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Oxidation of silicon carbide composites for nuclear applications at very high temperatures in steam

Abstract : Five 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 car-ried out until severe local degradation of the sample at maximum temperature of approximately 1845°C. The degradation was caused by complete consumption of the external CVD-SiC seal-coat resulting in steam access to the fiber-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. Three one-hour isothermal tests at 1700°C in steam with final water flooding and one three-hour experiment with fast cooldown in Ar atmosphere were run under nominally identical conditions. All isothermally tested samples survived the tests without any macroscopic degradation. The mechanical performance of such quenched clad seg-ments was not significantly affected with the maintenance of high capability to tolerate damages. Despite these harsh exposure conditions, load transfer between SiC fibers and matrix remains effi-cient, allowing the composites to accommodate deformation.
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https://hal-cea.archives-ouvertes.fr/cea-03771347
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Submitted on : Wednesday, September 7, 2022 - 12:00:25 PM
Last modification on : Saturday, September 10, 2022 - 3:26:04 AM

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Martin Steinbrueck, Mirco Grosse, Ulrike Stegmaier, James Braun, Christophe Lorrette. Oxidation of silicon carbide composites for nuclear applications at very high temperatures in steam. Progress in Color, Colorants and Coatings, Tehran Institute for Color Science and Technology, 2022, 12, pp.875. ⟨10.3390/coatings12070875⟩. ⟨cea-03771347⟩

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