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Experimental Study of Colloid Filtration by Compacted Bentonite

Published online by Cambridge University Press:  03 September 2012

Susumu Kurosawa ,
Mikazu Yui  and
Hideki Yoshikawa
Susumu Kurosawa
Affiliation:
Naka Energy Research Center, Mitsubishi Materials Corporation, 1002–14 Mukouyama, Naka-machi, Naka-gun, Ibaraki-ken, 311–01, Japan
Mikazu Yui
Affiliation:
Power Reactor and Nuclear Fuel Development Corporation, 4–33 Muramatsu, Tokai-mura, Naka-gun, Ibaraki-ken, 319–11, Japan
Hideki Yoshikawa
Affiliation:
Power Reactor and Nuclear Fuel Development Corporation, 4–33 Muramatsu, Tokai-mura, Naka-gun, Ibaraki-ken, 319–11, Japan
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Abstract

In this study, the transport behavior of colloids through compacted bentonite and sand-bentonite mixtures was investigated. Colloidal gold was used to simulate mobile colloids because it was well characterized and its dispersivity was controlled. The bentonite used was a sodium bentonite. The sand-bentonite mixtures were prepared by mixing up to 50wt.% silica sand with the bentonite. The bentonite and the sand-bentonite mixtures were compacted to dry densities of 1000 and 1800 kg/m3 and then saturated with distilled water. The sand-bentonite mixture was also saturated with synthetic sea-water. Column experiments were performed to investigate colloidal transport. Further, colloidal particles stabilities in high ionic strength water such as bentonite porewater or saline groundwater were interpreted based on the repulsion potential from the double layer force and the attraction potential from the van der Waals force.

The results indicated that the colloidal particles were effectively filtered by both the compacted bentonite and the sand-bentonite mixtures. This study indicated that the effect of colloids on radionuclide transport in compacted bentonite is negligible for the safety assessment of high level radioactive waste (HLW) disposal.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 465: Symposium II – Scienfific Basis for Nuclear Waste Management XX , 1996 , 963
Copyright
Copyright © Materials Research Society 1997

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References

REFERENCES

1. Sato, H., Yui, M. and Yoshikawa, H., in Scientific Basis for Nuclear Waste Management XVIII. edited by Takahashi, M. and Rodney, C. E. (Mater. Res. Soc. Symp. Proc. 353, Kyoto, 1994), pp269–276.Google Scholar
2. Kim, J. I., Buckau, G., Klenze, R., Rhee, D. S. and Wimmer, H., CEC Report EUR 13181, 41 (1991).Google Scholar
3. Ogino, K., Ohta, M. and Matsui, J., 18th Int. I.F.S.C.C. Cong., (Venezia, 1994), pp. 272–284.Google Scholar
4. Kurosawa, S., Yoshikawa, H. and Yui, M., Radioactive Waste Research 1 (2), 177(1995)(in Japanese).Google Scholar
5. Nakano, M., Amemiyaand, Y., Fujii, K., Trans. JSIDRE 100, 8 (1982)(in Japanese with English abstract, figures and tables).Google Scholar
6. Ishikawa, H., Amemiya, K., Yusa, Y. and Sasaki, N., Int. Clay Conf. Proc. 9, (Strasbourg, 1989).Google Scholar
7. Kruyt, H. R., Colloid Science, 1st ed. (Elsevier Publishers, New York, 1952), p. 271.Google Scholar