Hostname: page-component-586b7cd67f-rcrh6 Total loading time: 0 Render date: 2024-11-29T07:29:28.721Z Has data issue: false hasContentIssue false

Diffusion of Uranium in Compacted Bentonite in the Presence of Carbon Steel

Published online by Cambridge University Press:  25 February 2011

K. Idemitsu
Affiliation:
Kyushu University, Department of Nuclear Engineering, 6-10-1 Hakozaki, Fukuoka 812, JAPAN.
H. Furuya
Affiliation:
Kyushu University, Department of Nuclear Engineering, 6-10-1 Hakozaki, Fukuoka 812, JAPAN.
Y. Tachi
Affiliation:
Kyushu University, Department of Nuclear Engineering, 6-10-1 Hakozaki, Fukuoka 812, JAPAN.
Y. Inagaki
Affiliation:
Kyushu University, Department of Nuclear Engineering, 6-10-1 Hakozaki, Fukuoka 812, JAPAN.
Get access

Abstract

In a high-level waste repository, a carbon steel overpack will be corroded by consuming oxygen trapped in the repository after closure. This will create a reducing environment in the vicinity of repository. Reducing conditions are expected to retard the migration of redox-sensitive radionuclides such as uranium.

The apparent diffusivities of uranium were measured in compacted bentonite (Kunigel VI®, Japan) in contact with carbon steel under reducing conditions or without carbon steel under oxidizing conditions for comparison. The apparent diffusivities of uranium were 3.5 × 10-14 to 1.1 × 10-13 m2/s under reducing conditions and 9.0 × 10-13 to 1.4 × 10-12 m2/s under oxidizing conditions. There was no significant effect of dry density (1.6 to 1.8 g/cm3) and silica sand (0 or 40%) on the apparent diffusivities.

Since the bentonite pore water would be buffered at a pH between 8 and 9, uranium in the bentonite pore water would probably exist as a neutral hydroxide complex under reducing conditions and as an anioníc carbonate or hydroxide complex under oxidizing conditions. The anion exclusion theory cannot explain the difference of diffusivities between the two conditions. The uranium concentrations in bentonite under oxidizing conditions were one order of magnitude higher than those under the reducing conditions. The uranium concentration in the bentonite pore water under the reducing condition is estimated to be two orders of magnitude lower than that under the oxidizing conditions under the assumption of diffusion in porous media.

Type
Research Article
Copyright
Copyright © Materials Research Society 1994

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 Trestenfelt, B., Kipatsi, H., Anderson, K., Allard, B. and Olofsson, U. in Scientific Basis for Nuclear Waste Management V, edited by Lutze, W. (Mater. Res. Soc. Proc. 11, New York, NY, 1982), pp.659668.Google Scholar
2 Muurinen, A., Penttila-Hiltunen, P. and Uusheimo, K. in Scientific Basis for Nuclear Waste Management XII, edited by Lutze, W. and Ewing, R.C. (Mater. Res. Soc. Proc. 127, Pittsburgh, PA, 1989), pp.743748.Google Scholar
3 Sato, H., Ashida, T., Kohara, Y. and Yui, M. in Scientific Basis for Nuclear Waste Management XVI, edited by Interrante, C.G. and Pabalan, R.T. (Mater. Res. Soc. Proc. 294, Pittsburgh, PA, 1993), pp.403408.Google Scholar
4 Crank, J., The Mathematics of Diffusion, 2nd ed. (Clarendon Press, Oxford, 1975), pp.1121.Google Scholar
5 Idemitsu, K., Furuya, H. and Inagaki, Y. in Scientific Basis for Nuclear Waste Management XVI, edited by Interrante, C.G. and Pabalan, R.T. (Mater. Res. Soc. Proc. 294, Pittsburgh, PA, 1993), pp.467474.Google Scholar
6 Grenthe, I., Fuger, J., Koning, R.J.M., Lemire, R.J., Muller, A.B., Nguyen-Trung, C. and Wanner, H., Chemical Thermodynamics of Uranium, edited by Wanner, H. and Forest, I. (North Holland, Amsterdam, 1992).Google Scholar
7 Miyahara, K., J. Nuclear Science and Technology 30 (4), 314 (1993).CrossRefGoogle Scholar
8 Sneliman, M., Uotila, H. and Rantanen, J. in Scientific Basis for Nuclear Waste Management X, edited by Bates, J.K. and Seefeldt, W.B. (Mater. Res. Soc. Proc. 84, Pittsburgh, PA, 1987), pp.781790.Google Scholar
9 Grambow, B., Hermansson, H.P., Bjoner, I.K. and Werme, L. in Scientific Basis for Nuclear Waste Management IX, edited by Werme, L.O. (Mater. Res. Soc. Proc. 50, Pittsburgh, PA, 1985), pp. 187202.Google Scholar
10 Wanner, H. in Scientific Basis for Nuclear Waste Management IX, edited by Werme, L.O. (Mater. Res. Soc. Proc. 50, Pittsburgh, PA, 1985), pp.509516.Google Scholar
11 Trestenfelt, B. and Allard, B. in Scientific Basis for Nuclear Waste Management VII, edited by McVay, G.L. (Mater. Res. Soc. Proc. 26, New York, NY, 1984), pp.789795.Google Scholar
12 Muurinen, A., Ollila, K. and Lehikoinen, J. in Scientific Basis for Nuclear Waste Management XVI, edited by Interrante, C.G. and Pabalan, R.T. (Mater. Res. Soc. Proc. 294, Pittsburgh, PA, 1993), pp.409416.Google Scholar