Divertor in a fusion reactor is exposed to a high surface heat flux during its operation due to plasma fluence. For testing the different divertor configurations, an experimental fusion tokamak will be built in Frascati in Italy, which will allow testing of different plasma scenarios and divertor configurations. In this master thesis thermal loads, stresses and deformations in plasma-facing divertor components have been analysed. High stresses are expected due to high thermal loads and also material yielding can occur in non-structural components. The main objective of this thesis is to predict displacements and stresses in the components using numerical simulations as well as validation of stresses in critical cross-sections with the use of standardized criteria of structural design of components. At first, the geometry was prepared, then the meshes for the whole and small models together with computational setup were created using the ANSYS and ABAQUS software. In the first part, the thermo-hydraulic simulations were performed to get temperature distribution, which were used as a temperature boundary condition in thermo-mechanical analysis. It was found, that structural components withstand the foreseen loads and also yielding occurred in some non-structural components.
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