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Chemical durability and performance of assessment of spent fuel and high level waste forms under simulated repository conditions – Spanish contribution to IAEA project

Published online by Cambridge University Press:  21 March 2011

Aurora Martínez-Esparza ,
José Antonio Gago ,
Javier Quiñones ,
Eduardo Iglesias ,
Esther Cera ,
Juan Merino ,
Joan de Pablo  and
Ignasi Casas
Aurora Martínez-Esparza
Affiliation:
ENRESA, C/ Emilio Vargas 7, 28043-Madrid., SPAIN
José Antonio Gago
Affiliation:
ENRESA, C/ Emilio Vargas 7, 28043-Madrid., SPAIN
Javier Quiñones
Affiliation:
Ciemat. Avda. Complutense 22, 28040-Madrid., SPAIN
Eduardo Iglesias
Affiliation:
Ciemat. Avda. Complutense 22, 28040-Madrid., SPAIN
Esther Cera
Affiliation:
ENVIROS, Passeig de Rubi, 29 - 31, 08197 Valldoreix, Barcelona., SPAIN
Juan Merino
Affiliation:
ENVIROS, Passeig de Rubi, 29 - 31, 08197 Valldoreix, Barcelona., SPAIN
Joan de Pablo
Affiliation:
Dept. of Chemical Engineering. ETSEIB-UPC, Diagonal 647 H-4, 08028 Barcelona., SPAIN
Ignasi Casas
Affiliation:
Dept. of Chemical Engineering. ETSEIB-UPC, Diagonal 647 H-4, 08028 Barcelona., SPAIN
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Abstract

Chemical durability of spent fuel under repository conditions is one of the main topics of interest in national and international projects from the last two decades. During the last decade there have been growing the activities in Enresa related to the deep disposal concept with the aim of developing a spent fuel alteration model for the understanding of the behaviour of this nuclear waste under repository conditions. In this context, the development and utilisation of models and sub-models based on experimental work have been of great importance.

Experimental studies with spent fuel(in Collaboration Agreement with ITU) and spent fuel analogues in several environmental conditions have been carried out into Enresa R+D Programmes in order to reach a better knowledge of the relevant processes and to quantify the spent fuel chemical durability under repository conditions.

In this work, it is showed the utility of data provided from experiments with spent fuel analogues to test the mechanisms and the influence of relevant parameters in the spent fuel alteration under repository conditions.

The evolution of irradiated fuel under interim storage conditions and in deep geologic storage and its oxygen to metal ratio (O/M) before the water access to the fuel is another factor of great influence on enhanced spent fuel leaching. This effect has been also studied by means of spent fuel analogues and by using simulated (artificially) aged fuel.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 932: Symposium – Scientific Basis for Nuclear Waste Management XXIX , 2006 , 96.1
Copyright
Copyright © Materials Research Society 2006

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References

REFERENCES

[1] ENRESA,“Evaluación del comportamiento y de la seguridad de un almacenamiento geológico profundo en granito,” in Publicación técnica ENRESA, vol. 06-97. Madrid, 1997.Google Scholar
[2] ENRESA,“ENRESA 2000. Evaluación del comportamiento y de la seguridad de un almacenamiento de combustible gastado en una formación granítica,” vol. 49-1PP-M-15-01 Rev. 0. Madrid: ENRESA, 2001, pp. 400.Google Scholar
[3] Yucca Mountain Project,“Total System Performance Assessment - Analyses for Disposal of Commercial and DOE Waste Inventories at Yucca Mountain - Input to Final Environmental Impact Statement and Site Suitability Evaluation,” TSPA-SR 2000, 2001.Google Scholar
[4] DOE (U.S. Department of Energy),“Final Environmental Impact Statement - for a Geological Repository for the Disposal of Spent fuel and High Level Radioactive waste at Yucca Mountain, Nye Country, Nevada. DOE/EIS-0250,” U.S. Department of Energy, Office of Nuclear Waste Management., Washington, D.C. DOE/EIS-0250, 2002.Google Scholar
[5] Ewing, R. C.,“Less Geology in the Geological Disposal of Nuclear Waste,” Science, vol. 286, pp. 415–417, 1999.Google Scholar
[6] Shoesmith, D. W., Laboratoires de Whiteshell, and Energie atomique du Canada., Prediction of long-term behaviour for nuclear waste disposal. Pinawa, Man.: Whiteshell Laboratories, 1996.Google Scholar
[7] SKB,“Deep repository for nuclear fuel. SR 97 - Post-closure safety,” in SKB Technical Report, vol. TR-99-06, 1997.Google Scholar
[8] SPA project,“Spent fuel disposal performance assessment,” EUR, vol. 1932, 2000.Google Scholar
[9] Wronkiewicz, D. J., Bates, J. K., Gerding, T. J., Veleckis, E., and Tani, B. S.,“Uranium release and secondary phase formation during unsaturated testing of UO2 at 90 °C,” J. Nucl. Mater., vol. 190, pp. 101–106, 1992.Google Scholar
[10] Forsyth, R. S.,“Spent nuclear fuel: A review of properties of possible relevance to corrosion processes,” in SKB technical report, vol. 95:23. Stockholm: SKB, 1995, pp. vi, 46 bl.Google Scholar
[11] Lucuta, P. G., Balmer, B. J., Matzke, H. j., and Hartwig, D. S.,“Preparation and Characterization of SIMFUEL: Simulated CANDU High-Burnup Nuclear Fuel,” Atomic Energy of Canada Limited AECL-1017, 1989.Google Scholar
[12] Serrano, J. A., Quiñones, J., Cobos, J., Arocas, P. P. Díaz, Rondinella, V. V., Glatz, J. P., Matzke, H. j., Esparza, A. Martínez, and Esteban, J. A.,“Leaching study of the behaviour of spent fuel and SIMFUEL under simulated granitic repository conditions,” presented at VIII Int. Conf. On Environmental Management, Brujas, Bélgium, 2001.Google Scholar
[13] Gerenthe, I., Fuger, J., Konings, R. J., Lemire, R. J., Muller, A. B., Nguyen, C. Trung, and Wanner, H., Chemical Thermodynamics of Uranium, vol. 1. Amsterdam: North-Holland, 1992.Google Scholar