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Leaching of Spent Fuel and Simulated Fuel in the Presence of Environmental Materials: Integral Experiments

Published online by Cambridge University Press:  10 February 2011

K. Le Lous ,
S. Constantin ,
J.L. Paul ,
D. Sambugaro  and
E. Vernaz
K. Le Lous
Affiliation:
Commissariat à l'Énergie Atomique, Rhöne Valley Research Centre, Marcoule, BP 171, F-30207 Bagnols-sur-Cèze Cedex, France
S. Constantin
Affiliation:
Commissariat à l'Énergie Atomique, Rhöne Valley Research Centre, Marcoule, BP 171, F-30207 Bagnols-sur-Cèze Cedex, France
J.L. Paul
Affiliation:
Commissariat à l'Énergie Atomique, Rhöne Valley Research Centre, Marcoule, BP 171, F-30207 Bagnols-sur-Cèze Cedex, France
D. Sambugaro
Affiliation:
Commissariat à l'Énergie Atomique, Rhöne Valley Research Centre, Marcoule, BP 171, F-30207 Bagnols-sur-Cèze Cedex, France
E. Vernaz
Affiliation:
Commissariat à l'Énergie Atomique, Rhöne Valley Research Centre, Marcoule, BP 171, F-30207 Bagnols-sur-Cèze Cedex, France
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Abstract

We have designed an apparatus which simulates the conditions of a deep geological repository in order to study the behaviour of spent fuel under leaching. A spent fuel and a Simfuel have thus been leached by synthesized clayey or granitic groundwater in sandy clay (90 % sand) or granite, in reducing conditions, at 90°C and 40 bars.

The apparent leach rate for spent fuel in clayey water is 3.33 µg.m−2.dr−1 in the presence of clay and 3.37 µg.m-−2.d−1 in the presence of granite. The apparent leach rate in granitic water is slower, being 0.37 µg.m−2d−1 in the presence of clay and 0.74 µg.m−2d−1 in the presence of granite.

For Simfuel, the apparent leach rate in clayey water is 7.4 µg.m−2.d−1 in the presence of clay and 1. 1 µg.m−2.d−1 in the presence of granite, which is the same order of magnitude as that for spent fuel. In granitic water, the apparent leach rate is 20 to 40 times greater than that for spent fuel. It is 14.8 µg.m−2.d−1 in the presence of clay and 18.5 µg.m−2.d−1 in the presence of granite.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 506: Symposium – Scientific Basis for Nuclear Waste Management XXI , 1997 , 191
Copyright
Copyright © Materials Research Society 1998

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References

REFERENCES

1 Neal, W.L., Rawson, S.A. and Murphy, W.M., Mat. Res. Soc. Symp. Proc. 112 (1988) 505–515 Google Scholar
2 Rawson, S.A., Neal, W.J. and Burnell, J.R., Mat. Res. Soc. Symp. Proc. 112 (1988) 453–463 Google Scholar
3 Uziemblo, N.H., Thomas, L.E., Schoenlein, L.H., Mastel, B. and Jenson, E.D., Mat. Res. Soc. Symp. Proc. 84 (1987) 161–171 Google Scholar
4 Brunell, J.R., Coles, D.G. and Thomas, L.E., Geological Society of America, Abstracts 17 (1985) 361–371 Google Scholar
5 Glatz, J.P., Toscano, E.H., Pagliosa, G. and Nicholl, A., J. Nucl. Mater. 223 (1995) 84–89 Google Scholar
6 Tait, J.C., Stroes-Gascoyne, S., Porth, R.J., Wood, D. and Heimann, R.B., Mat. Res. Soc. Symp. Proc. 127 (1989) 309–315 Google Scholar
7 Heimann, R.B., Mat. Res. Soc. Symp. Proc. 84 (1987) 409–420 Google Scholar
8 Heimann, R.B., Cement and Concrete research 18 (1988) 389–400 Google Scholar
9 Heimann, R.B., Canadian Nuclear Society, 2nd International Conference on Radioactive Waste Management (1986) 408–414 Google Scholar
10 Forsyth, R.S., Werme, L.O. and Bruno, J., J. Nucl. Mater 160 (1988) 218–223 Google Scholar
11 Albinsson, Y., Forsyth, R.S., Skårnemark, G., Skglberg, M., Torstenfelt, B. and Werme, L.O., Mat. Res. Soc. Symp. Proc. 176 (1990) 559–565 Google Scholar
12 Ramebdck, H., Albinsson, Y.; Skflberg, M. and Werme, L.O., Radiochimica Acta 66/67 (1994) 405–408 Google Scholar
13 Rondinella, V.V. and Matzke, Hj., J. Nucl. Mater 238 (1996) 44–57 Google Scholar
14 Schrire, D., SKB Technical Note NF(P)-91-15 (March 1991)Google Scholar
15 Shoesmith, D.W. and Sunder, S., SKB Technical Report 91-63 (December 1991)Google Scholar
16 Grambow, B., Lo'da, A., Dressler, P., Geckeis, H., Gago, J., Casas, I., De, J. Pablo, Gimenez, J. and Torrero, M.E., Final Report FZKA 5702 (March 1996)Google Scholar
17 Lolda, A., Grambow, B. and Geckeis, G., J. Nucl. Mater. 238 (1996) 11–22 Google Scholar