Hostname: page-component-8448b6f56d-m8qmq Total loading time: 0 Render date: 2024-04-16T09:41:42.845Z Has data issue: false hasContentIssue false
  • English
  • Français

Modeling of Spent Fuel Oxidation at Low Temperature

Published online by Cambridge University Press:  19 October 2011

Arnaud Poulesquen ,
Lionel Desgranges  and
Cécile FERRY
Arnaud Poulesquen
Affiliation:
arnaud.poulesquen@cea.fr, CEA, Department of Physico Chemistry, CEA Saclay, Gif sur Yvette, 91191, France
Lionel Desgranges
Affiliation:
lionel.desgranges@cea.fr, CEA, Department of spent fuel studies, St Paul lez Durance, 13108, France
Cécile FERRY
Affiliation:
cecile.ferry@cea.fr, CEA, Department of Physico Chemistry, Gif sur Yvette, 91191, France
Get access

Abstract

During dry storage, the oxidation of the spent fuel in case of cladding and container failure (accidental scenario) could be detrimental for further handling of the spent fuel rod and for the safety of the facilities. Depending on whether the uranium dioxide is under the form of powder or pellet, irradiated or unirradiated, the weight gain curves do not present the same shape. To account for these different behaviours, two models have been developed. Firstly, the oxidation of unirradiated powders has been modelled based on the coexistence, during the oxidation, of two intermediate products, U4O9 and U3O7. The comparison between the calculation and the literature data is good in terms of weight gain curves and chemical diffusion coefficient of oxygen within the two phases. Secondly, the oxidation of spent fuel fragments is approached by a convolution procedure between a grain oxidation model and an empirical parameter which represents the linear oxidation speed of grain boundary or an average distance able to cover the entire spent fuel fragment. This procedure of calculation allows in one hand to account for the incubation period noticed on unirradiated pellets or spent fuel and in another hand to link the empirical parameter to physical as porosity, cracks or linear power, or operational parameters such as fission gas release (FGR) respectively. A comparison of this new modelling with experimental data will be proposed.

Keywords

oxidationUdiffusion
Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 985: Symposium NN – Scientific Basis for Nuclear Waste Management XXX , 2006 , 0985-NN05-04
Copyright
Copyright © Materials Research Society 2007

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. Campbell, T. K., Gilbert, E. R., Thornhill, C. K., Wrona, B. J., Nucl. Tech., 84, 182 (1978)Google Scholar
2. Tucker, P. M., Proc. Workshop on Chemical Reactivity of Oxide Fuel and Fission Product Release, 49 (1987)Google Scholar
3. Desgranges, L., Rousseau, G., Ferroud-Plattet, M-P., Ferry, C., Giaccalone, H., Aubrun, I., Delion, P., Untrau, J-M., Mat. Res. Soc. Symp. Proc. 932, 457 (2006)Google Scholar
4. Poulesquen, A., Desgranges, L., Ferry, C., accepted to J. Nucl. Mater. (2006)Google Scholar
5. Aronson, S., Roof, R. B., Belle, J., J. Phys. Chem., 27, 137 (1957)Google Scholar
6. McEachern, R. J., Taylor, P., J. Nucl. Mater., 254, 87 (1998)Google Scholar
7. Hanson, B., PNNL-11929 report, (1998)Google Scholar