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Diffusion of Uranium in Compacted Sodium Bentonite

Published online by Cambridge University Press:  01 January 1992

Arto Muurinen ,
Kaija Ollila  and
Jarmo Lehikoinen
Arto Muurinen
Affiliation:
Technical Research Centre of Finland, Reactor Laboratory, P.O. Box 200, SF-02151 Espoo, Finland
Kaija Ollila
Affiliation:
Technical Research Centre of Finland, Reactor Laboratory, P.O. Box 200, SF-02151 Espoo, Finland
Jarmo Lehikoinen
Affiliation:
Technical Research Centre of Finland, Reactor Laboratory, P.O. Box 200, SF-02151 Espoo, Finland
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Abstract

In this study the diffusion of uranium dissolved from uranium oxide fuel was studied experimentally in compacted sodium bentonite (Wyoming bentonite MX-80). The parameters varied in the study were the density of bentonite, the salt content of the solution and the redox conditions. In the studies with non-saline water of total dissolved solids about 300 ppm, uranium was both in aerobic and anaerobic experiments as anionic complexes and followed the anionic diffusion mechanism. Anion exclusion decreased effective diffusion coefficients, especially in more dense samples. In the studies with saline water of total dissolves solids about 35000 ppm, uranium appeared in the aerobic experiments probably as cationic complexes and followed the cationic diffusion mechanism. Uranium in the saline, anaerobic experiment was probably U(OH)4 and followed the diffusion mechanism of neutral species.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 294: Symposium V – Scientific Basis for Nuclear Waste Management XVI , 1992 , 409
Copyright
Copyright © Materials Research Society 1993

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References

REFERENCES

1. Muurinen, Arto, Penttili-Hiltunen, Pirkko and Uusheimo, Kari, in Scntific Basis for Nuclear Waste Management XII edited by Lutze, W. and Ewing, R. C. (Mat. Res. Soc. Proc. 127, Pittsburgh, PA, 1989), pp.743-748.Google Scholar
2 Muurinen, Arto, Transport processes in the buffer and backfill of spent fuel disposal. Data for TVO-92 safety analysis. Nuclear Waste Commission of Finnish Power Companies, Technical Report YJT-92-09, Helsinki, 1992.Google Scholar
3 Muurinen, Arto, Lehikoinen, Jarmo, Diffusion of uranium in compacted bentonite. Nuclear Waste Commission of Finnish Power Companies, Technical Report YJT-92-13, Helsinki, 1992.Google Scholar
4 Wolery, T.J., Calculation of chemical equilibrium between aqueous solution and minerals, the EQ3/6 software package. UCRL-52658, 1979.Google Scholar
5 Wolery, T.J. and Daveler, S.A., EQ6 - A computer Program for Reaction Path Modeling of Aqueous Geochemical Systems: Users Guide and Documentation. Lawrence Livemore National Laboratory, University of California, California, 1989.Google Scholar
6 Seeley, F.G., Kelmers, A.D., Scott, M.A., Uranium(VI) sorption ratios for standard clays, clay-rich soils and fly ashes. Paper presented at the International Symposium on Geochemical Behavior of Disposed Radioactive Waste, American Chemical Society Meeting, Seattle, Washington, 1983.Google Scholar
7 Torstenfelt, B., Allard, B., Andersson, K., Kipatsi, H., Eliasson, L., Olofsson, U., Persson, H., Radionuclide diffusion and mobilities in compacted bentonite. SKB Technical Report 83-34, Stockholm, 1983.Google Scholar
8 Muurinen, Arto, Penttilii-Hiltunen, Pirkko and Rantanen, Juha, in Scientific Basis for Nuclear Waste Management X, edited by Bates, John K. and Seefeldt, Waldemar B. (Mat. Res. Soc. Proc. 84, Pittsburgh, PA, 1986), pp. 803–812.Google Scholar