Hostname: page-component-8448b6f56d-jr42d Total loading time: 0 Render date: 2024-04-20T03:57:12.678Z Has data issue: false hasContentIssue false

The Development of a Mechanistic Basis for Modelling Fuel Dissolution and Container Failures Under Waste Vault Conditions

Published online by Cambridge University Press:  26 February 2011

D. W. Shoesmith
Affiliation:
Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment, Pinawa, Manitoba, Canada ROE ILO
S. Sunder
Affiliation:
Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment, Pinawa, Manitoba, Canada ROE ILO
B. M. Ikeda
Affiliation:
Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment, Pinawa, Manitoba, Canada ROE ILO
F. King
Affiliation:
Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment, Pinawa, Manitoba, Canada ROE ILO
Get access

Abstract

Due to the long containment periods required for radionuclides in a nuclear waste disposal vault, the justification that a particular containment system is acceptable will be based on relatively short-term experimental data used to support predictive models. To justify this approach, we must possess a sound mechanistic understanding of processes such as fuel dissolution, radionuclide release and container corrosion. Since these processes are driven by oxidants in the vault, it is natural to study them by electrochemical techniques. In this paper, we have reviewed a number of electrochemical methods used in the study of waste vault reactions. More detailed descriptions are given of the development of predictive models for the dissolution of UO2, the crevice corrosion of titanium alloys and the uniform dissolution of copper.

Type
Research Article
Copyright
Copyright © Materials Research Society 1989

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

REFERENCES

1. Marsh, G.P., in Scientific Basis for Nuclear Waste Management XI, edited by Apted, M.J. and Westerman, R.E., (Mater. Res. Soc. Proc. Pittsburgh, PA, 1987) p. 85.Google Scholar
2. Heimann, R.B., in Scientific Basis for Nuclear Waste Management X, edited by Bates, J.K. and Seefeldt, W.B., (Mater. Res. Soc. Proc. Pittsburgh, PA, 1987) p. 409.Google Scholar
3. Marsh, G.P., Taylor, K.J., Sharland, S.M. and Tasker, P.W., Scientific Basis for Nuclear Waste Management X, edited by Bates, J.K. and Seefeldt, W.B., (Mater. Res. Soc. Proc. Pittsburgh, PA, 1987) p. 227.Google Scholar
4. Parkins, R.N., Harwell Report G-AERE-3583, 1985.Google Scholar
5. Clarke, C.F., Hardie, D. and McKay, P., Corros. Sci. 26(6), 425 (1986).Google Scholar
6. Beavers, J.A., Thompson, N.G., Markworth, A.J., Cialone, H.J., Majumdar, B.S. and McCoy, J.K., U.S. Office of Nuclear Regulatory Research, NUREG/CR-4955, BMI-2155, 1987.Google Scholar
7. Moody, N.R., Robinson, S.L. and Greulich, F.A., Sandia National Laboratories Report, SAND85–8203, 1985.Google Scholar
8. Sorensen, N.R., Ruppen, J.A. and Schutz, R.W., Sandia National Laboratories Report, SAND83–2207C, 1984.Google Scholar
9. Shoesmith, D.W., Sunder, S., Bailey, M.G. and Wallace, G.J., submitted to Corros. Sci.Google Scholar
10. Shoesmith, D.W., Sunder, S., Bailey, M.G. and Owen, D.G., in Proc. Fifth International Symposium on Passivity, edited by Froment, M., Elsevier Publishing Co., Amsterdam, 1983, p. 125.Google Scholar
11. Marsh, G.P. and Taylor, K.J., Corros. Sci. 28(3), 289 (1988).Google Scholar
12. King, F. and Litke, C.D., Atomic Energy of Canada Limited Reports, AECL-9571, 9572, 9573, in press.Google Scholar
13. Bailey, M.G., Johnson, L.H. and Shoesmith, D.W., Corros. Sci. 25, 233 (1985).CrossRefGoogle Scholar
14. Glass, R.S., Overturf, G.E. III, Van Konynenburg, R.A. and Daniel McCright, R., Lawrence Livermore National Lab. Report, UCRL-92311, 1985.Google Scholar
15. Glass, R.S., Van Konynenburg, R.A. and Overturf, G.E., Lawrence Livermore National Lab. Report, UCRL-92941, 1985.Google Scholar
16. Ikeda, B.M., Bailey, M.G., Clarke, C.F. and Shoesmith, D.W., Atomic Energy of Canada Limited Report, AECL-9568, 1988.Google Scholar
17. Marsh, G.P., Bland, I.D. and Taylor, K.J., UKAEA Report, AERE R 12665, 1987.Google Scholar
18. Shoesmith, D.W., Sunder, S., Bailey, M.G. and Wallace, G.J., in Proc. 2nd Inter. Conf. on Radioactive Waste Management, Winnipeg, Sept. 7–11, 1986, publ, by Canadian Nuclear Society, Toronto, 1986, p. 674.Google Scholar
19. Garisto, F. and Garisto, N.C., Nucl. Sci. and Eng. 90, 103 (1985).Google Scholar
20. Garisto, N.C. and Garisto, F., Ann. Nucl. Energy, 13(11), 591 (1986).Google Scholar
21. Garisto, N.C. and Garisto, F., Atomic Energy of Canada Limited Report, AECL-9562, 1988.Google Scholar
22. Grenthe, I., in Scientific Basis for Nuclear Waste Management XI, edited by Apted, M.J. and Westerman, R.E. (Mater. Res. Soc. Proc. Pittsburgh, PA, 1987) p. 73.Google Scholar
23. Johnson, L.H., Shoesmith, D.W. and Stroes-Gascoyne, S., in Scientific Basis for Nuclear Waste Management XI, edited by Apted, M.J. and Westerman, R.E., (Mater. Res. Soc. Proc. Pittsburgh, PA, 1987) p. 99.Google Scholar
24. Stroes-Gascoyne, S., Johnson, L.H., Tait, J.C. and Sellinger, D.M., this symposium.Google Scholar
25. McNeil, M.B., in Scientific Basis for Nuclear Waste Management X, edited by Bates, J.K. and Seefeldt, W.B., (Mater. Res. Soc. Proc. Pittsburgh, PA, 1987) p. 199.Google Scholar
26. King, F. and Litke, C.D., this symposium.Google Scholar
27. Cheung, S.C.H., in Centennial Symposium on Management of Waste Contamination of Groundwater, edited by Yong, R.N., (Canadian Society for Civil Engineering, Montreal, May 1987) p. 195.Google Scholar
28. Gillham, R.W., Sharma, H.D. and Robin, M.J.L., Atomic Energy of Canada Technical Record, TR-426*, 1987.Google Scholar