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The Long-Term Corrosion and Modelling of Two Simulated Belgian Reference High-Level Waste Glasses - Part II

Published online by Cambridge University Press:  21 February 2011

J. Patyn
Affiliation:
S.C.K/C.E.N., Boeretang 200, B-2400 Mol, Belgium
P. Van Iseghem
Affiliation:
S.C.K/C.E.N., Boeretang 200, B-2400 Mol, Belgium
W. Timmermans
Affiliation:
S.C.K/C.E.N., Boeretang 200, B-2400 Mol, Belgium
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Abstract

The long term corrosion of two reference Belgian high-level waste glasses (SAN60 and SM58) were investigated in pure water. The corrosion was studied using powdered glass at a high surface area to volume ratio and temperatures of 90 and 120°C. The experimental data at 90°C reveal a “final” leach rate which decreases with time. At 120°C this “final” state is transient and followed by an enhanced dissolution, which was correlated with extensive surface crystallization. Modelling using the PHREEQE and GLASSOL computer codes described the initial corrosion, but was unable to account for the enhanced dissolution at 120°C.

Type
Research Article
Copyright
Copyright © Materials Research Society 1990

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References

REFERENCES

[1] Iseghem, P. Van, Timmermans, W., Batist, R. De; in Scientific Basis for Nuclear Waste Management VIII, edited by Jantzen, C.M., Stone, J.A. and Ewing, R.C. (Mater. Res. Soc., Proc. 44, Pittsburgh, PA 1985, pp.5562 Google Scholar
[2] Iseghem, P. Van and Grambow, B.; in Scientific Basis for Nuclear Waste Management XI, edited by Apted, M.J. and Westerman, R.E. (Mater. Res. Soc. Proc. 112, Pittsburg, PA 1988), pp.631640 Google Scholar
[3] PNL-5157, Final Report of the Defense High-Level Waste Leaching Mechanisms Program, 1984 Google Scholar
[4] EUR 10852, Testing and Evaluation of Solidified High Level Radioactive Waste, edited by Hall, A.R. (Graham & Trotman Publ. 1987)Google Scholar
[5] Shade, J.W. and Strachan, D.M., Ceramic Bulletin vol.65, no 12, 1986, pp. 15681573 Google Scholar
[6] Grambow, B., Nuclear Waste Glass Dissolution: Mechanism, Model and Application Report to JSS-Project, Phase IV, SKB, 1987 Google Scholar