A three dimensional (3-D) shielding analysis of the International Ther
monuclear Experimental Reactor (ITER) has been performed with the aim
of calculating the nuclear heating on the magnet system, correlating i
t to the existing vertical and horizontal ports. When these openings a
re left unshielded, more than 50 kW are calculated for the upper half
of Toroidal Field Coil system and two of the Poloidal Field Coils. A s
imple plug, with same thickness as of the vacuum vessel can lower the
heating to meet the imposed requirements.