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