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Modeling Chemical Interactions in the Hydrated Layers of Nuclear Waste Glasses.

Published online by Cambridge University Press:  25 February 2011

Terrence M. Sullivan  and
Albert J. Machiels
Terrence M. Sullivan
Affiliation:
University of Illinois, Nuclear Engineering Program, Urbana, IL 61801;
Albert J. Machiels
Affiliation:
Electric Power Research Institute, P. O. Box 10412, Palo Alto, CA 94303.
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Abstract

The distribution of glass constituents within the hydrated layer is investigated through a mathematical representation of the fundamental processes that influence mass transport. A brief description of the models that are developed is presented. The resulting equations are implemented in a computer code named GELOH. The importance of the processes of network hydration and layer growth, alteration product formation, and dissolution is studied through the use of GELOH. The results of these studies are presented and interpreted in the light of the experimental evidence available on the aqueous corrosion of nuclear waste glass.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 26: Symposium D – Scientific Basis for Nuclear Waste Management VII , 1983 , 597
Copyright
Copyright © Materials Research Society 1984

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References

REFERENCES

[1] Sullivan, T.M., and Machiels, A.J., 1983 Growth of Hydrated Gel Layers in Nuclear Waste Glasses. Advances in Ceramics, American Ceramic Society, In press.Google Scholar
[2] Cussler, E.L., 1982 Dissolution and Reprecipitation in Porous Solids. A.I.Ch.E.J., 28, 500.Google Scholar
[3] Bunker, , , B.C., Arnold, G.W., and Day, D.E., 1982 Alkali Leaching from Mixed Alkali Silicate Glasses. 84th Annual Meeting, American Ceramic Society, Cincinnati, Ohio, May 2–5,1982.Google Scholar
[4] See for example: McVay, G.L., Bradley, D.J., Kircher, J.F., 1981 Elemental Release from Glass and Spent Fuel. ONWI-275, Office of Nuclear Waste Isolation, Battelle Memorial Institute, Columbus, Ohio.10.2172/12184888Google Scholar
[5] Sullivan, T.M., 1984. Modeling Diffusional Processes in the Hydrated Layer of Vitrified Nuclear Waste Forms. Ph. D. Thesis, University of Illinois, Urbana, IL.Google Scholar
[6] Eisenmann, G., 1967 The Origin of the Glass Electrode Potential, Glass Electrodes for Hydrogen and Other Cations, Edited by Eisenmann, G. and Dekker, M., p. 133, New York, NY.Google Scholar
[7] McVay, G.L., 1981 Leaching Mechanisms, Waste“Rock Interactions Technology Program: Executive Summary Report of Technical Progress for January throuh March 1981, Richland, WA.Google Scholar
[8] Machiels, A.J., and Pescatore, C., 1982. Modeling of Waste Form Leaching – Part II: Mechanistic Modeling of Nuclear Waste Form Leaching by Aqueous Solutions, UILU-ENG-82-5360, University of Illinois, Urbana, IL.Google Scholar