Abstract
In the framework of the Enresa 2000 PA exercise and as a continuation of the developments made during SR 97, we have developed a conceptual and numerical model to calculate the release of radionuclides from spent fuel under repository conditions. The model includes both thermodynamic and kinetic considerations. Hence, although certain radionuclides are solubility controlled, for other radionuclides their release is governed by kinetic processes such as radiolytically promoted oxidative dissolution of the matrix and the associated water turnover inthe gap. The fluxes of selected radionuclides are calculated as an indication of the relative importance of the various processes considered to define source term concentrations in the performance assessment of the spent fuel repository.
This is a preview of subscription content, log in via an institution to check access.
Similar content being viewed by others
References
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.
Bruno J., Cera E., Duro L., Eriksen T.E. Sellin P. Spahiu K. and Werme L.O., 1997b. A kinetic model for the stability of the spent fuel matrix under oxic conditions. Model development against experimental evidence. Mater. Res. Soc. Symp. Proc. 465, 491–502.
Bruno J., Cera E., Duro L., Pon J. de Pablo J. and Eriksen T.E., 1998. Development of a kinetic model for the dissolution of UO2 spent nuclear fuel. Application of the model to the minor radionuclides. SKB Technical Report. TR-98-22.
Eriksen T.E., Eklund U.-B., Werme L.O. and Bruno J., 1995. Dissolution of irradiated fuel: a radiolytic mass balance study. J. Nucl. Mater. 227, 76–82.
Bruno J., Cera E., Griv M.é, U.-Eklund B. and Eriksen T.E., 1999. Experimental determination and chemical modelling of radiolytic processes at the spent fuel/water interface. SKB Technical Report. TR-99-26
Cera E., Merino J. and Bruno J., (2000). Liberación de los radionucleidos e isótopos estables contenidos en la matriz del combustible. Modelo conceptual y modelo matemático del comportamiento del residuo. Publicación Técnica ENRESA, to be published.
Enresa 2000, 1998. Elemento combustible de referencia irradiado: inventario másico y radiactivo, potencia térmica residual, espectro fotónico e inventario radiotóxico. Proyecto AGP 49-1PP-L-02-02.
Quiñones, J., Serrano, J., Díaz Arocas, P., Rodríguez Almazán, J.L., Bruno, J., Cera, E., Merino, J., Esteban, J.A., Mart, A.ínez-Esparza, 2000. Cálculo de la generación de productos radiolíticos en agua por radiación α. Determinación de la velocidad de alteración de la matriz del combustible nuclear gastado. Publicación Técnica ENRESA (to be published).
AMBER, 1999. AMBER 4.0 Reference Guide. QSL-5046a-1 Version 1.0 Oct 1998 Enviros Software Solutions. AMBER 4.2 Release Note. QSL-5046A-4 Version 1.0 Nov 1999 QuantiSci Limited. Henley-on-Thames, UK.
Wolery T.J., 1992. EQ3NR, A Computer Program for Geochemical Aqueous Speciation-Solubility Calculations: Theoretical Manual, User’s Guide, and Related Documentation (Version 7.0). UCRL-MA-110662 PT III, Lawrence Livermore National Laboratory, Livermore, California.
Author information
Authors and Affiliations
Corresponding author
Rights and permissions
About this article
Cite this article
Cera, E., Merino, J. & Bruno, J. Release of Radionuclides from Spent Fuel Under Repository Conditions: Mathematical Modelling and Preliminary Results. MRS Online Proceedings Library 663, 459 (2000). https://doi.org/10.1557/PROC-663-459
Published:
DOI: https://doi.org/10.1557/PROC-663-459