Hostname: page-component-8448b6f56d-m8qmq Total loading time: 0 Render date: 2024-04-19T08:18:05.364Z Has data issue: false hasContentIssue false
  • English
  • Français

Spent Fuel Degradation

Published online by Cambridge University Press:  28 February 2011

Roy S. Forsyth
Roy S. Forsyth*
Affiliation:
Studsvik AB, S-611 82 Nyköping, Sweden
Get access

Abstract

The degradation and dissolution of spent nuclear fuel in groundwaters occurs by three partly concurrent processes: dissolution of mobile species which have migrated to the fuel rod void, grain boundary attack and matrix dissolution. Of the first two processes, both clearly dependent on the irradiation history of the fuel, the first is fairly well understood, but there is currently insufficient data on the migration of key nuclides to grain boundaries during reactor operation and their release kinetics during subsequent water corrosion to enable satisfactory modelling of this process to be performed.

This paper presents results from recent experiments included in the Swedish programme which are relevant to this issue.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 212: Symposium P – Scientific Basis for Nuclear Waste Management XIV , 1990 , 177
Copyright
Copyright © Materials Research Society 1991

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 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, 1988) p 99.Google Scholar
2 Forsyth, R.S., Werme, L.O. and Bruno, J., J. Nucl. Mater. 138 (1986) 1–15.Google Scholar
3 Forsyth, R.S., Werme, L.O.. SKB Technical Report 87–16, Stockholm, Sweden 1987.Google Scholar
4 Werme, L.O. and Forsyth, R.S., SKB Technical Report 89–14, Stockholm, Sweden 1989.Google Scholar
5 Choppin, G.R., in Scientific Basis for Nuclear Waste Management XIII, edited by Oversby, V.M. and Brown, P.W., (Mater. Res. Soc. Proc, Pittsburgh, PA, 1990) p 449.Google Scholar
6 Forsyth, R.S., Eklund, U.B., Mattsson, O. and Schrire, D., SKB Technical Report 90–04, Stockholm, Sweden 1990.Google Scholar
7 Wilson, C.N. and Oversby, V.M., in Proc. Waste Management 85, edited by Post, R.G., Tucson (1985) p 497.Google Scholar
8 Forsyth, R.S., Proceedings of the IAEA Specialist Meeting on Post-Irradiation Examination Techniques for Reactor Fuel, Workington, England, September 1990.Google Scholar
9 Forsyth, R.S., Mattsson, O. and Schrire, D.. To be published.Google Scholar
10 Schrire, D., Studsvik Technical Report NF(P)-84/10. 1984.Google Scholar