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Leaching of Cesium and Uranium from Spent PWR fuel in the Gel-state Clays

Published online by Cambridge University Press:  21 March 2011

S. S. Kim ,
K. S. Chun ,
J. W. Choi ,
W. J. Cho  and
P. S. Hahn
S. S. Kim
Affiliation:
Radwaste Disposal Research Division, Korea Atomic Energy Research Institute, P.O. Box 105, Yuseong, Deajeon, Republic of Korea
K. S. Chun
Affiliation:
Radwaste Disposal Research Division, Korea Atomic Energy Research Institute, P.O. Box 105, Yuseong, Deajeon, Republic of Korea
J. W. Choi
Affiliation:
Radwaste Disposal Research Division, Korea Atomic Energy Research Institute, P.O. Box 105, Yuseong, Deajeon, Republic of Korea
W. J. Cho
Affiliation:
Radwaste Disposal Research Division, Korea Atomic Energy Research Institute, P.O. Box 105, Yuseong, Deajeon, Republic of Korea
P. S. Hahn
Affiliation:
Radwaste Disposal Research Division, Korea Atomic Energy Research Institute, P.O. Box 105, Yuseong, Deajeon, Republic of Korea
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Abstract

The amounts of cesium and uranium released from crushed spent PWR fuel in the gel-state clays with a few ml of supernatant at hot cell temperature under Ar-atmosphere have been measured. The fractions of cesium dissolved from the fuel for 873 days were 0.29 and 0.25% in Boom clay/Boom-clay water and Ca-bentonite/synthetic granitic groundwater, respectively. These cesium fractions were very close to the gap inventory of cesium, which was determined to be around 0.30% in the previous experiment. The fraction of uranium released up to 193 days in the Boom clay media was 0.011% and this fraction has been retained until 873 days. Such this phenomenon was also obtained in the Ca-bentonite media even though the released fraction was higher than that in Boom clay. The increase of less than 0.001% in the dissolved uranium fraction between 193 and 873 days suggests that the long-term leach rate of uranium from spent fuel would be much less than 24 μg·m−2·day−1.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 932: Symposium – Scientific Basis for Nuclear Waste Management XXIX , 2006 , 67.1
Copyright
Copyright © Materials Research Society 2006

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