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Mechanistic Model for the Durability of Concrete Barriers Exposed to Sulphate-Bearing Groundwaters

Published online by Cambridge University Press:  21 February 2011

Alan Atkinson  and
John A. Hearne
Alan Atkinson
Affiliation:
Materials Development Division, Building 429, Harwell Laboratory, Oxon. OX11 0RA, UK
John A. Hearne
Affiliation:
Materials Development Division, Building 429, Harwell Laboratory, Oxon. OX11 0RA, UK
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Abstract

The durability of concretes in radioactive waste repositories is likely to be limited by their reaction with sulphate-bearing groundwaters. In such a situation the concrete slowly degrades by sulphate penetrating into the concrete where it reacts with the cement to cause stress and eventual disruption. Experiments have been carried out to quantify these reactions and the resulting expansions. The data have been incorporated into an overall mechanistic model for sulphate degradation in which the criterion for disruption is the accumulation of a critical amount of stored elastic energy in the reaction zone. The results of this model are in good agreement with those of an earlier empirical model and enable extrapolations to be made to different concretes and groundwaters.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 176: Symposium U – Scientific Basis for Nuclear Waste Management XIII , 1989 , 149
Copyright
Copyright © Materials Research Society 1990

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References

REFERENCES

1. Atkinson, A. and Hearne, J.A., Harwell Laboratory Report AERE-R11465, 1984.Google Scholar
2. Atkinson, A., Goult, D.J. and Hearne, J.A., Mat. Res. Soc. Symp. Proc. 50, 239 (1985).Google Scholar
3. Gutt, W.H. and Harrison, W.H., Concrete 11, 35 (1977).Google Scholar
4. Atkinson, A., Haxby, A. and Hearne, J.A., UK Nirex Report NSS/R127, 1988.Google Scholar
5 Atkinson, A. and Nickerson, A.K., J. Mater. Sci. 19, 3068 (1984).Google Scholar
6. Atkinson, A., Nelson, K. and Valentine, T.M., Nuclear and Chemical Waste Management 6, 241 (1986).Google Scholar
7. Bernstein, H.L., Metall. Trans. A 18A, 975 (1987).Google Scholar
8. Evans, H.E. and Lobb, R.C., Corros. Sci. 24, 209 (1984).Google Scholar
9. Eden, N. B. and Bailey, J.E., J. Mater. Sci. 19, 150 (1984).Google Scholar
10. Rasmuson, A., Neretnieks, I. and Zhu, M., in Proceedings of an NEA Workshop on Near-field Assessment of Repositories for Low and Medium Level Radioactive Waste Baden (1987) pp 159–171.Google Scholar