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Diffusion of Cs and Sr in Compacted Bentonites Under Reducing Conditions and in the Presence of Corrosion Products of Iron

Published online by Cambridge University Press:  10 February 2011

K. Idemitsu ,
Y Tachi ,
H. Furuya ,
Y. Inagaki  and
T. Arima
K. Idemitsu
Affiliation:
Department of Nuclear Engineering, Kyushu University, Fukuoka 812-8 1, JAPAN
Y Tachi
Affiliation:
Department of Nuclear Engineering, Kyushu University, Fukuoka 812-8 1, JAPAN
H. Furuya
Affiliation:
Department of Nuclear Engineering, Kyushu University, Fukuoka 812-8 1, JAPAN
Y. Inagaki
Affiliation:
Department of Nuclear Engineering, Kyushu University, Fukuoka 812-8 1, JAPAN
T. Arima
Affiliation:
Department of Nuclear Engineering, Kyushu University, Fukuoka 812-8 1, JAPAN
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Abstract

In high-level waste repositories, a carbon steel overpack will be corroded by consuming oxygen trapped in the repository after closure. Iron corrosion products are expected to interfere with migration of radionuclides by filling the pore in bentonite and sorbing radionuclides. In this study the apparent diffusion coefficients of cesium and strontium were measured in compacted Na-bentonites (Kunigel VI® and Kunipia F®, JAPAN) contacted with carbon steel and its corrosion products under reducing conditions or without carbon steel under oxidizing conditions for comparison. The apparent diffusion coefficients of cesium with and without corrosion product were 2.2 to 13 × 10−12 m2/s. The apparent diffusion coefficients of strontium with and without corrosion product were 3.1 to 25 × 10−12 m2/s. There were significant effects of dry density (0.8 to 2.0 g/cm3) and montmorillonite contents (50% for Kunigel V1 or 100% for Kunipia F). The presence of corrosion product decreased the apparent diffusion coefficients of Cs in both bentonites and that of Sr in Kunigel V1, especially at low dry density. This may be due to corrosion product filling the pore in the bentonite, decreasing the free pore size and density for diffusion.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 506: Symposium – Scientific Basis for Nuclear Waste Management XXI , 1997 , 351
Copyright
Copyright © Materials Research Society 1998

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References

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