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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

REFERENCES

1. President Clinton's March 1, 1995 Address to the Nixon for Peace Freedom Policy Conference.Google Scholar
2. Bates, J. K., Ellison, A. J. G., Emery, J. W., and Hoh, J. C., Mater. Res. Soc. Symp. Proc. 412, pp. 57–64 (1996).Google Scholar
3. Ellison, A. J. G., Mazer, J. J., and Ebert, W. L., Effect of Glass Composition on Waste Form Durability: A Critical Review, Argonne National Laboratory Report ANL-94/28 (1994).Google Scholar
4. Kingery, W. D., Bowen, H. K. and Uhlmann, D. R., Introduction to Ceramics, John Wiley & Sons, New York (1976).Google Scholar
5. Hanchar, J. M., Ph.D. Thesis, Rensselaer Polytechnic Institute (1996).Google Scholar
6. Farges, F., Brown, G. E. Jr., Navrotsky, A., Gan, H., and Rehr, J. J., “Coordination Chemistry of Ti (IV) in Silicate Glasses and Melts: II. Glasses at Ambient Temperature and Pressure,” Geochim. Cosmochim. Acta 60, 3039 (1996).Google Scholar
7. Volf, M. B., Chemical Approach to Glass. Glass Science and Technology, 7, Elsevier, New York (1984).Google Scholar
8. Veal, B. W., Mundy, J. N., and Lam, D. J., in Handbook on the Physics and Chemistry of the Actinides, edited by Freeman, A. J. and Lander, G.H., Elsevier, Amsterdam, pp. 271–309(1987).Google Scholar
9. Watson, E. B., Contrib. Mineral. Petrol. 70, 407 (1979).Google Scholar
10. Ellison, A. J. G. and Hess, P. C., Contrib. Mineral. Petrol. 94, 343 (1986).Google Scholar
11. Ebert, W. L., Argonne National Laboratory, personal communication (1996).Google Scholar
12. Test Method for Static Leaching of Monolithic Waste Forms for Disposal of Radioactive Waste, ASTM Standard C1220–92, ASTM, Philadelphia PA (1992).Google Scholar
13. Standard Test Methods for Determining Chemical Durability of Nuclear Waste Glasses: The Product Consistency Test (PCT), ASTM Standard C1285–94, ASTM, Philadelphia PA (1994).Google Scholar