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Leaching Behavior of Unirradiated High Temperature Reactor (HTR) UO2-ThO2 Mixed Oxides Fuel Particles

Published online by Cambridge University Press:  01 February 2011

Catherine Landesman ,
Sandra Delaunay  and
Bernd Grambow
Catherine Landesman
Affiliation:
Laboratoire Subatech, UMR 6457, F-44307 Nantes Cedex 03, France
Sandra Delaunay
Affiliation:
Laboratoire Subatech, UMR 6457, F-44307 Nantes Cedex 03, France
Bernd Grambow
Affiliation:
Laboratoire Subatech, UMR 6457, F-44307 Nantes Cedex 03, France
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Abstract

The dissolution rate of small UO2, ThO2 and mixed UO2–ThO2 particles, representative of unirradiated HTR fuel, are investigated in the pH range 1.7 to 5.5 under oxic conditions. For UO2 particles, the dissolution is kinetically control while for ThO2 particles, a solubility control mechanism seems to prevail for pH > 2. In the mixed oxides UO2–ThO2 particles, a selective release of uranium is observed, which could be either the result of a dissolution/precipitation mechanism in which thorium reprecipitate as oxide or hydroxide phase, or a result of a higher accessible surface area. Under oxic conditions, uranium may be considered as a tracer for the other soluble elements. So, assuming constant conditions with time, one can estimate from these preliminary results that unirradiated thorium based fuel kernels seem to present intrinsic confinement properties for 15000 years relative to soluble elements.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 807: Symposium Scientific Basis for Nuclear Waste Management XXVII , 2003 , 95
Copyright
Copyright © Materials Research Society 2004

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References

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