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High-temperature oxidation of silicon carbide composites for nuclear applications

Steinbrück, M. ORCID iD icon; Große, M.; Stegmaier, U.; Braun, J.; Lorrette, C.

Abstract (englisch):

Three oxidation experiments at very high temperatures in steam atmosphere were conducted with advanced, nuclear grade SiCf/SiC CMC cladding tube segments. One transient experiment was carried out until local failure of the sample at maximum temperature of approximately 1845°C. The failure was caused by complete consumption of the external CVD-SiC seal-coat resulting in steam access to the fibre-matrix composite with less corrosion resistance. Approaching these very high temperatures was accompanied by accelerated gas release mainly of H2 and CO2, formation of surface bubbles and white smoke. Two isothermal tests lasting 1 hour at 1700°C in steam with final flooding with water were run under nominally identical conditions. Both samples survived the tests without any macroscopic degradation. The mechanical performance of such quenched clad segments was not significantly affected with the maintenance of high capability to tolerate damages. Despite these harsh conditions of exposure, the SiC fibre-matrix load transfer remains efficient to provide ability to the composites to accommodate the deformation.

Preprint §
DOI: 10.5445/IR/1000141512
Veröffentlicht am 23.12.2021
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Angewandte Materialien – Angewandte Werkstoffphysik (IAM-AWP)
Publikationstyp Proceedingsbeitrag
Publikationsmonat/-jahr 10.2021
Sprache Englisch
Identifikator KITopen-ID: 1000141512
HGF-Programm 32.12.02 (POF IV, LK 01) Beyond Design Basis and Emergency Management
Erschienen in Proceedings of the TOPFUEL 2021 Conference
Veranstaltung TopFuel (2021), Santander, Spanien, 24.10.2021 – 28.10.2021
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