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Migration of Plutonium in a Simulated Engineered Barrier System Consisting of Waste Glass and Ompacted Bentonite

Published online by Cambridge University Press:  10 February 2011

Y. Inagaki
Affiliation:
Kyushu Univ., Dept. of Nucl. Eng., Fukuoka 812–8581, Japan
R. Saito
Affiliation:
Kyushu Univ., Dept. of Nucl. Eng., Fukuoka 812–8581, Japan
H. Furuya
Affiliation:
Kyushu Univ., Dept. of Nucl. Eng., Fukuoka 812–8581, Japan
K. Idemitsu
Affiliation:
Kyushu Univ., Dept. of Nucl. Eng., Fukuoka 812–8581, Japan
T. Arima
Affiliation:
Kyushu Univ., Dept. of Nucl. Eng., Fukuoka 812–8581, Japan
T. Banba
Affiliation:
Japan Atomic Energy Research Institute, Tokai Research Establish., Ibaraki 319–1195, Japan
T. Maeda
Affiliation:
Japan Atomic Energy Research Institute, Tokai Research Establish., Ibaraki 319–1195, Japan
S. Matsumoto
Affiliation:
Japan Atomic Energy Research Institute, Tokai Research Establish., Ibaraki 319–1195, Japan
Y. Tamura
Affiliation:
Japan Atomic Energy Research Institute, Tokai Research Establish., Ibaraki 319–1195, Japan
S. Kikkawa
Affiliation:
Japan Atomic Energy Research Institute, Tokai Research Establish., Ibaraki 319–1195, Japan
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Abstract

In a simulated engineered barrier system consisting of a simulated HLW glass doped with Pu, a compacted bentonite and water under reducing conditions, migration tests of Pu from the glass into the bentonite through water were performed. The following results were obtained: (1) The presence of bentonite enhances the glass dissolution while it has no remarkable influence on the concentration of Pu dissolved species in the solution. (2) Only a small part of the leached Pu, which may correspond to the dissolved species, can diffuse into the bentonite with the apparent diffusion coefficient of 3×10−14m2/s. (3) Interactions between the glass and the bentonite have no remarkable influence on the diffusion of Pu.

Type
Research Article
Copyright
Copyright © Materials Research Society 1999

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References

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