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Migration Behavior of Ferrous Ions in Compacted Bentonite Under Reducing Conditions Using Electromigration

Published online by Cambridge University Press:  17 March 2011

Kazuya Idemitsu ,
Xiaobin Xia ,
Yoshiro Kikuchi ,
Yaohiro Inagaki  and
Tatsumi Arima
Kazuya Idemitsu
Affiliation:
Dept of Applied Quantum Physics and Nuclear Engineering, Kyushu Univ., Fukuoka, JAPAN, idemitsu@nucl.kyushu-u.ac.jp
Xiaobin Xia
Affiliation:
Dept of Applied Quantum Physics and Nuclear Engineering, Kyushu Univ., Fukuoka, JAPAN, idemitsu@nucl.kyushu-u.ac.jp
Yoshiro Kikuchi
Affiliation:
Dept of Applied Quantum Physics and Nuclear Engineering, Kyushu Univ., Fukuoka, JAPAN, idemitsu@nucl.kyushu-u.ac.jp
Yaohiro Inagaki
Affiliation:
Dept of Applied Quantum Physics and Nuclear Engineering, Kyushu Univ., Fukuoka, JAPAN, idemitsu@nucl.kyushu-u.ac.jp
Tatsumi Arima
Affiliation:
Dept of Applied Quantum Physics and Nuclear Engineering, Kyushu Univ., Fukuoka, JAPAN, idemitsu@nucl.kyushu-u.ac.jp
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Abstract

Carbon steel is one of the candidate overpack materials for high-level waste disposal and is expected to assure complete containment of vitrified waste glass during an initial period of 1000 years in Japan. The lifetime of the carbon steel overpack will depend on its corrosion rate. The corrosion rate of carbon steel is reduced by the presence of buffer material such as bentonite. Buffer material will delay the supply of corrosive materials and discharge of corrosion products through it. Carbon steeloverpack will be corroded by consuming oxygen introduced by repository construction after closure of repository and then will keep the reducing environment in the vicinity of repository. Therefore, it is important to study the migration of iron corrosion products through the buffer material because it may affect the corrosion rate of overpack, migration of redox-sensitive radionuclides, and the properties of the buffer material. Electromigration experiments have been carried out with source of iron ions supplied byanode corrosion of iron coupon in compacted bentonite. The carbon steel coupon was connected as the working electrode to the potentiostat and was held at a constant applied potential between - 200 to 1000 mV vs. Ag/AgCl electrode for 48 hours. Corrosion currents were 0.5 to 2mA initially and depended on the supplied electrical potential, then decreased to approximately 0.1 mA in a few hours. The final corrosion current was independent of supplied electrical potential. It is expected that iron ion could migrate as ferrous ion through interlayer of montmorillonite replacing exchangeable sodium ions in the interlayer. The rate-determining process of this experimental configuration could be infiltration rate of ferrousioninto bentonite. Infiltration rate of ferrous ion into bentonite was increasing with dry density of bentonite.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 824: Symposium CC – Scientific Basis for Nuclear Waste Management XXVIII , 2004 , CC8.47
Copyright
Copyright © Materials Research Society 2004

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References

1.JNC, H12:Project of Establish the Scientific and Technical Basis for HLW Disposal in JAPAN, (2000).Google Scholar
2. Honda, A., Teshima, T., Tsurudome, K., Ishikawa, H., Yusa, Y. and Sasaki, N. in Scientific Basis for Nuclear Waste Management XIV, edited by Abrajano, T. Jr . and Johnson, L.H. (Mater. Res. Soc. Proc. 212, Pittsburgh, PA, 1990) pp.287-294.Google Scholar
3. Osada, K., Nagano, T., Kozai, N., Nakashima, S., Nakayama, S. and Muraoka, S. in Proc. of The 3rd International Symposium on Advanced Nuclear Energy Research - Global Environment and Nuclear Energy (held in Mito Japan, 1991) pp.359-362.Google Scholar
4. Idemitsu, K., Furuya, H., Tachi, Y. and Inagaki, Y. in Scientific Basis for Nuclear Waste Management XVII, edited by Barkatt, A. and Konynenburg, R.A.Van (Mater. Res. Soc. Proc. 333, Pittsburgh, PA, 1994), pp.939-946.Google Scholar
5. Kuroda, Y., Idemitsu, K., Furuya, H., Inagaki, Y. and Arima, T. in Scientific Basis for Nuclear Waste Management XX, edited by Gray, W.J. and Triay, I.R. (Mater. Res. Soc. Proc. 465, Pittsburgh, PA, 1997), pp.909-916.Google Scholar
6. Albinsson, Y., Christiansen-Sätmark, B., Engkvist, I. and Johansson, W., Radiochimica Acta 52/53, pp.283–286,(1991).Google Scholar
7. Idemitsu, K., Yano, S., Xia, X., Kikuchi, Y., Inagaki, Y., T. Arima in Scientific Basis for Nuclear Waste Management XXVI, edited by , R. J.Finch and Bullen, D. B. (Mater. Res. Soc. Proc. 757, Pittsburgh, PA, 2003) pp.657-664.Google Scholar
8. Kozaki, K., Nuclear Technology 115, pp.3–69, (1998).Google Scholar
9. Taniguchi, N., Honda, A. and Ishikawa, H. in Scientific Basis forNuclear Waste Management XXI, edited by Mckinley, I. G. and McCombie, C.(Mater. Res. Soc. Proc. 506, Pittsburgh, PA, 1998), pp.495-501.Google Scholar
10. King, F., Litke, C.D. and Ryan, S.R., Corrosion Science 33(129), pp. 1979–1995, (1992).Google Scholar