Hostname: page-component-7bb8b95d7b-s9k8s Total loading time: 0 Render date: 2024-09-16T04:41:45.743Z Has data issue: false hasContentIssue false
  • English
  • Français

Modeling the Durability of Silica Additives Proposed to Protect Nuclear Waste Glass Packages in A Geological Repository

Published online by Cambridge University Press:  10 February 2011

Yves Minet  and
Étienne Vernaz
Yves Minet
Affiliation:
Commissariat à l' Énergie Atomique (CEA), Rhône Valley Research Center BP 171, 30207 Bagnols-sur-Cèze Cedex, Franceyves.minetQcea.fr, [email protected]
Étienne Vernaz
Affiliation:
Commissariat à l' Énergie Atomique (CEA), Rhône Valley Research Center BP 171, 30207 Bagnols-sur-Cèze Cedex, Franceyves.minetQcea.fr, [email protected]
Get access

Abstract

Silica additives have been proposed to protect nuclear waste glass packages in deep geological repositories by presaturating silicon adsorption sites* in the media surrounding the package (engineered barrier, canister and overpack corrosion products). The durability of such additives was estimated using a one-dimensional dissolution-transport model developed at the CEA's Rhône Valley Research Center for the French reference glass in typical disposal sites. The silica additive would be placed between the wasteform and the overpack and thus dissolved before the waste glass. Its lifetime is proportional to Madd2(where Madd is the added silica mass) up to a critical value Mcrit at which it increases considerably (from 103 or 104 to 108 years) due to saturation of the adsorption sites. Excess silica consumption is then limited by the typically very low (3 × 10−3 l·m−2y−1 ) groundwater flow in the geological site. After consumption of the added silica, the evolution of the altered waste glass fraction is comparable to the evolution without added silica if Madd « Mcrit, but much lower if Madd ≈ Mcrit or Madd > Mcrit. These findings were confirmed by some experimental evidence, and establish that a few kilograms of added silica for a 400 kg package can considerably enhance the waste glass durability.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 556: Symposium QQ – Scientific Basis for Nuclear Waste Management XXII , 1999 , 633
Copyright
Copyright © Materials Research Society 1999

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. Curti, E., Godon, N. and Vernaz, E., in Scientific Basis for Nuclear Waste Management XVJ, vol.294, pp. 163–170 (1993).Google Scholar
2. Gin, S., in CEA-VALRHO Summer Session Proceedings on Glass – Scientific Research for High Performance Containment, ed. Graphot, , pp. 514–526 (1997).Google Scholar
3. Maillard, S. and Iracane, D., in Scientific Basis for Nuclear Waste Management XXI, vol.506, pp. 231–238 (1998).Google Scholar
4. Godon, N., Andriambololona, Z. and Vernaz, E., in Scientific Basis for Nuclear Waste Management XV, vol.257, pp. 135–141 (1992).Google Scholar
5. Grambow, B., in Scientific Basisfor Nuclear Waste Management VIII, vol.44, pp. 15–21 (1985).Google Scholar
6. Techer, I., Advocat, T., Vernaz, E., Lancelot, J-R. and Liotard, J-M., in CEA-VALRHO Summer Session Proceedings on Glass – Scientific Research for High Performance Containment, ed. Graphot, , pp. 615–621 (1997).Google Scholar
7. Delage, F., Étude de la fonction cinétique de dissolution d'un verre nucl´aire, Thesis University Montpellier-II (1992).Google Scholar
8. Lehikoinen, J., Carlsson, T., Muurinen, A., Olin, M. and Salonen, P., in Scientific Basis for Nuclear Waste Management XIX, vol.412, pp. 675–682 (1996).Google Scholar
9. Kote, F. Van, Peres, J-M., Olivier, M., Lewi, J., Assouline, M. and Mejon-Goula, M-J., PAGISÉtude des performances de systkmes d'isolement géologique pour ddchets radioactifs – Enfouissement dans des formations granitiques, EUR 11177 FR, pp. 31–56 (1988).Google Scholar
10. Carslaw, H-S. and Jaeger, J-C., Conduction of Heat in Solids, pp. 114–127, Oxford (1959).Google Scholar