Silicon carbide (SiC) and SiC matrix composites (SiCf/SiC) are being investigated as potential fuel cladding materials for advanced PWRs in order to improve the safety of nuclear power plants. The conceptual design of multi-layered SiC cladding (consisting of a monolithic SiC layer, SiCf/SiC composite layer and a monolithic SiC coating layer) has been investigated to meet the fuel requirements of both the strength and impermeability. A stress distribution model of the triple-layered SiC is developed on the basis of the theory of thermo-elasticity mechanics, taking radial temperature gradient and swelling effects into account as well. The heat transferring behavior of the cladding is investigated by analyzing the temperature distribution under steady conditions. Finite Element Analysis (FEA) code ANSYS is used to obtain the stress and temperature nephogram of multi-layered SiC fuel cladding under simulated steady conditions. Compared with the results of ANSYS, the stress distribution model and temperature distribution is validated.

Volume Subject Area:
Nuclear Fuel and Material, Reactor Physics and Transport Theory
Topics:
Cladding systems (Building), Pressurized water reactors, Stress analysis (Engineering), Fuels, Composite materials, Finite element analysis, Stress concentration, Temperature distribution, Coating processes, Coatings, Conceptual design, Heat, Nuclear power stations, Safety, Silicon, Stress, Temperature, Temperature gradient, Thermoelasticity
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