Properties of silicon carbide for nuclear fuel particle coatings

The properties of pyrolytic silicon carbide (SiC) that are important to its use in nuclear fuel particle coatings are reviewed. The structure of material deposited under different conditions varies in growth features and the constituent phases; the principal effects of neutron irradiation on the structure are to create point defect clusters at irradiation temperatures below ∼1000°C (1273 K) and voids above ∼1000°C (1273 K), with a concomitant volume expansion. The thermal conductivity is greatly reduced by neutron irradiation. Data are available for mechanical properties including Young’s modulus, flexural strength, biaxial strength, and creep. Some useful results have followed from application of the Weibull model to strength measurements. The strength of single-phase beta-SiC is barely affected by neutron irradiation, but the strength of material containing excess silicon may be seriously reduced after irradiation. SiC has excellent resistance to oxidation as long as a surface film of silica is maintain...

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