The Divertor Tokamak Test (DTT) facility, under construction at ENEA Frascati, is an Italian tokamak project conceived to address the plasma exhaust challenge, a key obstacle identified in the European Fusion Roadmap toward the realisation of DEMO. Among its critical subsystems, the Thermal Shield (THS) is a barrier against radiative and conductive heat transfer from the warm tokamak components to the superconducting magnet system operating at 4.5 K. This thesis presents a thermo-mechanical finite element analysis of the DTT Port Thermal Shield (PTS), for structural integrity and to inform design optimisation. The state-of-the-art, ITER and JT-60SA thermal shields are reviewed, whose design philosophies and analytical strategies provide the methodological foundation for the present work.