The ITER Tokamak will be the largest magnetic confinement fusion device ever built. Confinement will be achieved by a combination of magnetic fields generated by a plasma current of 15MA and externally applied toroidal field of 5.4T. The toroidal field will be generated in 18 superconducting coils which must be protected from the radiation from the burning plasma. This paper describes the radiation transport studies that have been conducted to examine the shielding properties of the components which protect the coils and summarizes the principles which have been developed to optimise the shielding.