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The Corrosion of Spent Uo2-Fuel in Synthetic Groundwater

Published online by Cambridge University Press:  25 February 2011

P S Forsyth ,
K Svanberg  and
L Werme
P S Forsyth
Affiliation:
Studsvik Energiteknik AB, Sweden
K Svanberg
Affiliation:
Studsvik Energiteknik AB, Sweden
L Werme
Affiliation:
The Swedish Nuclear Fuel Supply Co, Sweden
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Abstract

Segments of fuel and clad have been leached in deionized water and in groundwater. The leachants were centrifuged through membrane filters. Both centrifugate and the filters were analysed for U, Sr-90, α- and γ-emitters. The results are discussed in terms of preferential leaching, solubility limitations and adsorption effects. For U an apparent saturation at about 800 ppb was observed. Pu also appeared to attain saturation at a few ppb. For Sr the leach rate was 3·10-7 /d after ca 400 days. Attempts to impose reducing conditions showed decreased leach rates.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 26: Symposium D – Scientific Basis for Nuclear Waste Management VII , 1983 , 179
Copyright
Copyright © Materials Research Society 1984

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References

REFERENCES

1. Eklund, U.B. and Forsyth, R.S., KBS Technical Report No 70 (1978).Google Scholar
2. Katayama, Y.B.et al, PNL-3173 (1980).Google Scholar
3. Vandergraaf, T.T., AECL TR-100 (1980).Google Scholar
4. Johnson, L.H., AECL-6837 (1982)Google Scholar
5. Elkert, J., AB Atomenergi report: AE-RF-72–374 (1972).Google Scholar
6. Koizumi, M.et al, J. Nucl. Materials 51, 90–94 (1974).Google Scholar
7. Forsyth, R.S. and Blackadder, W.H., Unpublished results.Google Scholar
8. Paquette, J. and Lemire, R.J., Nucl. Sci. Eng., 79, 26–48 (1981).CrossRefGoogle Scholar
9. Norris, A.E., Report ONWI/SUB/79/ESII-01200-11 (1979).CrossRefGoogle Scholar