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Leaching of Used Candu™ Fuel in the Presence of Clay, Titanium and Granite Rock

Published online by Cambridge University Press:  26 February 2011

John C. Tait ,
Simcha Stroes-Gascoyne ,
Robert J. Porth ,
Don Wood  and
Robert B. Heimann
John C. Tait
Affiliation:
Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment, Pinawa, Manitoba, Canada, ROE ILO
Simcha Stroes-Gascoyne
Affiliation:
Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment, Pinawa, Manitoba, Canada, ROE ILO
Robert J. Porth
Affiliation:
Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment, Pinawa, Manitoba, Canada, ROE ILO
Don Wood
Affiliation:
Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment, Pinawa, Manitoba, Canada, ROE ILO
Robert B. Heimann
Affiliation:
Alberta Research Council, 250 Karl Clark Road, Edmonton, Alberta, Canada, T6H 5X2
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Abstract

Dissolution experiments have been performed at 95 or 100°C on used fuel in the presence of various components of a disposal system: granite rock, clay (Na-montmorillonite, illite), container (titanium), and two groundwaters with different ionic strengths (0.0015, 0.28). The results showed that Cs and Sr release to solution is highest in the high-ionic-strength groundwater and that clay type is less important in determining short-term release from the fuel. It also appears that after an initial release period lasting about 10 to 20 days, radionuclide release from the fuel to solution slows considerably. Cs was found to sorb more effectively than Sr on illite and montmoril-lonite, while Sr sorbed more effectively than Cs on the granite.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 127: Symposium BERLIN – Scientific Basis for Nuclear Waste Management XII , 1988 , 309
Copyright
Copyright © Materials Research Society 1989

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References

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