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Uranium (iv) Dioxide and Simfuel as Chemical Analogues of Nuclear Spent Fuel Matrix Dissolution. A Comparison of Dissolution Results in a Standard Naci/NaHCO3 Solution

Published online by Cambridge University Press:  15 February 2011

Jordi Bruno ,
I. Casas ,
E. Cera ,
J. de Pablo ,
J. GimÉnez  and
M. E. Torrero
Jordi Bruno
Affiliation:
MBT Tecnologia Ambiental, 08290 Barcelona, Spain.
I. Casas
Affiliation:
Dept. Chem. Eng., Universitat Politècnica de Catalunya, 08028 Barcelona, Spain.
E. Cera
Affiliation:
MBT Tecnologia Ambiental, 08290 Barcelona, Spain.
J. de Pablo
Affiliation:
Dept. Chem. Eng., Universitat Politècnica de Catalunya, 08028 Barcelona, Spain.
J. GimÉnez
Affiliation:
Dept. Chem. Eng., Universitat Politècnica de Catalunya, 08028 Barcelona, Spain.
M. E. Torrero
Affiliation:
Dept. Chem. Eng., Universitat Politècnica de Catalunya, 08028 Barcelona, Spain.
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Abstract

We have carried out an experimental comparison study of the dissolution rates of unirradiated UO2 and SIMFUEL pellets and particles (100–300 μm) in a standard NaCI/NaHC03 solution, under oxidizing conditions. We have performed the experiments using batch and flow methodologies. Both methodologies gave similar results, indicating that the overall oxidation/dissolution process is the same in both cases. The results from the experiments indicate that under these conditions the dissolution process is both oxygen and bicarbonate promoted. The dissolution rates we obtained are: R=2.4 ± 0.8 mg U/m2 d for U02 and R= 0.17 ± 0.05 mg U/m2 d for SIMFUEL. The results of the experiments indicate that the dissolution rate under oxic conditions is clearly dependent on the number of U(VI) surface sites which for spent nuclear fuel is a function of the extent of radiolytic oxidation.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 353: Symposium – Scientific Basis for Nuclear Waste Management XVIII , 1994 , 601
Copyright
Copyright © Materials Research Society 1995

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References

REFERENCES

1. SKB Technical Report 92–02, Final Disposal of Spent Fuel. Importance of Bedrock for Safety (1992).Google Scholar
2. Bruno, J., Casas, I. and Sandino, A., J. Nucl. Mater. 190, 61 (1992).Google Scholar
3. Gray, W.J., Leider, H.R. and Steward, S.A., J. Nucl. Mater. 190, 46 (1992).Google Scholar
4. Casas, I., Gimenez, J., Marti, V., Torrero, M.E. and de Pablo, J., Radiochim. Acta (1994) in pressGoogle Scholar
5. Shoesmith, D.W., Sunder, S., Bailey, M.G. and Wallace, G.J., Corrosion Sci. 29, 1115 (1989).Google Scholar
6. Schrire, D., in SKB Technical Note NF(P) 91–15: SIMFUEL: Physical and Chemical Microstructure (1991).Google Scholar
7. Casas, I., Gimenez, J., Marti, V., Torrero, M.E. and de Pablo, J., in Scientific Basis for Nuclear Waste Management XVI, edited by Interrante, Ch.G. and Pabalan, R.T. (Mater. Res. Soc. Symp. Proc. 294, Pittsburgh, PA 1993) pp 61–66.Google Scholar
8. Bruno, J., Casas, I. and Puigdomenech, I., Geochim. Cosmochim. Acta, 55, 647 (1991).Google Scholar
9. Robbins, J.C., Can. Inst. Min. Metall. Bull. 71, 61 (1978).Google Scholar
10. Gray, W.J., Steward, S.A., Tait, J.C. and Shoesmith, D.W., in High Level Radioactive Waste Management. Proceedings of The Fith International Conference, (American Nuclear Society 1994) pp. 2597–2601.Google Scholar
11. Matzke, Hj., J. Nucl. Mater. 190, 101 (1992).Google Scholar
12. Forsyth, R.S. and Werme, L.O., J. Nucl. Mater. 190, 3 (1992).Google Scholar
13. Gray, W.J., Thomas, L.E. and Einziger, R.E., in Scientific Basis for Nuclear Waste Management XVI, edited by Interrante, Ch.G. and Pabalan, R.T. (Mater. Res. Soc. Symp. Proc. 294, Pittsburgh, PA 1993) pp 47–54.Google Scholar
14. Gray, W.J. and Thomas, L.E., in High Level Radioactive Waste Management, Proceedings of The Third International Conference, (American Nuclear Society 1992) pp. 1458–1464.Google Scholar
15. Grambow, B., Loida, A., Dressier, R., Friese, K., Geckeis, H., Muller, N., Schweigel, B., Reger, R., Diaz Arocas, P., Gago, J., Casas, I., de Pablo, J., Gimenez, J. and Torrero, M.E., in KFK Annual Report 1993, Contract No. F12W–CT90–0055: Chemistry of the Reation of Fabricated and High Burnup UO2 Fuel in Saline Brines (1993).Google Scholar