Pour les actualités en français, voir la page News in French.

Toroidal field coils

First ITER magnet arrives this year

Please see the gallery below for a full update on manufacturing progress.

QST_firstTF_coldtest_396.JPG
The first Japanese winding pack was cold tested in October in this purpose-built cryogenic chamber at Mitsubishi. In a final step before shipment to ITER, the winding pack will be inserted in its structural case.

Eleven years after completing the signatures on documents specifying technical and quality control requirements for the supply of nine toroidal field coils, the Japanese Domestic Agency is overseeing the last, spectacular sequences on its first production unit.

 
The toroidal field coils are the ITER magnets responsible for confining the plasma inside the vacuum vessel using high-performance, internally cooled superconductors called CICC (cable-in-conduit) conductors. Following the completion of the single largest superconductor procurement in industrial history, fabrication of the final coils is proceeding in Japan (9 toroidal field coils plus 10 coil structures to be sent to Europe) and Europe (10 toroidal field coils). Each coil is made up of a superconducting winding pack and surrounding stainless steel coil case.
 
The list of applicable superlatives is long—the toroidal field coils are the largest and most powerful superconductive magnets ever designed, with a stored magnetic energy of 41 GJ and a nominal peak field of 11.8 T. Together they weigh in at over 6,000 tonnes including superstructure, representing 60 percent of the magnetic array on the machine and over one-fourth of the Tokamak's total weight. They require 4.57 km of conductor per coil wound into 134 turns in the central core, or winding pack, of the magnet. And they have required the longest procurement lead-time of any ITER component, with six out of seven ITER Members involved in the production of 500 tonnes of niobium-tin superconducting strand (100,000 km) required for the toroidal field superconducting cables.

 

all_tf_coil_cases_types_overview_tags.jpg
In the insert, the different elements of the toroidal field coils are shown: the superconducting winding pack (in green), and the inner (BP, AP) and outer (BU, AU) coil case sub-assemblies. QST—with the cooperation of Mitsubishi Heavy Industries, Ltd., Mitsubishi Electric Corporation, Hyundai Heavy Industries, and Toshiba Energy Systems & Solutions Corporation—will supply 9 toroidal field coils (assembly of winding packs and coil structures) plus another 10 coil structures to the ITER Project.
The first winding pack to come off the assembly line in Japan is currently undergoing final inspection by the industrial consortium Mitsubishi Heavy Industries/Mitsubishi Electric Corporation. The final sequence of testing involved high voltage tests, helium leak tests, and finally cryogenic tests, during which the winding pack is inserted into a cryostat (see top photo) and cooled to 80 K (-193 ˚C) to confirm leak tightness. With the successful end of cold testing, the winding pack is now undergoing post-cold-test helium leak tests and high voltage tests and will soon be ready for assembly with its toroidal field coil case. Five other winding packs are in various stages of production.

The 200-tonne case assemblies are also in series production. After successful fitting tests early last year, two have been delivered to Europe for insertion activities and a third will arrive this month; another completed production unit will remain at Mitsubishi for the assembly of the Japanese coil that is due at ITER in 2019. The fitting tests are the most delicate stage in the coil case manufacturing process, demonstrating that sub-assemblies manufactured and welded at different factory sites can be successfully paired with gap tolerances as strict as 0.25 to 0.75 mm along 15-metre weld grooves.

Please see the gallery below for a full update on manufacturing progress.