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Release of Radionuclides from Spent Fuel Under Repository Conditions: Mathematical Modelling and Preliminary Results

Published online by Cambridge University Press:  21 March 2011

Esther Cera ,
Juan Merino  and
Jordi Bruno
Esther Cera
Affiliation:
EnvirosQuantiSci (Spain), Parc Tecnològic del Vallàs, 08290 Cerdanyola (Spain)
Juan Merino
Affiliation:
EnvirosQuantiSci (Spain), Parc Tecnològic del Vallàs, 08290 Cerdanyola (Spain)
Jordi Bruno
Affiliation:
EnvirosQuantiSci (Spain), Parc Tecnològic del Vallàs, 08290 Cerdanyola (Spain) Email:jbruno@quantisci.es
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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.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 663: Symposium – Scientific Basis for Nuclear Waste management XXIV , 2000 , 459
Copyright
Copyright © Materials Research Society 2001

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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. Bruno, J., Cera, E., Duro, L., Eriksen, T.E. Spahiu, Sellin P. , 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.Google Scholar
3. Bruno, J., Cera, E., Duro, L., , Pon Pablo, J. de , 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.Google Scholar
4. 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.Google Scholar
5. Bruno, J., Cera, E., Grivé, M., Eklund, U.-B. and Eriksen, T.E., 1999. Experimental determination and chemical modelling of radiolytic processes at the spent fuel/water interface. SKB Technical Report. TR-99-26Google Scholar
6. 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.Google Scholar
7.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.Google Scholar
8. Quiñones, J., Serrano, J., Díaz Arocas, P., Rodríguez Almazán, J.L., Bruno, J., Cera, E., Merino, J., Esteban, J.A., Martínez-Esparza, A., 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).Google Scholar
9.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.Google Scholar
10. 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.Google Scholar