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Reactive Transport Modeling of Radionuclide Source-Terms in an Underground Spent Fuel Disposal

Published online by Cambridge University Press:  01 February 2011

L. De Windt
Affiliation:
Centre for Geological Computer Sciences, Paris School of Mines, rue Saint-Honoré 35, 77305 Fontainebleau, France
H. Catalette
Affiliation:
Electricité de France, Research and Development Division, Les Renardières, 77818 Moret sur Loing, France.
J. M. Gras
Affiliation:
Electricité de France, Research and Development Division, Les Renardières, 77818 Moret sur Loing, France.
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Abstract

The reactive transport model HYTEC was used to simulate the migration over 100,000 years of cesium, americium and uranium released from spent fuel packages in the near-field components of an underground stiff clay disposal site. A global equilibrium thermodynamic approach including kinetic control of the spent fuel pellets was used with instantaneous release fractions and congruent dissolutions of the rim and the core zones. A failure scenario of the waste package after 10,000 years was considered with magnetite as the main corrosion product. The retention properties of magnetite and the different effects of bentonite and cementitious backfill materials were specifically analysed.

Type
Research Article
Copyright
Copyright © Materials Research Society 2004

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References

1. De Windt, L., Cabrera, J. and Boisson, J.-Y., “Radioactive Waste Containment in Indurated Claystones: Comparison between the Chemical Containment Properties of Matrix and Fractures”, Geological Society of London 157, 167181 (1999).CrossRefGoogle Scholar
2. van der Lee, J., De Windt, L., Lagneau, V. and Goblet, P., “Module-oriented modeling of reactive transport with HYTEC”, Comp. Geosc. 29, 265275 (2003).CrossRefGoogle Scholar
3. Röllin, S., Spahiu, K., and Eklund, U.B.. “Determination of dissolution rates of spent fuel in carbonate solutions under different redox conditions with a flow-through experiment”, J. Nucl. Mat. 297(3), 231243 (2001).CrossRefGoogle Scholar
4. Pellegrini, D. and De Windt, L., “Assessment of Geochemical Containment Properties in the Near-field of a Deep Underground Repository”, Scient. Basis Nucl. Waste Manag., Boston, US (Dec. 2002).Google Scholar
5. Shoesmith, D.W., “Fuel corrosion processes under waste disposal conditions”, J. Nucl. Mat. 282, 131 (2000).CrossRefGoogle Scholar
6. Berner, U., “Concentration limits in the cement based Swiss repository for long-lived, intermediate-level radioactive wastes (LMA)”, Techn. rep. 99–10, PSI (1999).Google Scholar

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Reactive Transport Modeling of Radionuclide Source-Terms in an Underground Spent Fuel Disposal
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