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An Experimental Study on the Influence of Gamma Radiation on Spent Fuel Dissolution in the Presence of a H2 Atmosphere

Published online by Cambridge University Press:  17 March 2011

Javier Quiñones ,
Jose Manuel Cobo ,
Ángel González de la Huebra  and
Aurora Martínez Esparza
Javier Quiñones
Affiliation:
Nuclear Fission Department, Ciemat (Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas), Avda Complutense 22, 28040 Madrid, Spain, javier.quinones@ciemat.es
Jose Manuel Cobo
Affiliation:
Nuclear Fission Department, Ciemat (Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas), Avda Complutense 22, 28040 Madrid, Spain
Ángel González de la Huebra
Affiliation:
Nuclear Fission Department, Ciemat (Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas), Avda Complutense 22, 28040 Madrid, Spain
Aurora Martínez Esparza
Affiliation:
ENRESA (Empresa Nacional de Residuos Radiactivos), C/ Emilio Vargas 7, 28043 Madrid, Spain
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Abstract

Any environmental performance assessment of spent nuclear fuel disposal requires a prediction of the spent fuel matrix alteration rate when contact with groundwater is established. Taking into account the disposal design, the groundwater at the expected depth of the repository are generally reducing. These reducing redox conditions near the spent fuel surface may be changed to oxidising conditions by the radiolysis of water, due to radiation associated with the waste. This study is focussed on determining the influence of the γ radiation on the spent fuel matrix alteration rate under simulated repository conditions. A series of sequential leaching experiments under controlled conditions have been done. The experiments simulate the repository environmental conditions when engineering barriers are degraded and groundwater arrives at the surface of the spent fuel. In these experiments SIMFUEL (SIMulated FUEL) was used as analogue of spent fuel. Two types of leachant (i.e., granitic water and bentonitic-granitic water) were used in the leaching experiments. These experiments were irradiated using γ- radiation at an industrial irradiation facility with a 60Co source. The results obtained in this study show different behaviour as a function of both the leachant used in the leaching experiments and the initial atmosphere used in the experiments. As a preliminary conclusion of this experimental work, under γ radiation and a small partial pressure of H2 (1 bar) in the first steps of the leaching process has a beneficial effect since U in solution is lower than any other conditions and overall alteration rate is minimized. For experimental times longer than one day, a clear increase of the U in solution is revealed in the experimental run products.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 824: Symposium CC – Scientific Basis for Nuclear Waste Management XXVIII , 2004 , CC9.6
Copyright
Copyright © Materials Research Society 2004

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References

[1] Shoesmith, D. W., J. Nucl. Mater., 282, 1 (2000).Google Scholar
[2] Serrano, J. A., Quiñones, J., Cobos, J. et al., in Scientific Basis for Nuclear Waste Management XXIII, edited by Smith, R.W. and Shoesmith, D. W. (The Materials Research Society) 608, 61 (2000).Google Scholar
[3] Oversby, V. M., in SKB Technical Reports, TR-99-22 (1999).Google Scholar
[4] Lucuta, P. G., Verall, R. A., Matzke, H. J. et al., J. Nucl. Mater., 178, 48 (1991).Google Scholar
[5] Quiñones, J., Serrano, J. García, Agejas, J. A. Serrano et al., in Scientific Basis for Nuclear Waste Management XXI, edited by McKinley, I. G. and McCombie, C. (Materials Research Society) 506, 247 (1998).Google Scholar
[6] Serrano, J. A., Quiñones, J., Cobos, J. et al., Radioactive Waste Management and Environmental Remediation - ASME (2001).Google Scholar
[7] Martinez, B., Melon, A., and Valladares, J, in Informes Técnicos (Ciemat), PR-X8-01 (1996).Google Scholar
[8] Röllin, S., Spahiu, K., and Eklund, U.-B., J. Nucl. Mater., 297, 231 (2001).Google Scholar
[9] Quiñones, J., Serrano, J. García, Serrano|Agejas, J. A. et al., in Scientific Basis for Nuclear Waste Management XXIII (Materials Research Society) 556, 479 (1999).Google Scholar