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High Level Radioactive Waste Glass Production and Product Description

Published online by Cambridge University Press:  25 February 2011

James F. Sproull ,
Sharon L. Marra  and
Carol M. Jantzen
James F. Sproull
Affiliation:
Westinghouse Savannah River Co., P.O. Box 616, Aiken, SC 29803
Sharon L. Marra
Affiliation:
Westinghouse Savannah River Co., P.O. Box 616, Aiken, SC 29803
Carol M. Jantzen
Affiliation:
Westinghouse Savannah River Co., P.O. Box 616, Aiken, SC 29803
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Abstract

A summary of the current state of defense high-level radioactive waste in the U.S. is presented. Reasons for the selection of borosilicate glass as the matrix for the waste glass product over other glasses is enunciated. The product and processing requirements which the waste glass must meet are summarized. Finally the effects of crystallization and glass-in-glass phase separation on waste glass durability are discussed. Crystallization, under typical cooling conditions, has minimal effect on durability but glass-in-glass phase separation should be avoided.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 333: Symposium V – Scientific Basis for Nuclear Waste Management XVII , 1993 , 15
Copyright
Copyright © Materials Research Society 1994

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References

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