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The Role of Water Diffusion in the Corrosion of the French Nuclear Waste Glass SON 68 under Solution Saturation Conditions

Published online by Cambridge University Press:  01 February 2011

Karine Ferrand ,
Abdesselam Abdelouas ,
Bernd Grambow  and
Jean-Louis Crovisier
Karine Ferrand
Affiliation:
SUBATECH (UMR 6457), 4, rue Alfred Kastler B.P. 20722 44307 Nantes cedex 3, France.
Abdesselam Abdelouas
Affiliation:
SUBATECH (UMR 6457), 4, rue Alfred Kastler B.P. 20722 44307 Nantes cedex 3, France.
Bernd Grambow
Affiliation:
SUBATECH (UMR 6457), 4, rue Alfred Kastler B.P. 20722 44307 Nantes cedex 3, France.
Jean-Louis Crovisier
Affiliation:
Ecole et Observatoire des Sciences de la Terre, Centre de Géochimie de la Surface - CNRS (UMR 7517), 1, rue Blessig, 67084 Strasbourg Cedex, France.
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Abstract

The alteration kinetics of the French borosilicate glass SON 68 have been investigated in a dynamic system at 50°C and 90°C under solution saturation conditions. The pH was adjusted to 4.8, 7.2 and 9.8 with addition of chemical buffers or/and by bubbling CO2 in solution. In all experiments, Li and Cs leaching seems to be controlled by a diffusion process. The Li- and Cs-concentrations were used to calculate the sum of ionic exchange and matrix dissolution rates of the glass while Mo-concentrations indicate matrix dissolution. The final leaching rates in saturation condition of Mo were in the order of 10–4–10- g.m-2.d-1 in good agreement with those given in literature for static tests. The glass surface was studied by scanning and transmission electron microscopy (SEM, STEM) for analysis of the corrosion products and by infrared spectroscopy (FTIR) for water speciation and concentration. A good inverse correlation between the water content and the alkali concentrations released from the glass has been obtained. About three hydrogen ions replaced one alkali ion. Modeling of the experimental data using GM 2001 model gives water diffusion coefficients between 10–20 and 10–22 m2.s-1.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 807: Symposium Scientific Basis for Nuclear Waste Management XXVII , 2003 , 193
Copyright
Copyright © Materials Research Society 2004

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