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The Effect of Nearfield Constraints on the Corrosion Behavior of High Burnup Spent Fuel

Published online by Cambridge University Press:  21 March 2011

Andreas Loida ,
Manfred Kelm ,
Bernhard Kienzler ,
Horst Geckeis  and
Andreas Bauer
Andreas Loida
Affiliation:
Forschungszentrum Karlsruhe, Institut für Nukleare Entsorgung, P.O.Box 3640, D-76021 Karlsruhe, Germany
Manfred Kelm
Affiliation:
Forschungszentrum Karlsruhe, Institut für Nukleare Entsorgung, P.O.Box 3640, D-76021 Karlsruhe, Germany
Bernhard Kienzler
Affiliation:
Forschungszentrum Karlsruhe, Institut für Nukleare Entsorgung, P.O.Box 3640, D-76021 Karlsruhe, Germany
Horst Geckeis
Affiliation:
Forschungszentrum Karlsruhe, Institut für Nukleare Entsorgung, P.O.Box 3640, D-76021 Karlsruhe, Germany
Andreas Bauer
Affiliation:
Forschungszentrum Karlsruhe, Institut für Nukleare Entsorgung, P.O.Box 3640, D-76021 Karlsruhe, Germany
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Abstract

The long-term immobilization for individual radioelements released from the waste form “spent fuel” in solid phases upon groundwater contact depends strongly on the (geo)chemical constraints prevailing in the repository. Related experimental studies comprise effects induced by the presence of Fe based container material, and near field materials other than Fe for a rock salt environment. The effect of the presence of an argillaceous host rock containing organic matter and pyrite on fuel alteration was studied in addition. The results have shown that oxidative radio-lysis products were found to be consumed at a significant extent by the metallic Fe and by the argillaceous host rock. Under these conditions a decrease at a factor of ca.100 for both the matrix dissolution rates and the solution concentrations of U and Pu was found. There is mutual support between the matrix dissolution rates, the solution concentrations and the amounts of oxygen encountered during the experiments under various conditions controlled by the presence of near field materials under study.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 932: Symposium – Scientific Basis for Nuclear Waste Management XXIX , 2006 , 72.1
Copyright
Copyright © Materials Research Society 2006

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References

REFERENCES

1. Loida, A., Metz, V., Kienzler, B., Geckeis, H., Radionuclide release from high burnup spent fuel during corrosion in salt brine in the presence of hydrogen overpressure, Journal of Nuclear Materials 346 (2005) 24–31 Google Scholar
2. Loida, A., Kienzler, B., Geckeis, H., Mobilization/Retention of Radionuclides during Corrosion of High Burnup Spent Fuel and Backfill Materials in Salt Brines, Mater. Res. Soc. Proc. 757 (2003) S.II8.2/1–7 Google Scholar
3. Schäfer, T., Claret, F., Bauer, A., Griffault, E., Ferrage, E., Lanson, B., Natural organic matter clay association and impact on Callovo-Oxfordian clay stability in high alkaline solution, J. Phys.IV France 104 (2003), 413–416 Google Scholar
4. Claret, F., Bauer, A., Schäfer, T., Griffault, L., Lanson, B., Experimental Investigation of the interaction of clays with high pH solutions: a case study from the Callovo-Oxfordian forma tion, Meuse-Haute Marne underground laboratory (France), Clays and Clay Minerals, 50 No 5, 633–646, 2002 Google Scholar
5. Grambow, B., Loida, A., Dressler, P., Geckeis, H., J.Gago, I. Casas, I., Pablo, J. de, Gimenez, J., J., , Torrero, M.E., “Long-term safety of radioactive waste disposal: Chemical reac tion of fabricated and high burnup spent fuel with saline brines”, FZKA 5702 (1996)Google Scholar
6. Grambow, B., Müller, R., Mater. Res. Soc. Proc., Chemistry of Glass Corrosion in High Saline Brines, Mater. Res. Soc. Symp.Proc. 176 (1990) 229–241 Google Scholar
7. Grambow, B., Werme, L., Forsyth, R., Bruno, J., Constraints by experimental data for modeling of radionuclide release from spent fuel, Mater. Res. Soc. Proc 176, 1990, 465–474 Google Scholar
8. Loida, A., Kienzler, B., Geckeis, H., Corrosion Behavior of Pre-oxidized High Burnup Spent Fuel in Salt Brine, Mat. Res. Soc. Symp. Proc. 807 (2004) 53–59 Google Scholar