In nuclear fusion devices such as the Wendelstein 7-X (W7-X) stellarator, the divertor is a critical component responsible for particle and heat exhaust. It consists of multiple target elements (tiles) that intercept plasma particles and must withstand extremely high thermal loads, up to 20 MW/m^2. The divertor geometry is designed to spread the heat flux over a larger surface while maintaining structural integrity under severe operating conditions. This thesis investigates the thermo-hydraulic performance of a simplified version of a divertor tile based on Triply Periodic Minimal Surfaces (TPMS), realized through Additive Manufacturing (AM). TPMS geometries offer a promising solution for enhancing convective heat transfer while minimizing pressure losses.