Hostname: page-component-8448b6f56d-gtxcr Total loading time: 0 Render date: 2024-04-25T05:41:59.269Z Has data issue: false hasContentIssue false
  • English
  • Français

An Approach for Evaluating the General and Localised Corrosion of Carbon-Steel Containers for Nuclear Waste Disposal

Published online by Cambridge University Press:  28 February 2011

G.P. Marsh ,
K.J. Taylor ,
S.M. Shrland  and
P.W. Tasker
G.P. Marsh
Affiliation:
Materials Development Division, Harwell Laboratory, Oxfordshire, OXI1 ORA, U.K
K.J. Taylor
Affiliation:
Materials Development Division, Harwell Laboratory, Oxfordshire, OXI1 ORA, U.K
S.M. Shrland
Affiliation:
Theoretical Physics Division, Harwell Laboratory, Oxfordshire, OXI1 ORA, U.K
P.W. Tasker
Affiliation:
Theoretical Physics Division, Harwell Laboratory, Oxfordshire, OXI1 ORA, U.K
Get access

Abstract

The paper considers the long term corrosion of carbon-steel containers for heat generating nuclear waste in a granitic repository. Under such conditions carbon steel may exhibit general, localised or passive corrosion behaviour depending on the exact composition and redox potential of the groundwater contacting the containers; localised corrosion being of most concern because it has the fastest propagation rate. It is well established, however, that such localised corrosion is only possible when the environment is sufficiently oxidising to maintain a positive potential gradient between the cathodic surface and the corrosion sites, which requires that species with oxidising potentials greater than water need to be present. This fact provides a basis for estimating the periods during which containers may be subject to localised and subsequently to general corrosion, and hence for making an overall assessment of the metal allowance required for a specified container life. A model for the diffusion transport of oxygen has been developed, and a sensitivity analysis has shown that the period of possible localised attack is strongly dependent on the passive film leakage current, the radiation dose rate and the oxygen diffusion coefficient.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 84: Symposium L – Scientific Basis for Nuclear Waste Management X , 1986 , 227
Copyright
Copyright © Materials Research Society 1987

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., Nucl. Energy, 21, No. 4, 253 (1982).Google Scholar
2. Marsh, G.P., Bland, I.D., Desport, J.A., Naish, C.C., Westcott, C. and Taylor, K.J., European Appl. Res. Rept. - Nucl. Sci. Technol., 5, No. 2, 223 (1983).Google Scholar
3. Marsh, G.P., Bland, I.D., Taylor, K.J., Sharland, S.M. and Tasker, P., 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
4. Parkins, R.N., Stress Corrosion Cracking Tests on Electron Beam Welded Carbon Steel Specimens in Carbonate-Bicarbonate Solution, AERE-G3583 (1985).Google Scholar
5. Hardie, D., An Assessment of the Risk of Embrittlement of a Steel Container by Hydrogen Picked up from the Ocean Bed, AERE-G3587 (1985).Google Scholar
6. 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, September 1985, editor Werme, L..CrossRefGoogle Scholar
7. Sharland, S.M., A Mathematical Model of Crevice and Pitting Corrosion, TP-1183 (1986).CrossRefGoogle Scholar
8. Pourbaix, M., Corrosion, 26, No. 10, (October 1970, 431–438.Google Scholar
9. Deltombe, E. and Pourbaix, M., CEBELCOR Rapport Technique 8, Centre Belge d'Etude de la Corrosion.Google Scholar
10. Sutcliffe, J.M., Fessler, R.R., Boyd, W.K. and Parkins, R.N., Corrosion, 28, No. 8, 313–320 (1972).Google Scholar
11. Thomas, J.G.N., Nurse, T.J. and Walker, R., Br. Corros. J., 5, 87–92, (March 1970).CrossRefGoogle Scholar
12. Localized Corrosion, NACE-3, edited by Staehle, R.W., Brown, B.F., Kruger, J., Agrawal, A., (published by National Association of Corrosion Engineers.Google Scholar
13. Pourbaix, M., The Theory of Stress Corrosion Cracking in Alloys, p. 17, edited by Scully, J.C. (published by NATO Scientific Affairs Division, Brussels) 1971.Google Scholar
14. Brown, B.F., Fujii, C.T. and Dahlberg, E.P., J. of Electrochem. Soc., 116, No. 2, pp. 218–219 (1969).Google Scholar
15. Sandoz, G., Fujii, C.T. and Brown, B.F., Corrosion Science, 10, No. 12, pp. 839–846 (1970).CrossRefGoogle Scholar
16. Final Storage of Spent Nuclear Fuel - KBS 3, I - General, SKBF/KBS Report, eds. Svenke, E. and Nilsson, L.B. (1983).Google Scholar
17. Ekbom, L., Copper as Canister Material for Unreprocessed Nuclear Waste -Evaluation with Respect to Corrosion, KBS-TR-90, Final Report 1978-03-31.Google Scholar
18. Talbot, A., The Accurate Numerical Inversion of Laplace Transforms, J. Inst. Maths. Applics., 23, 97 (1979).CrossRefGoogle Scholar
19. Marsh, G.P., Pinard-Legry, G., Smailos, E., Casteels, F., Quang, K. Vu, Cripps, J. and Haijtink, B., HLW Container Corrosion and Design, Proceedings of 2nd European Community Conference on Radioactive Waste Management and Disposal, Luxembourg, p. 314, (1985).Google Scholar
20. Glass, G.K, Corrosion Science, 26, No. 6, pp 441–454 (1986).Google Scholar