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Thin film samples: a new methodology for investigating the mechanisms of fission gas releases from nuclear fuel during a LOCA

Published online by Cambridge University Press:  13 July 2016

Guillaume Brindelle ,
Gianguido Baldinozzi ,
Hélène Capdevila ,
Lionel Desgranges  and
Yves Pontillon
Guillaume Brindelle*
Affiliation:
CEA, DEN, DEC, F-13108 Saint-Paul-Lez-Durance, France CNRS, SPMS, LRC CARMEN, CentraleSupelec, F-92295, Châtenay-Malabry, France
Gianguido Baldinozzi
Affiliation:
CNRS, SPMS, LRC CARMEN, CentraleSupelec, F-92295, Châtenay-Malabry, France
Hélène Capdevila
Affiliation:
CEA, DEN, DEC, F-13108 Saint-Paul-Lez-Durance, France
Lionel Desgranges
Affiliation:
CEA, DEN, DEC, F-13108 Saint-Paul-Lez-Durance, France
Yves Pontillon
Affiliation:
CEA, DEN, DEC, F-13108 Saint-Paul-Lez-Durance, France
*
*(Email: guillaume.brindelle@cea.fr)
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Abstract

Accurately predicting fission gas releases (FGR) from high burn-up fuels during off-normal conditions, such as a loss-of-coolant accident (LOCA), is an important, major challenge. A significant step forward would be to identify and assess the basic mechanisms causing this FGR. A helpful way of better understanding these basic mechanisms is to separate these effects and to perform irradiations on materials simulating the nuclear fuel. Mesoporous or dense CeO2 and UO2 samples (with thin film geometry) were selected for these studies as materials representative of irradiated fuels. A basic mechanism to obtain a better understanding of FGR is described and a new methodology using thin film samples is developed to test the validity of this mechanism.

Keywords

nuclear materialsannealingthin film
Type
Articles
Information
MRS Advances , Volume 1 , Issue 35: Materials Design , 2016 , pp. 2439 - 2445
Copyright
Copyright © Materials Research Society 2016 

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References

REFERENCES

Pontillon, Y., Bonnin, J., European Working Group, Hot Laboratories and Remote Handling, Plenary Meeting, Petten, the Netherlands, 2005.Google Scholar
Pontillon, Y., Ducros, G., International Conference, Nuclear Energy for New Europe, Slovenia, 2006.Google Scholar
Marcet, M., Pontillon, Y., Contribution to High Burn up Structure the Fission Gas Release under Transient Condition, WRFPM/ Top Fuel, 2009.Google Scholar
Colle, J.-Y., Journal of Nuclear Materials 442, 330–340 (2013).Google Scholar
Noirot, J., Pontillon, Y., Journal of Nuclear Materials 446, 163–171 (2014).Google Scholar
Matzke, H., Nuc. Inst. & Meth. in Phys. Res. 65, 30–39 (1992).Google Scholar
Turos, A., Matzke, H., and Kwiatkowski, S., Physical Review Letters 65, 1215–1218 (1990).Google Scholar
Turos, A., Matzke, H., Wielunski, M., and Nowicki, L., Nuc. Inst. & Meth.. in Phys. Res. 80-1, 1259–1263 (1993).Google Scholar
Labrim, H., Barthe, M.-F., Desgardin, P., Sauvage, T., Corbel, C., Blondiaux, G., and Piron, J. P., Nuc. Inst. & Meth. in Phys. Res. 261, 883–887 (2007).Google Scholar
Thompson, A. E. al., Physical Review B 84, 134111 (2011).Google Scholar
Brillant, G. and al, Journal of Nuclear Materials 412, 170–176 (2011).Google Scholar
Nakamura, , NSR 46, n°9, 944 (2009).Google Scholar
Kishino, T., Nuc. Inst. & Meth. in Phys. Res. 314, 191–194 (2013).Google Scholar
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