The ITER magnet systems: progress on construction

Abstract

Construction of the ITER magnet systems has been started at the end of 2007 following the signature of the first procurement arrangements (PA) for the toroidal field (TF) conductors. Six ITER members are involved in the share of the ITER magnet components and, to date, eighteen PA between the ITER Organization and six domestic agencies have been signed. Substantial progress towards full-scale construction has been achieved with the placement of the first large manufacturing contracts, the production of several tens of tons of advanced Nb 3 Sn and NbTi strand, and the setup of large cabling and jacketing facilities. The detailed design of the coils and support structures has also been finalized. The qualification of the fabrication processes for the TF coils and poloidal field (PF) coils has been initiated. The detailed design of the central solenoid (CS) coils is being developed. The design of the correction coils (CCs) with their support structures has been finalized, as well as for the TF gravity supports and clamps of the PF coils. The manufacture of prototypes of the feeder lines and current leads has been started, while ITER is in charge of the procurement of the required magnet instrumentation. This paper provides a progress report on the ITER magnet construction as per December 2010.

Compact steady-state tokamak performance dependence on magnet and core physics limits

“…To better understand the role of advanced superconductors on the achievable fusion performance versus aspect ratio, different combinations of maximum magnetic field at the magnet Btrueprefixmax and winding pack current density are considered as shown in figure 3. An important reference case is the ITER toroidal field coil set [27–29] with Btrueprefixmax≈12 T and J WP = 20 MAm −2 . Figure 3 a shows that for these magnet parameters the maximum allowable magnetic field cannot be reached for A ≤ 2.5 due to space constraints on the inboard TF magnet.…”

Conceptual design of the cryogenic system and estimation of the recirculated power for CFETR

“…The structural overview and cross-sectional dimensions of the CFETR magnet system are shown in figure 1. Since CFETR in phase I is an ITER-like tokamak except for the additional breeding blanket, and all the coils (TF, PF, CS and CC) of CFETR share a similar design philosophy and use the same superconducting conductors as their ITER counterparts [13], the weight of the CFETR coils can be extrapolated from the corresponding ITER coils [14]. Comparing the volume of a TF winding pack (structure) of CFETR and one of ITER, their ratio is 1.07 (1.05).…”

ITER project and fusion technology

“…However, further development and optimization of the manufacturing technologies in terms of technical risk mitigation and cost reduction are issues to be explored in the initial phase of the construction activities. This is particularly important for the TF coils because of their unprecedented scale, which is three times larger than the TF model coil, and stringent requirements; therefore, a variety of R&D activities have been initiated in EU and Japan for the TF magnet mass production [28].…”