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Microstuctural Characterization of the Radiation Effects in ZrC, a Potential Material for Next Generation Nuclear Plants

Published online by Cambridge University Press:  01 February 2011

Gianguido Baldinozzi ,
Dominique Gosset ,
David Simeone ,
Mickael Dollé ,
Lionel Thomé  and
Suzy Surblé
Gianguido Baldinozzi
Affiliation:
[email protected], CNRS, SPMS CNRS-Ecole Centrale Paris, ECP, grande voie des vignes, Chatenay-Malabry, 92295, France, Metropolitan, +33141131233
Dominique Gosset
Affiliation:
[email protected], CNRS, SPMS, Ecole Centrale Paris, Chatenay-Malabry, 92295, France, Metropolitan
David Simeone
Affiliation:
[email protected], CNRS, SPMS, Ecole Centrale Paris, Chatenay-Malabry, 92295, France, Metropolitan
Mickael Dollé
Affiliation:
[email protected], CNRS, SPMS, Ecole Centrale Paris, Chatenay-Malabry, 92295, France, Metropolitan
Lionel Thomé
Affiliation:
[email protected], CNRS, CSNSM, Université Paris XI, Orsay, 91405, France, Metropolitan
Suzy Surblé
Affiliation:
suzy.surblé@ecp.fr, CNRS, SPMS, Ecole Centrale Paris, Chatenay-Malabry, 92295, France, Metropolitan
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Abstract

The development of a new generation of nuclear reactors (Gen-IV), with improved thermodynamic yield and a reduction of waste production, makes necessary to consider materials able to withstand high operating temperatures. Transition metal carbides, like ZrC, are then under consideration. Despite their good thermal and neutron properties, they have unfortunately a brittle mechanical behaviour. This is the reason why it is important to investigate the properties of these systems with sub-micrometric grains and as a function of their composition. Therefore, samples having micrometric and nanometric grain sizes (and different oxygen content) were irradiated by low energy ions at room temperature to simulate their behaviour in a neutron flux. The irradiation effects in these materials were studied by grazing X-ray diffraction and transmission electron microscopy.

Keywords

radiation effectsdefectsphase transformation
Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 1043: Symposium T – Materials Innovations for Next-Generation Nuclear Energy , 2007 , 1043-T02-01
Copyright
Copyright © Materials Research Society 2008

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