for Vitrification

Published online by Cambridge University Press:  26 February 2011

B. A. Hamm
Affiliation:
Savannah River Laboratory, Aiken, South Carolina 29808
R. E. Eibling
Affiliation:
Savannah River Laboratory, Aiken, South Carolina 29808
M. A. Ebra
Affiliation:
Savannah River Laboratory, Aiken, South Carolina 29808
T. Motyka
Affiliation:
Savannah River Laboratory, Aiken, South Carolina 29808
H. D. Martin
Affiliation:
Savannah River Laboratory, Aiken, South Carolina 29808
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Abstract

At the Savannah River Plant (SRP), 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 processes 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.

Type
Research Article
Copyright
Copyright © Materials Research Society 1985

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References

1. Boersma, M. D., “Process Technology for Vitrification of Defense High-Level Waste at the Savannah River Plant,” Presented at Meeting of the American Nuclear Society Meeting, Fuel Reprocessing and Waste Management, Jackson Hole, Wyoming, August 26–29, 1984.Google Scholar
2. Maher, R., Shafranek, L. F., Stevens, W. R. III, “Solidification of Savannah River Plant High Level Waste,” Report No. CONF-8311117-1, American Institute of Chemical Engineers, Washington DC, November 4, 1983.Google Scholar
3. Defense Waste Processing Facility, DOE/SR-0011.Google Scholar