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Durabilities and Microstructures of Radioactive Glasses for Immobilization of Excess Actinides at the Savannah River Site

Published online by Cambridge University Press:  15 February 2011

N. E. Bibler ,
W. G. Ramsey ,
T. F. Meaker  and
J. M. Pareizs
N. E. Bibler
Affiliation:
Westinghouse Savannah River Co., Savannah River Technology Center Aiken, SC 29808
W. G. Ramsey
Affiliation:
Westinghouse Savannah River Co., Savannah River Technology Center Aiken, SC 29808
T. F. Meaker
Affiliation:
Westinghouse Savannah River Co., Savannah River Technology Center Aiken, SC 29808
J. M. Pareizs
Affiliation:
Westinghouse Savannah River Co., Savannah River Technology Center Aiken, SC 29808
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Abstract

This paper presents results of an investigation of the microstructures and durabilities of glasses for immobilization of excess Pu, Am, and Cm at the Savannah River Site (SRS). The glasses investigated had compositions based on commercial lanthanide glasses developed in the 1930's. All the glasses were prepared remotely in shielded cells and the analyses performed using instruments in radio hoods or benches. Durabilities were measured using the ASTM C-1285 standard leach test (PCT). Results for three glasses are presented. Two glasses contained 15 and 7 wt.% Pu, respectively. The third glass contained Am and Cm. The 15 wt% Pu glass was not completely amorphous and contained crystals of undissolved PuO2 and as well as dissolved PuO2. The 7 wt% Pu glass was completely amorphous. The Am/Cm glass contained <1 wt% actinides and was homogenous. The PCT tests for the Pu glasses indicated that B and Ba were leached congruently. Sm and Pu were leached at slower rates. In some cases release rates for specific Ba, Sm, and Pu isotopes were measured by analyzing the leachates by mass spectroscopy. For the Am-Cm glass release rates for B and Ba were equal indicating congruent dissolution. All three glasses were 25 to 50 times more durable than the borosilicate glasses developed at SRS for immobilization of the fission product HLW resulting from reprocessing operations at SRS.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 412: Symposium V – Scientific Basis for Nuclear Waste Management XIX , 1995 , 65
Copyright
Copyright © Materials Research Society 1996

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References

1. Volf, M. B., Chemical Approach to Glass, Glass Science and Technology Vol.7, Chapter 27, Elsevier Science Publishing Co., Inc., New York, NY, (1984), p. 391.Google Scholar
2. Ramsey, W. G., Bibler, N. E., and Meaker, T. F., “Compositions And Durabilities Of Glasses For Immobilization of Plutonium And Uranium”, Waste Management '95, Record 23828–23907, WM Symposia, Inc., Tucson, AZ, (1995).Google Scholar
3. Annual Book of ASTM Standards, Vol.12.01, pp 797–814 ASTM, Philadelphia, PA (1995)Google Scholar
4. Bibler, N. E., and Bates, J. K., “Product Consistency Leach Tests of Savannah River Site Radioactive Waste Glasses”, Material Research Society Symposium Proceedings, Vol.176, pp. 327–338, Materials Research Society, Pittsburgh, PA (1990).Google Scholar
5. Bates, J. K., Liam, D. J, Steindler, M. J., “Extended Leach Studies of Actinide-Doped SRL 131 Glasses”, Material Research Society Symposium Proceedings, Vol.15, pp. 183–190, Materials Research Society, Pittsburgh, PA (1983).Google Scholar