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Study on the mechanical properties and thermal conductivity of silicon carbide-, zirconia- and magnesia aluminate-based simulated inert matrix nuclear fuel materials after cyclic thermal shock

Materials ScienceMaterials EngineeringNuclear CeramicCeramic Matrix CompositeEngineeringMechanical PropertiesCeramic MaterialMechanical EngineeringCyclic Thermal ShockThermodynamicsHeat TransferThermal EngineeringThermal ConductivityThermal Properties