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Alteration Behavior of High Burnup Spent Fuel in Salt Brine Under Hydrogen Overpressure and in Presence of Bromide

Published online by Cambridge University Press:  19 October 2011

Andreas Loida ,
Volker Metz  and
Bernhard Kienzler
Andreas Loida
Affiliation:
[email protected], Forschungszentrum Karlsruhe, Institut für Nukleare Entsorgung, P.O.Box 3640, Karlsruhe, D-76021, Germany, ++49 7247 824721, ++49 7247 823927
Volker Metz
Affiliation:
[email protected], Forschungszentrum Karlsruhe, Institut für Nukleare Entsorgung, P.O.Box 3640, Karlsruhe, D-76021, Germany
Bernhard Kienzler
Affiliation:
[email protected], Forschungszentrum Karlsruhe, Institut für Nukleare Entsorgung, P.O.Box 3640, Karlsruhe, D-76021, Germany
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Abstract

Recent studies have shown that in the presence of H2 overpressure, which forms due to the corrosion of the Fe based container, the dissolution rate of the spent fuel matrix is slowed down by a factor of about 10, associated with a distinct decrease of concentrations of important ra-dionuclides. However, in a natural salt environment as well as in geological formations with chloride rich groundwater the presence of radiation chemically active impurities such as bro-mide must be taken in consideration. Bromide is known to react with β/γ radiolysis products, thus counteracting the protective H2 effect. In the present experiments using high burnup spent fuel it is observed that during 212 days the matrix dissolution rate was enhanced by a factor of about10 in the presence of up to 10-3 M bromide and 3.2 bar H2 overpressure. However, concen-trations of matrix bound actinides were found at the same level or below as found under identical conditions, but in the absence of bromide. In the long-term it is expected that the effect of bro-mide becomes less important, because the decrease of β/γ-activity results in a decrease of oxida-tive radicals, which react with bromide, while α activity will dominate the radiation field.

Keywords

corrosionchemical reactionU
Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 985: Symposium NN – Scientific Basis for Nuclear Waste Management XXX , 2006 , 0985-NN01-02
Copyright
Copyright © Materials Research Society 2007

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References

REFERENCES

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