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Development and Testing of a Glass Waste Form for the Immobilization of Plutonium

Published online by Cambridge University Press:  03 September 2012

D. B. Chamberlain ,
J. M. Hanchar ,
J. W. Emery ,
J. C. Hoh ,
S. F. Wolf ,
R. J. Finch ,
J. K. Bates ,
A. J. G. Ellison  and
D. B. Dingwell
D. B. Chamberlain
Affiliation:
Argonne National Laboratory, 9700 S. Cass Ave., Argonne, IL 60439.
J. M. Hanchar
Affiliation:
Argonne National Laboratory, 9700 S. Cass Ave., Argonne, IL 60439.
J. W. Emery
Affiliation:
Argonne National Laboratory, 9700 S. Cass Ave., Argonne, IL 60439.
J. C. Hoh
Affiliation:
Argonne National Laboratory, 9700 S. Cass Ave., Argonne, IL 60439.
S. F. Wolf
Affiliation:
Argonne National Laboratory, 9700 S. Cass Ave., Argonne, IL 60439.
R. J. Finch
Affiliation:
Argonne National Laboratory, 9700 S. Cass Ave., Argonne, IL 60439.
J. K. Bates
Affiliation:
Argonne National Laboratory, 9700 S. Cass Ave., Argonne, IL 60439.
A. J. G. Ellison
Affiliation:
Corning Inc., Coming, NY, 14831, USA.
D. B. Dingwell
Affiliation:
Bayerisches Geoinstitut, Universität Bayreuth, 95440 Bayreuth, Germany.
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Abstract

Two alkali-tin-silicate (ATS) glasses have been prepared at Argonne National Laboratory (ANL) as part of our ongoing research in radioactive waste glass development. These glasses dissolved 5% and approximately 7% Pu. Early corrosion test results indicate that Pu-bearing ATS glass is extremely durable. The initial goal in this project concerned equally both the solubility of Pu and the durability of the ATS glasses; however, our primary emphasis has changed recently to maximizing the loading of Pu in the glass. ATS-based glasses, using Th(VI) and Ce(III) as surrogates for Pu(IV), are now being investigated to increase the solubility of Pu without substantially sacrificing the durability of the current ATS formulations. The solution data from various corrosion tests on the original Pu-containing ATS glasses are also presented.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 465: Symposium II – Scienfific Basis for Nuclear Waste Management XX , 1996 , 1229
Copyright
Copyright © Materials Research Society 1997

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References

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