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Leaching/Migration of UO2-Fuel in Compacted Bentonite

Published online by Cambridge University Press:  21 February 2011

Y. Albinsson ,
R. Forsyth ,
G. Skarnemark ,
M. Skålberg ,
B. Torstenfelt  and
L. Werme
Y. Albinsson
Affiliation:
Department of Nuclear Chemistry, Chalmers University of Technology, S–412 96 Göteborg, Sweden
R. Forsyth
Affiliation:
Studsvik AB, S–611 82 Nyköping, Sweden
G. Skarnemark
Affiliation:
Department of Nuclear Chemistry, Chalmers University of Technology, S–412 96 Göteborg, Sweden
M. Skålberg
Affiliation:
Department of Nuclear Chemistry, Chalmers University of Technology, S–412 96 Göteborg, Sweden
B. Torstenfelt
Affiliation:
ABB-Atom, S–721 63 Västerås, Sweden
L. Werme
Affiliation:
Swedish Nuclear Fuel and Waste Management Co., Box 5864, S-102 48 Stockholm, Sweden
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Abstract

The release and migration of the fission products cesium, europium and technetium, the actinides plutonium, americium and curium, and the activation product cobalt from spent nuclear fuel pellets in highly compacted bentonite clay has been measured after contact times of 101 and 386 days. Experiments at longer contact times are in progress. In some cases small amounts (0.5–1%) of powdered copper or iron metal, or vivianite (Fe3(PO4)2) have been mixed with the bentonite clay.

The results indicate as expected a high mobility of cesium. The actinides have a very low mobility. After 386 days, plutonium has diffused less than 0.5 mm away from the fuel, while americium and curium appear to be somewhat more mobile. The behaviour of europium is similar to that of trivalent actinides. Very little technetium has been leached from all samples. Cobalt shows a strong retention in pure bentonite as well as in the presence of vivianite, while the mobility is much larger when iron or copper is added.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 176: Symposium U – Scientific Basis for Nuclear Waste Management XIII , 1989 , 559
Copyright
Copyright © Materials Research Society 1990

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References

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