Hostname: page-component-cd9895bd7-jn8rn Total loading time: 0 Render date: 2024-12-27T01:42:55.087Z Has data issue: false hasContentIssue false

Key Parameters of Glass Dissolution in Integrated Systems

Published online by Cambridge University Press:  28 February 2011

Etienne Y. Vernaz
Affiliation:
CEA, CEN Valrho, BP 171, 30205 BagnoIs-sur-Cèze Cedex, France
Nicole Godon
Affiliation:
CEA, CEN Valrho, BP 171, 30205 BagnoIs-sur-Cèze Cedex, France
Get access

Abstract

Leaching cells were designed to test the alterability of nuclear waste glasses under conditions closely simulating an actual geological repository. This paper summarizes the results of twenty long-duration tests simulating a variety of storage conditions. The effects of the backfilling materials, the canister, glass cracking and crystallization, a activity and the nature of the host rock are discussed. Moreover, an experiment has been in progress for over seven years in a granite medium; after three years the corrosion rate dropped to about 2 × 10−3 g m−2 d−1, and is sustained only by the water renewal due to sampling at regular intervals. These results constitute a valuable data base on R7T7 glass alteration in geological media at 90°C. Glass alteration mechanisms described in pure water appear to be applicable to a hard rock medium. In clay and salt, however, considerable work remains to be done before environmental factors can be taken into account in an overall dissolution model.

Type
Research Article
Copyright
Copyright © Materials Research Society 1991

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] Grambow, B.. “A General Rate Equation for Nuclear Waste Glass Corrosion”. In Scientific Basis for Nuclear Waste Management VIII, edited by Jantzen, C., Stone, J. and Ewing, R. (Mater Res Soc Symp Proc 44, Pittsburgh, 1985) pp 1524.Google Scholar
[2] Vernaz, E. and Dussossoy, J.L.. “Current State of Knowledge of Nuclear Waste Glass Corrosion Mechanisms: The Case of R7T7 Glass”. Submitted to Applied Geochemistry special issue (1991).Google Scholar
[3] Nogues, J.L., Vernaz, E. and Jacquet-Francillon, N.. “Alterability of the French LWR Solution Reference Glass in Repository Conditions”. In Scientific Basis for Nuclear Waste Management VIII, edited by Jantzen, C., Stone, J. and Ewing, R. (Mater Res Soc Symp Proc 44, Pittsburgh, 1985) pp 195204.Google Scholar
[4] Godon, N., Vernaz, E., Thomassin, J.H. and Touray, J.C.. “Effect of Environmental Materials on Aqueous Corrosion of R7T7 Glass”. In Scientific Basis for Nuclear Waste Management XII, edited by Lutze, W. and Ewing, R. (Mater Res Soc Symp Proc 127, Pittsburgh, 1989) pp 97104.Google Scholar
[5] Godon, N. and Vernaz, E.. “R7T7 Nuclear Waste Glass Behavior in Moist Clay: Role of the Clay Mass / Surface Area Ratio”. In Scientific Basis for Nuclear Waste Management XIII, edited by Oversby, V.M. and Brown, P.W. (Mater Res Soc Symp Proc 176, Pittsburgh, 1990) pp 319326.Google Scholar
[6] Vernaz, E., Advocat, T. and Dussossoy, J.L.. “Effect of the SA/V Ratio on the Long-Term Corrosion Kinetics of R7T7 Glass”. In Nuclear Waste Management III: Ceramic Transactions (Amer Ceram Soc 9, 1990) pp 175–185.Google Scholar
[7] Mouche, E. and Vernaz, E.. “Aqueous Corrosion of the French LWR Solution Reference Glass: First-Generation Model”. In Scientific Basis for Nuclear Waste Management XI, edited by Apted, M.J. and Westerman, R.E. (Mater Res Soc Symp Proc 112, Pittsburgh, 1988) pp 703712.Google Scholar
[8] Vernaz, E. and Dussossoy, J.L.. Basic Mechanisms of Aqueous Corrosion of Nuclear Waste Glasses. Commission of the European Communities (CEC) Contract FI1W-0030 F. Final Report (Luxembourg, 1990).Google Scholar