Hostname: page-component-cd9895bd7-gxg78 Total loading time: 0 Render date: 2024-12-27T01:44:52.007Z Has data issue: false hasContentIssue false
  • English
  • Français

Predicting the Long Term Corrosion of Metal Containers for Nuclear Waste Disposal

Published online by Cambridge University Press:  28 February 2011

G. P. Marsh
G. P. Marsh*
Affiliation:
Materials Development Division, Harwell Laboratory, Oxon OXIl ORA, U.K.
Get access

Abstract

The prediction of the long term corrosion of metal containers for nuclear waste under geological disposal conditions requires the extrapolation of corrosion data over several hundred years. There is a general trend to use either simulation or ‘worst case’ experiments as a means of materials selection, but neither really addresses the problem of long term extrapolation. It is proposed that such an extrapolation can only be done convincingly if it is based on a sound and generally accepted mechanistic understanding of the processes involved. If such knowledge does not exist the first step must be to acquire it through experimental mechanistic studies. Subsequently such knowledge should be formulated into mathematical models, which can be used to make long term predictions, and which can be validated by comparison with short term experimental results. The application of this combined mathematical modelling/experimental approach is illustrated for three corrosion processes which may affect carbon steel containers, namely general corrosion, localised attack and stress corrosion cracking.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 112: Symposium P – Scientific Basis for Nuclear Waste Management XI , 1987 , 85
Copyright
Copyright © Materials Research Society 1988

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

1. Marsh, G.P., Pinard-Legry, G., Smailos, E., Casteels, F., Quang, K. Vu, Cripps, J and Haijtink, B., High Level Waste Corrosion and Design, Proceedings of the 2nd European Community Conference on Radioactive Waste Management and Disposal, Edited by Simon, R.R., Luxembourg, 1985.Google Scholar
2. Westerman, R.E. and Pitman, S.G., Corrosion of Candidate Iron-Base Waste Package Structural Barrier Materials in Moist Salt Environments, MRS Conference on Radioactive Waste Management, Boston, November 1984.Google Scholar
3. Simpson, J.P., Schenck, R. and Knecht, B., Corrosion Rate of Unalloyed Steels and Cast Irons in Reducing Granitic Groundwaters and Chloride Solutions, MRS Conference on Radioactive Waste Management, Stockholm, 1985, (Editor Werme, L.).Google Scholar
4. Marsh, G.P., Bland, I.D., Taylor, K.J., Sharland, S.M. and Tasker, P.W., An Assessment of Carbon Steel Overpacks for Radioactive Waste Disposal, Report EUR-10437 EN, Published by the Commission of the European Communities, 1986.Google Scholar
5. Marsh, G.P. and Taylor, K.J., An Assessment of Carbon Steel Overpacks for Radioactive Waste Disposal, to be published in Corrosion Science.Google Scholar
6. Marsh, G.P., Harker, A.H. and Taylor, K.J., Corrosion of Carbon Steel Nuclear Waste Containers in Marine Sediment, AERE Report R 12510, 1987 (submitted for publication in Corrosion).Google Scholar
7. Marsh, G.P., Taylor, K.J., Sharland, S.M. and Tasker, P.W., An Approach for Evaluating the General and Localised Corrosion of Carbon Steel Containers for Nuclear Waste Disposal, MRS Conference on Radioactive Waste Management, Boston, 1986.Google Scholar
8. Smailos, E., Schwarzkopf, W. and Kirster, R., Corrosion Behaviour of Container Materials for the Disposal of High Level Waste Forms in Rock Salt Formations, Karlsruhe Nuclear Research Centre Report KfK 4265, 1987.Google Scholar
9. Molecke, M.A., Ruppen, J.A. and Diegle, R.B., Materials for High Level Waste Canister/Overpacks in Salt Formations, Nuclear Technology, Vol. 63, pp 476–506, 1983.CrossRefGoogle Scholar
10. Marsh, G.P., Taylor, K.J., Bland, I.D., Westcott, C., Tasker, P.W. and Sharland, S.M., Evaluation of the Localised Corrosion of Carbon Steel Overpacks for Nuclear Waste Disposal in Granite Environments, MRS Conference on Radioactive Waste Management, Stockholm, 1985.Google Scholar
11. Sharland, S.M., The Theoretical Evaluation of Localised Corrosion in Radioactive Waste Containers, MRS Conference on Radioactive Waste Management, Boston, 1986.Google Scholar
12. Beavers, J.A. and Thompson, N.J., Effect of Pit Wall Reactivity on Pit Propagation in Carbon Steel, Corrosion, Vol.43, No. 3, pp 185–188, 1987.Google Scholar
13. Beavers, J.A., Thompson, N.J. and Parkins, R.N., Stress Corrosion Cracking of Low Strength Carbon Steels in Candidate High Level Waste Repository Environments: Environmental Effects, Nuclear and Chemical Waste Management, Vol. 5, No. 4, pp 279–296 1985.CrossRefGoogle Scholar
14. Parkins, R.N., Stress Corrosion Cracking Tests on Electron Beam Welded Carbon Steel Specimens in Carbonate-Bicarbonate Solutions, AERE Report G3583, 1985.Google Scholar
15. Ove Arup and Partners Ltd., Geological Disposal of High Level Radioactive Waste, Container Design Study, a Report to the UK Department of the Environment and the Commission of the European Communities, March 1986.Google Scholar
16. Haijtink, B., Corrosion Behaviour of Container Materials for Geological Disposal of High Level Waste, Annual Progress Report 1984, EUR Report 10398 EN, published by the Commission of the European Communities.Google Scholar
17. Debruyn, W., Dresselaers, J. and Tas, H., Corrosion of Container and Infrastructure Materials Under Clay Repository Conditions, SCK/CEN Report N15/241/JD/MW, 1987 (Mol, Belgium).Google Scholar
18. Merz, M.D. and Wang, R., Test Methods to Predict Long Term Corrosion of Container Materials in Repositories, MRS Conference on Scientific Basis of Nuclear Waste Management, Boston, 1984.Google Scholar
19. Lutton, J.M., Brehm, W.F., Maffei, H.P., Rivera, C.L. and Anantatmula, R.P., General Corrosion Studies of Candidate Container Materials for the Basalt Waste Isolation Project, Westinghouse Hanford Company, PO Box 1970, Richland, Washington, USA.Google Scholar
20. Lanza, F., Final Report of the Near-Field Task Group of the OECD-NEA Seabed Working Group, to be published by Sandia Laboratories.Google Scholar