The SiC/SiC composite has been proposed as a candidate material for the fuel cladding component in advanced nuclear reactors. The present thesis aims to characterize the damage evolution within a SiC/SiC composite in different conditions and then validate a multiscale damage model. In order to gain insight into the damage mechanisms, in situ experimental methods are required to detect damage development and quantify the mechanical response at different scale to support the reliability assessment and simulation modelling of the components. In this thesis, in situ 3D laboratory and synchrotron X-ray computed tomography and quantitative digital volume correlation have been applied to characterize the damage evolution in a SiC/SiC composite,...
International audienceThe present paper proposes an investigation of the failure events in a melt-in...
International audienceThe present paper proposes an investigation of the failure events in a melt-in...
International audienceThe present paper proposes an investigation of the failure events in a melt-in...
The SiC/SiC composite has been proposed as a candidate material for the fuel cladding component in a...
The mechanical behaviour of a braided SiC-SiC ceramic composite tube has been investigated under dif...
SiC-SiC ceramic matrix composites are candidate materials for fuel cladding in Generation IV nuclear...
SiC-SiC ceramic matrix composites are candidate materials for fuel cladding in Generation IV nuclear...
SiC-SiC ceramic matrix composites are candidate materials for fuel cladding in Generation IV nuclear...
International audienceSiC/SiC composites are studied for their potential use in the next generation ...
International audienceSiC/SiC composites are studied for their potential use in the next generation ...
International audienceSiC/SiC composites are studied for their potential use in the next generation ...
SiC/SiC composites are studied for their potential use in the next generation of ...
SiC/SiC composites are studied for their potential use in the next generation of ...
International audienceThe present paper proposes an investigation of the failure events in a melt-in...
International audienceThe present paper proposes an investigation of the failure events in a melt-in...
International audienceThe present paper proposes an investigation of the failure events in a melt-in...
International audienceThe present paper proposes an investigation of the failure events in a melt-in...
International audienceThe present paper proposes an investigation of the failure events in a melt-in...
The SiC/SiC composite has been proposed as a candidate material for the fuel cladding component in a...
The mechanical behaviour of a braided SiC-SiC ceramic composite tube has been investigated under dif...
SiC-SiC ceramic matrix composites are candidate materials for fuel cladding in Generation IV nuclear...
SiC-SiC ceramic matrix composites are candidate materials for fuel cladding in Generation IV nuclear...
SiC-SiC ceramic matrix composites are candidate materials for fuel cladding in Generation IV nuclear...
International audienceSiC/SiC composites are studied for their potential use in the next generation ...
International audienceSiC/SiC composites are studied for their potential use in the next generation ...
International audienceSiC/SiC composites are studied for their potential use in the next generation ...
SiC/SiC composites are studied for their potential use in the next generation of ...
SiC/SiC composites are studied for their potential use in the next generation of ...
International audienceThe present paper proposes an investigation of the failure events in a melt-in...
International audienceThe present paper proposes an investigation of the failure events in a melt-in...
International audienceThe present paper proposes an investigation of the failure events in a melt-in...
International audienceThe present paper proposes an investigation of the failure events in a melt-in...
International audienceThe present paper proposes an investigation of the failure events in a melt-in...