Parametric Structural Design of GEN IV Canadian Super Critical Water Reactor (SCWR)

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A parametric solid mechanics model for the design of the reactor core of the GEN IV Canadian Supercritical Water Reactor (SCWR)will be developed to predict transient temperature, displacement, strain and stress fields in the reactor core in the early design stages. The model would be based on 3D transient FEM thermal-stress analysis for normal operation, startup, shut-down, upset and accident conditions. The model would be coupled to the best available estimates of fluid flow velocities, pressures, temperatures and densities. Temperature and if needed microstructure dependent properties would be used. The model would include non-linear contact elements for thermal and stress analysis based on the best available knowledge and if not available, sensitivity studies would be helpful, of the gap width, surface roughness, gap material of each contact interface.