Hostname: page-component-745bb68f8f-f46jp Total loading time: 0 Render date: 2025-01-15T06:59:53.124Z Has data issue: false hasContentIssue false
  • English
  • Français

Modelling UO2 and Simfuel Leaching Behaviour in Granite Groundwater Under Oxidizing Conditions

Published online by Cambridge University Press:  10 February 2011

J. Quiñones ,
J. Garcia Serrano ,
J. A. Serrano ,
P. Diaz Arocas ,
J. L. Rodriguez  and
J. Blazquez
J. Quiñones
Affiliation:
CIEMAT. Dept. de Fision Nuclear. Avda. Complutense 22. 28040-Madrid. SPAIN, quinones@ciemat.es
J. Garcia Serrano
Affiliation:
CIEMAT. Dept. de Fision Nuclear. Avda. Complutense 22. 28040-Madrid. SPAIN, quinones@ciemat.es
J. A. Serrano
Affiliation:
CIEMAT. Dept. de Fision Nuclear. Avda. Complutense 22. 28040-Madrid. SPAIN, quinones@ciemat.es
P. Diaz Arocas
Affiliation:
CIEMAT. Dept. de Fision Nuclear. Avda. Complutense 22. 28040-Madrid. SPAIN, quinones@ciemat.es
J. L. Rodriguez
Affiliation:
CIEMAT. Dept. de Fision Nuclear. Avda. Complutense 22. 28040-Madrid. SPAIN, quinones@ciemat.es
J. Blazquez
Affiliation:
CIEMAT. Dept. de Fision Nuclear. Avda. Complutense 22. 28040-Madrid. SPAIN, quinones@ciemat.es
Get access

Abstract

The Uranium concentration leaching behaviour for UO2 and SIMFUEL in granite groundwater under oxidizing conditions is modelled. The model contemplates two terms: a source term and a loss term. The source term represents the bulk dissolution process and its upper limit is controlled by the solubility of the thermodynamically stable solid phase. The loss term emulates the solute removed due to groundwater flow into the repository. It can forecast the uranium steady state concentration when groundwater flow is considered. The model has been tested with three different types of leaching experiments, performed with UO2 and SIMFUEL. Good agreement between experimental results and model predictions are found.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 556: Symposium QQ – Scientific Basis for Nuclear Waste Management XXII , 1999 , 479
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. Peters, E. and Halpen, J., Can. Mining Metall. Bull. 46, p. 649–644 (1953).Google Scholar
2. Halpern, J. and Smith, J.G., Can. J. Chem. 34, p. 1419–1427 (1956).Google Scholar
3. Pablo, J. De, Casas, JI., Giménez, J., Martí, V., and Torrero, M.E., J. Nucl. Mat. 232, p. 138–145 (1996).Google Scholar
4. Bruno, J., Cera, E., Duro, L., Eriksen, T.E., Sellin, P., Spahiu, K., and Werme, L.O., in Scientific Basis for Nuclear Waste Management XX, edited by Gray, W.J. and Triay, I.R. (Mat. Res. Soc. Proc. 465, Pittsburgh, PA 1997), p. 491–502.Google Scholar
5. Trocelier, P., Cachoir, C., and Guilbert, S., J. Nucl. Mater. 256, p. 197–206 (1998).Google Scholar
6. Lucuta, P.G., Palmer, B.J., Matzke, H.J., and Hastings, D.S., in Proc. 2nd Int. Conf. On CANDU Fuel, edited by Hastings, I.J. (CNS, Pembroke, 1989) p. 132.Google Scholar
7. Pablo, J. De, private communication, 1995.Google Scholar
8. CIEMAT Procedimiento especffico NO PR-X8-01 (1996) (in Spanish).Google Scholar
9. Grambow, B. and Müller, R., in Scientific Basis for Nuclear Waste Management XIII, edited by Oversby, V.M. and Brown, P.W. (Mat. Res. Soc. Proc. 176, Pittsburgh, PA 1990), p. 229–240.Google Scholar
10. Wolery, T.J., EQ3NR A computer program for geochemical aqueous speciation - solubility calculations: Theoretical manual, user's guide and related documentation (version 7.0) (1992).Google Scholar
11. Grenthe, et al. “Chemical Thermodynamics of Uranium”, edited by Wanner, H. and Forest, I., NEA-OCDE (1992).Google Scholar
12. Garcia-Serrano, J., Serrano, J.A., Diaz-Arocas, P., Quiñones, J., and Almazan, J.L.R., in Scientific Basis for Nuclear Waste Management XIII, edited by Oversby, V.M. and Brown, P.W. (Mat. Res. Soc. Proc. 412, Pittsburgh, PA 1996), p. 229–240.Google Scholar
13. Quihones, J., Garcia-Serrano, J., Serrano, J.A., Diaz-Arocas, P., and Almazan, J.L.R., in Scientific Basis for Nuclear Waste Management XXI, edited by McKinley, I.G. and McCombie, C. (Mat. Res. Soc. Proc. 506, Pittsburgh, PA 1998), p. 247–252.Google Scholar