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Key Parameters of Glass Dissolution in Integrated Systems

  • Etienne Y. Vernaz (a1) and Nicole Godon (a1)

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.

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[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.
[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).
[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.
[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.
[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.
[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.
[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.
[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).

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Key Parameters of Glass Dissolution in Integrated Systems

  • Etienne Y. Vernaz (a1) and Nicole Godon (a1)

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