SiC/SiC composite behavior in LWR conditions and under high temperature steam environment
Résumé
Tubular nuclear-grade SiC/SiC composites produced by CEA were investigated
in the present work as cladding material to enhance the accident tolerance of
Light Water Reactors (LWRs). A first part reports a preliminary assessment of the
behavior of SiC/SiC composite tubes in simulated relevant LWR conditions
related with the manufacturing parameters. The dependence of the corrosion rate
on the chemical composition of water is also investigated for a better
understanding of the hydrothermal SiC corrosion mechanisms. Additionally, the
ability of SiC/SiC composite tubes to preserve their geometry and maintain
coolability under high temperature steam environment is examined. Oxidation
tests are performed to confirm the favorable behavior and to evaluate the
oxidation kinetics of the composite exposed to high-temperature steam (up to
1400°C) under pressure and under dynamic gas flow conditions.
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