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Aqueous Corrosion of the French LWR Solution Reference Glass First Generation Model

Published online by Cambridge University Press:  28 February 2011

E. Mouche  and
Vernaz E.
E. Mouche
Affiliation:
Commissariat à l'Energie Atomique, DRDD/SESD, BP N°6, 92265 Fontenay aux Roses, France
Vernaz E.
Affiliation:
Commissariat à l'Energie Atomique, DRDD/SDHA, BP N°171, 30205 Bagnols sur Ceze cedex, France
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Abstract

Experiments have been performed on the aqueous dissolution of French LWR solution reference glass that have identified key dissolution mechanisms to be considered in modeling. The physical hypotheses on which the model relies are a dissolution rate governed by the silica concentration in solution according to a first order kinetic law, congruent release of the mobile elements at the gel-glass interface, and diffusion of silicic acid in the gel interstitial solution. A comparison of theoretical results obtained by a semi-analytical solution to the model and experimental results suggests some modifications to develop a more advanced model.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 112: Symposium P – Scientific Basis for Nuclear Waste Management XI , 1987 , 703
Copyright
Copyright © Materials Research Society 1988

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References

1 Nogues, J.L., Vernaz, E., Jacquet-Francillon, N. in Scientific Basis for Nuclear Waste Management VIII, edited by Jantzen, C.M., Stone, J.A., Ewing, R.C. (Materials Research Society, Pittsburgh, 1984), p. 89 Google Scholar
2. Fillet, S., Vernaz, E., Nogues, J.L., Jacquet-Francillon, N. “Corrosion rate of nuclear glass in saturated media”. To be published in Advances in CeramicsGoogle Scholar
3. Goblet, P., Guetat, P., Lewi, J., Mangin, J.P., de Marsily, G., Raimbault, P. in Scientific Basis for Nuclear Waste Management IX, edited by Werme, L.O. (Materials Research Society, Pittsburgh 1985), p. 817 Google Scholar
4. Fillet, S., “Mécanismes de corrosion et comportement des actinides dans le verre R7T7”. Thèse de Docteur Ingénieur, Montpellier (1987)Google Scholar
5. Nogues, J.L., “Les mécanismes de corrosion des verres de confinement des produits de fission”. Thèse de Docteur Ingénieur, Montpellier (1984)Google Scholar
6. Iler, R.K., The Chemistry of Silica, (Wiley - Interscience publishers, 1979)Google Scholar
7. Ockendon, J.R., Hodgkins, W.R., in Moving boundary problems in heat flow and diffusion,(Clarendon Press, Oxford, 1975)Google Scholar
8. Wallace, R.M., Wicks, G.G. in Scientific Basis for Nuclear Waste Management edited by Brookins, D.G. (North Holland, New-York, 1982), p. 23 Google Scholar
9. Conradt, R., Roggendorf, H., Scholze, H., Scientific Basis for Nuclear Waste Management VIII, edited by Jantzen, C.M., Stone, J.A., Ewing, R.C. (Materials Research Society, Pittsburgh, 1984), p. 155 Google Scholar
10. Batchelor, G.K., J. Fluid.Mech., 74 n°1, 21, (1976)Google Scholar
11. Strachan, D.M., Nuclear and Chemical Waste Management, 4, 177 (1983)Google Scholar