Hostname: page-component-77c89778f8-5wvtr Total loading time: 0 Render date: 2024-07-21T06:37:34.512Z Has data issue: false hasContentIssue false

Thermokinetic Model of Borosilicate Glass Dissolution: Contextual Affinity

Published online by Cambridge University Press:  21 February 2011

T. Advocat
Affiliation:
CEN-Valrhô, SDHA, BP 171, 30205 Bagnols-sur-Cèze Cedex, France
J.L. Crovisier
Affiliation:
CGS (CNRS), 1 rue Blessig 67000 Strasbourg, France
B. Fritz
Affiliation:
CGS (CNRS), 1 rue Blessig 67000 Strasbourg, France
E. Vernaz
Affiliation:
CEN-Valrhô, SDHA, BP 171, 30205 Bagnols-sur-Cèze Cedex, France
Get access

Abstract

Short and long-term geochemical interactions of R7T7 nuclear glass with water at 100°C were simulated with the DISSOL thermokinetic computer code. Both the dissolved glass quantity and the resulting water composition, saturation states and mineral quantities produced were calculated as a function of time. The rate equation used in the simulation was first proposed by Aagaard and Hegelson: v = k+.S.a(H+)-n(l - e-(A/RT)). It simulates a gradually diminishing dissolution rate as the reaction affinity diminishes. The best agreement with 1-year experimental data was obtained with a reaction affinity calculated from silica activity (Grambow's hypothesis) rather than taking into account the activity of all the glass components as proposed by Jantzen and Plodinec. The concept of residual affinity was introduced by Grambow to express the fact that the glass dissolution rate does not cease. We prefer to replace the term “residual affinity” by “contextual affinity”, which expresses the influence on the dissolution rate of three factors: the solution chemistry, the metastability of SiO2(m), and the possible precipitation of certain aluminosilicates such as zeolites.

Type
Research Article
Copyright
Copyright © Materials Research Society 1990

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

[1] Aagaard, P. and Hegelson, H.C., Am. J. of Sci. 282, 237285 (1982).Google Scholar
[2] Hegelson, H.C., Murphy, W.M. and Aagaard, P., Geoch. Cosmoch. Acta, 4, 24052432 (1984).Google Scholar
[3] Lasaga, A.C., J. Geo. Res. 81B6 40094025 (1984).Google Scholar
[4] Grambow, B., in Scientific Basis for Nuclear Waste Management VIII, (Mater. Res. Soc. Proc.) 44, 1527 (1984).Google Scholar
[5] Grambow, B., SKB Technical Report 87-02 (1987).Google Scholar
[6] Vernaz, E., Advocat, T. and Dussossoy, J.L., presented at the 4th International Symposium on Ceramics in Nuclear Waste Management (91st Am. Ceram. Soc. Meeting, 1989).Google Scholar
[7] Grambow, B. and Strachan, D.M., in Scientific Basis for Nuclear Waste Management XI, (Mater. Res. Soc. Proc.) 112, 713724 (1988).Google Scholar
[8] Pederson, L.R., Buckwalter, C.Q., McVay, G.L., Riddle, R., in Scientific Basis for Nuclear Waste Management VI, (Mater. Res. Soc. Proc.) 15, 4754 (1982).Google Scholar
[9] Haaker, R., Malow, J. and Offermann, P.. in Scientific Basis for Nuclear Waste Management VIII, (Mater. Res. Soc. Proc.) 44, 121128 (1985).Google Scholar
[10] Iseghem, P. Van and Grambow, B., in Scientific Basis for Nuclear Waste Management XI, (Mater. Res. Soc. Proc.) 11, 631639 (1988).Google Scholar
[11] Godon, N. and Vernaz, E., in Scientific Basis for Nuclear Waste Management (this volume) (Mater. Res. Soc. Proc.).Google Scholar
[12] Paul, A., J. Mat. Sci., 12, 22462268 (1977).Google Scholar
[13] Jantzen, C.M. and Plodinec, M.J., J. Non Cry. Sol., 67, 207223 (1984).Google Scholar
[14] Fillet, S., PhD Thesis: University of Montpellier, France (1987).Google Scholar
[15] Fritz, B., Sci. Geol. Mem., 65, (1981).Google Scholar
[16] Tardy, Y. and Fritz, B., Clays Minerals, 16, 361373 (1981).Google Scholar
[17] Crovisier, J.L., Advocat, T., Petit, J.C. and Fritz, B., in Scientific Basis for Nuclear Waste Management XII, (Mater. Res. Soc. Proc.) 127, 5764 (1989).Google Scholar
[18] Bourcier, W.L., Knauss, K.G. and Merzbacher, C.I., presented at 4th International Symposium on Ceramics in Nuclear Waste Management (91st Am. Ceram. Soc. Meeting, 1989).Google Scholar
[19] Hegelson, H.C., Delany, J.M., Nesbitt, H.W. and Bird, D.K., Am. J. Sci, 274, 10891198 (1978).Google Scholar