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Development and Testing of a Glass Waste Form for theImmobilization 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 NationalLaboratory (ANL) as part of our ongoing research in radioactive waste glassdevelopment. These glasses dissolved 5% and approximately 7% Pu. Earlycorrosion test results indicate that Pu-bearing ATS glass is extremelydurable. The initial goal in this project concerned equally both thesolubility of Pu and the durability of the ATS glasses; however, our primaryemphasis 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), arenow being investigated to increase the solubility of Pu withoutsubstantially sacrificing the durability of the current ATS formulations.The solution data from various corrosion tests on the original Pu-containingATS glasses are also presented.

Information

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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