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Mercury Reduction and Removal During High-Level Radioactive Waste Processing and Vitrification

Published online by Cambridge University Press:  15 February 2011

Russell E. Eibling  and
John R. fowler
Russell E. Eibling
Affiliation:
E. I. du Pont de Nemours & Co., Savannah River Laboratory, Aiken, South Carolina, USA 29808–0001
John R. fowler
Affiliation:
E. I. du Pont de Nemours & Co., Savannah River Laboratory, Aiken, South Carolina, USA 29808–0001
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Abstract

A reference process for immobilizing the high-level radioactive waste in borosilicate glass has been developed at the Savannah River Plant. This waste contains a substantial amount of mercury from separations processing. Because mercury will not remain in borosilicate glass at the processing temperature, mercury must be removed before vitrification or must be handled in the off-gas system. A process has been developed to remove mercury by reduction with formic acid prior to vitrification. Additional benefits of formic acid treatment include improved sludge handling and glass melter redox control.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 6: Symposium D – Scientific Basis for Nuclear Waste Management IV , 1981 , 617
Copyright
Copyright © Materials Research Society 1982

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References

REFERENCES

1. Woolsey, G. B., Baumgarten, P. K., Eibling, R. E. and Ferguson, R. B.. “A Small-Scale Integrated Demonstration of High-Level Radioactive Waste Processing and Vitrification Using Actual SRP Waste.” Google Scholar
Waste Management '81 ANS Topical Meeting, Volume 2, 811–823, Phoenix, Arizona (1981).Google Scholar