Hostname: page-component-6bf8c574d5-mggfc Total loading time: 0 Render date: 2025-02-20T14:33:15.442Z Has data issue: false hasContentIssue false
  • English
  • Français

Modeling of Near Field Actinide Concentrations in Radioactive Waste Repositories in Salt Formations: Effect of Buffer Materials

Published online by Cambridge University Press:  21 March 2011

W. Schuessler ,
B. Kienzler ,
S. Wilhelm ,
V. Neck  and
J.I. Kim
W. Schuessler
Affiliation:
Institut für Nukleare Entsorgung, Forschungszentrum Karlsruhe Postfach 3640, D-76021 Karlsruhe, GermanyEmail: [email protected]
B. Kienzler
Affiliation:
Institut für Nukleare Entsorgung, Forschungszentrum Karlsruhe Postfach 3640, D-76021 Karlsruhe, GermanyEmail: [email protected]
S. Wilhelm
Affiliation:
Institut für Nukleare Entsorgung, Forschungszentrum Karlsruhe Postfach 3640, D-76021 Karlsruhe, GermanyEmail: [email protected]
V. Neck
Affiliation:
Institut für Nukleare Entsorgung, Forschungszentrum Karlsruhe Postfach 3640, D-76021 Karlsruhe, GermanyEmail: [email protected]
J.I. Kim
Affiliation:
Institut für Nukleare Entsorgung, Forschungszentrum Karlsruhe Postfach 3640, D-76021 Karlsruhe, GermanyEmail: [email protected]
Get access

Abstract

Engineered barrier systems are designed to reduce the near field actinide concentrations in case of water penetration into a repository. In this paper, the influence of buffer materials, such as MgO/CaO and clays, on the solubilities of Am, Np, Pu, and U is studied. The analysis is performed for low level cemented waste forms in a rock salt formation in contact with MgCl2 saturated salt brine (Q-brine).

The evolution of the geochemical milieu by cement corrosion is calculated using reaction path modeling supported by the code EQ3/6. The influence of different buffer materials is analyzed with respect to their impact on the solution chemistry and corresponding actinide concentrations.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 663: Symposium – Scientific Basis for Nuclear Waste management XXIV , 2000 , 791
Copyright
Copyright © Materials Research Society 2001

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

1. Claiborne, H. C., ORNL/TM-8372, (1982).Google Scholar
2. Kim, J.-I. and Grambow, B., Eng. Geol. 52, p. 221–230, (1999).Google Scholar
3. Grambow, B., Kienzler, B., Bauer, A., Vejmelka, P., and Rudolph, B., International Backfill Workshop, Carlsbad, USA, May 1998, 1998.Google Scholar
4. Kienzler, B., Vejmelka, P., Herbert, H.-J., Meyer, H., and Altenhein-Haese, C., Nucl. Technol. 129, p. 101–118, (2000).Google Scholar
5. Wolery, T. J., Lawrence Livermore National Laboratory, Livermore, California UCRL-MA- 110662-PT-I, (1992).Google Scholar
6. Harvie, C. F., Mφller, N., and Weare, J. H., Geochim. Cosmochim. Acta 48, p. 723, (1984).Google Scholar
7. Pitzer, K. S., in Activity coefficients in electrolyte solutions, Pitzer, K. S., Ed. Raton, Boca, Florida: CRC Press, 1979.Google Scholar
8. Pitzer, K. S., in Thermodynamic Modeling of Geological Materials: Minerals, Melts and Fluids. Reviews in Mineralogy., Carmichael, H. P., Ed.: Mineralogical Society of America, 1987, pp. 97–142.Google Scholar
9. Kienzler, B. and Altenhein-Haese, C., DisTec'98, Hamburg, 1998.Google Scholar
10. Kienzler, B., Radioactive Waste Products 1997, Würzburg, Germany, 1998.Google Scholar
11. Silva, R. J., Bidoglio, G., Rand, M. H., Robouch, P., Wanner, H., and Puigdomenech, I., Chemical Thermodynamics Vol. 2. Thermodynamics of Americium, vol. 48, (1995).Google Scholar
12. Grenthe, I., Fuger, J., Konings, R. J. M., Lemire, R. J., Muller, A. B., Cregu, C. Nguyen-Trung, and Wanner, H., Chemical Thermodynamics Vol. 1. Thermodynamics of Uranium, vol. 48, (1992).Google Scholar
13. Neck, V. and Kim, J. I., Institut für Nukleare Entsorgungstechnik, Forschungszentrum Karlsruhe, FZKA 6350, (1999).Google Scholar
14. Neck, V., Fanghänel, T., and Kim, J. I., Institut für Nukleare Entsorgungstechnik, Forschungszentrum Karlsruhe, FZKA 6110, (1998).Google Scholar
15. Neck, V., Fanghänel, T., and Kim, J. I., Institut für Nukleare Entsorgungstechnik, Forschungszentrum Karlsruhe, FZKA 6340, (1999).Google Scholar
16. Vejmelka, P., pers. communication, 2000 Google Scholar