Abstract
The overall programme objective of ITER is to demonstrate the scientific and technologicalfeasibility of fusion power production for peaceful purposes. ITER would accomplish thisobjective by demonstrating controlled burn of deuterium tritium plasmas, andby demonstrating essential technologies (of a reactor) in an integrated system.The magnetic coils of ITER are all made of superconducting conductors. A comprehensiveresearch and development programme has been carried out to demonstrate the feasibility ofthe magnetic system. The major elements of this programme have been the construction ofthe toroidal field and central solenoid model coils. The testing of these model coils hasproduced all the necessary information to finalize the design of the ITER magneticsystem. In addition, a poloidal field conductor insert is being manufactured and willbe tested in 2006 at Naka (J) to confirm the design of the poloidal field coils.
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