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Further Developments of the Reductive Capacity Model for Spent Fuel Stability: Application to Minor Radionuclides

Published online by Cambridge University Press:  10 February 2011

J. Bruno ,
E. Cera ,
L. Duro ,
K. Spahiu ,
T. Eriksen ,
U-B. Eklund  and
L.O. Werme
J. Bruno
Affiliation:
QuantiSci, Parc Tecnològic del Vallés, 08290 Cerdanyola (Spain). [email protected]
E. Cera
Affiliation:
QuantiSci, Parc Tecnològic del Vallés, 08290 Cerdanyola (Spain)
L. Duro
Affiliation:
QuantiSci, Parc Tecnològic del Vallés, 08290 Cerdanyola (Spain)
K. Spahiu
Affiliation:
Swedish Nuclear Fuel and Waste Management (SKB), Box 5864, S 102 48, Stockholm (Sweden)
T. Eriksen
Affiliation:
Dept. of Nuclear Chemistry, Royal Institute of Technology, S 100 44, Stockholm (Sweden)
U-B. Eklund
Affiliation:
Studsvik Nuclear AB S-611 82 Nykcping (Sweden)
L.O. Werme
Affiliation:
Swedish Nuclear Fuel and Waste Management (SKB), Box 5864, S 102 48, Stockholm (Sweden)
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Abstract

A reductive capacity (RDC) kinetic model previously developed for the radiolitically induced oxidative dissolution of the spent fuel matrix has been applied to critical minor radionuclides present in spent fuel [1]. The model has been tested in front of experimental results from spent fuel corrosion obtained within the SKB programme. The experimental procedure is detailed in a previous publication [2]. The RDC model considers

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 506: Symposium – Scientific Basis for Nuclear Waste Management XXI , 1997 , 1021
Copyright
Copyright © Materials Research Society 1998

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References

REFERENCES

1 Bruno, J., Cera, E., Duro, L., Eriksen, T.E. and Werme, L.O.. J. Nucl. Mater. 238, 1 (1996)Google Scholar
2 Forsyth, R.S. and Werme, L.O.. J. Nucl. Mater. 189, 3 (1992)Google Scholar