Hostname: page-component-586b7cd67f-g8jcs Total loading time: 0 Render date: 2024-11-28T16:26:48.372Z Has data issue: false hasContentIssue false
  • English
  • Français

Modelling the Release of Radionuclides from the Spent Fuel and their Transport in the Near Field: a Coupled Approach

Published online by Cambridge University Press:  01 February 2011

Juan Merino ,
Esther Cera ,
Jordi Bruno  and
Aurora Martínez-Esparza
Juan Merino
Affiliation:
Enviros Spain, Pg. de Rubí 29–31, 08197 Valldoreix (Spain)
Esther Cera
Affiliation:
Enviros Spain, Pg. de Rubí 29–31, 08197 Valldoreix (Spain)
Jordi Bruno
Affiliation:
Enviros Spain, Pg. de Rubí 29–31, 08197 Valldoreix (Spain)
Aurora Martínez-Esparza
Affiliation:
Enresa, C/ Emilio Vargas 7, 28043 Madrid (Spain)
Get access

Abstract

In this work we have developed a model for the release of radionuclides from the spent fuel coupled with their transport through the near field. A compartmental approach has been used, as this methodology is well suited to model integrated systems. Several processes have been taken into account: oxidative dissolution of the spent fuel matrix, radioactive decay and chains, diffusive and advective transport, retardation by sorption and secondary phase precipitation. Results illustrate the complex evolution of the radionuclide concentrations in the gap and the near field. Hence, the main conclusion from this study is the requirement to model this coupled system using a compartmental integrated approach.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 807: Symposium Scientific Basis for Nuclear Waste Management XXVII , 2003 , 785
Copyright
Copyright © Materials Research Society 2004

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. Bruno, J., Cera, E., Duro, L., Eriksen, T.E. and Werme, L.O., 1996. A kinetic model for the stability of spent fuel matrix under oxic conditions. J. Nucl. Mater. 238, 110–120.Google Scholar
2. Cera, E., Merino, J., Bruno, J., 2000. Release of radionuclides from spent fuel under repository conditions: mathematical modelling and preliminary results. In: Scientific Basis for Nuclear Waste Management XXIV, edited by Hart, K.P. and Lumpkin, G.R. (Mat. Res. Soc. Symp. Proc. 663, 2000), pp. 459–467.Google Scholar
3. Enresa 2000. Evaluación del comportamiento y de la seguridad de un almacenamiento de combustible gastado en una formación granítica. Proyecto AGP, 49–1PP-M–1–501.Google Scholar
4. AMBER 4.4 Reference Guide, April 2002. Enviros QuantiSci, Culham, UK.Google Scholar
5. Merino, J., Cera, E., Bruno, J., Eriksen, T., Quiñones, J. and Martínez-Esparza, A., 2001. Long term modelling of spent fuel oxidation/dissolution under repository conditions. In: 8th International Conference on Radioactive Waste Management and Environmental Remediation. Bruges, Belgium, 30 Sept. – 4 Oct. 2001.Google Scholar