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Coupling of Chemical Processes in the Near Field

Published online by Cambridge University Press:  21 March 2011

B. Grambow  and
E. Giffaut
B. Grambow
Affiliation:
SUBATECH, Nantes (France)
E. Giffaut
Affiliation:
Andra, Chatenay Malabry (France)
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Abstract

Coupled modelling has been performed using geochemical/transport codes and radiolysis models to describe the chemical evolution of the waste forms “high-level waste glass” and “spent nuclear fuel” together with its waste package and engineered barrier surroundings. Near field processes considered include container corrosion, hydrogen generation, mass transfer for radionuclides and other waste matrix components in corrosion products and buffer materials, geochemistry of near field solution chemistry, sorption of radionuclides on surface sites in the nano-sized pore space of near field materials and the radiolytic decomposition of pore water. The rate limiting steps in waste form dissolution and secondary phase formation mechanism and the associated radionuclide mobilisation chemistry (solubility, solid solution formation, speciation, redox stability) are strongly influenced by the near field constraints.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 932: Symposium – Scientific Basis for Nuclear Waste Management XXIX , 2006 , 119.1
Copyright
Copyright © Materials Research Society 2006

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References

REFERENCES

1. Vernaz, E. et al. , Present understanding of R7T7 glass alteration kinetics and their impact on long-term alteration modeling. J. Nucl. Mater., 2001. 298 p. 27–36.Google Scholar
2. Grambow, B. and Müller, R., First order dissolution rate law and the role of surface layers in glass performance assessment. J. Nucl. Mat., 2001. 298 p. 112–124.Google Scholar
3. Ribet, I. et al. , GLASTAB, Long-term behaviour of glass: improving the glass source term and substantiating the basic hypotheses, CONTRACT N°FIKW-CT-2000-00007, FINAL TECHNICAL REPORT. 2004.Google Scholar
4. Advocat, T. et al. , Effect of geological repository parameters on aqueous corrosion of nuclear waste glass. 1996, European Commission: Luxemburg.Google Scholar
5. Ribet, S. 2005: Nantes.Google Scholar
6. Parkhurst, D.L. and Appelo, C.A.J., USER'S GUIDE TO PHREEQC (VERSION 2)- A COMPUTER PROGRAM FOR SPECIATION, BATCH-REACTION, ONE-DIMENSIONAL TRANSPORT, AND INVERSE GEOCHEMICAL CALCULATIONS, in Water resources investigations report 99-4259. 1999, USGS: Denver, Colorado.Google Scholar
7. Van Iseghem, P. et al. GLASTAB and GLAMOR projects: Main Conclusions and Remaining Uncertainties. in this conference. 2005.Google Scholar
8. Ferrand, K. et al. Silica sorption on container corrosion products siderite and magnetite. in this conference. 2005.Google Scholar
9. Cachoir, C. et al. , Effect of alpha irradiation field on long-term corrosion rates of spent fuel. 2005, European Commission, Joint Research Center, ITU: Karlsruhe.Google Scholar
10. Spahiu, K., Cui, D., and Lundström, M., The fate of radiolytic oxidants during spent fuel dissolution in the presence of dissolved near field hydrogen. Radiochim. Acta, 2004. 92 p. 625–629.Google Scholar
11. Lundström, T., Radiation Chemistry of Aqueous Solutions Related to Nuclear Reactor Systems and Spent Fuel Management. 2003, Linköping Univerity: Linköping, Sweden.Google Scholar
12. Rother, A., Lutze, W., and Schubert-Bischoff, P., Characterization of lanthanoid phases formed upon glass dissolution in salt solutions. Mater. Res. Soc. Symp. Proc., 1992. 257 p. 57–64.Google Scholar
13. Grambow, B. et al. , Release of Rare Earth Elements and Uranium from Glass in Low pH High Saline Brines. Radiochimica Acta, 1991. 52/53: p. 501–506.Google Scholar
14. Sattonnay, G. et al. , Alpha-radiolysis effects on UO2 alteration in water. Journal of Nuclear Materials, 2001. 288 p. 11–19.Google Scholar
15. Diaz Arocas, P. et al. , Coprecipitation of mono-, di-, tri-, tetra- and hexavalent Ions with Na-polyuranates. Radiochimica Acta, 1996. 74 p. 51–58.Google Scholar
16. Rousseau, G., Coprécipitation de Th, Eu, La et Ac avec UO2 comme phase d'accueil., in Ecole Doctorale STIM. 2002, Université de Nantes: Nantes.Google Scholar
17. Bruno, J. and Sandino, A., The thermodynamics and kinetics of coprecipitation and its effect on radionuclide solubility. Radiochimica Acta, 1988. 44/45: p. 17–21.Google Scholar
18. Langmuir, D., Uranium Solution-Mineral Equilibria at low Temperatures with Applications to Sedimentary ore Deposits. Geochimica et Cosmochimica Acta, 1978. 42 p. 547–569.Google Scholar
19. Grenthe, I., Fuger, J., Konings, R.J.M., Lemire, R.J., Muller, A.B., Nguyen-Trung, C., Wanner, H., Chemical thermodynamics of uranium. North-Holland, Amsterdam, 1992: p. 0–0.Google Scholar
20. Robit, V. et al. Assessment of the relevance of coffinite formation within the nearfield environment of spent nuclear fuel geological disposal. in this conference. 2005. Gent.Google Scholar
21. Rovira, M. et al. , Study of the Role of Magnetite in the Immobilisation of U(VI) by Reduction to U(IV) under the Presence of H2(G) In Hydrogen Carbonate Media., in Technical Report. 2003, SKB: Stockholm.Google Scholar
22. Lemmens, K., The effect of clay on the dissolution of nuclear waste glass. J. Nucl. Mat., 2001. 298 p. 11–18.Google Scholar
23. Godon, N. and Vernaz, E., R7T7 nuclear waste glass behavior in moist clay: role of the clay mass/glass surface area ratio. Mater. Res. Soc. Symp. Proc. (1990), 176(Sci. Basis Nucl. Waste Manage. 13), 319-26 CODEN: MRSPDH; ISSN: 0272-9172: p. F.Google Scholar
24. Grambow, B. et al. , Sorption of Cs, Ni, Pb, Eu, Am, Cm, Ac, Tc, Th, Zr, and U(IV) on MX-80 bentonite: an experimental approach to assess model uncertainty. Migration-05, Avignon 2005, 2005.Google Scholar
25. Bradbury, M.H. and Baeyens, B., Modelling the sorption of Mn(II), Co(II), Ni(II), Zn(II), Cd(II), Eu(III), Am(III), Sn(IV), Th(IV), Np(V) and U(VI) on montmorillonite: Linear free energy relationships and estimates of surface binding constants for some selected heavy metals and actinides, in Geochimica et Cosmochimica Acta. 2005. p. 875.Google Scholar
26. Evolution phénoménologique du stockage géologique, in Dossier 2005 Argile. 2005, ANDRA.Google Scholar
27. Savage, D., Noy, D.J., and Mihara, M., Modelling The Interaction Of Bentonite With Hyperalkaline Fluids. Applied Geochemistry, 2002. 17 p. 207–223.Google Scholar
28. Gaucher, E. et al. , Modeling diffusion of an alkaline plume in a clay barrier. Applied Geochemistry, 2004. 19 p. 1505–1515.Google Scholar
29. ANDRA, Référentiel du comportement des radionucléides et des toxiques chimiques d'un stockage dans le Callovo-Oxfordien jusqu'à l'homme. Site de Meuse / Haute-Marne. 2005, ANDRA: Chatenay-Malabry.Google Scholar