Conveners
THU-OR4-202 Fusion Magnets II
- Laura Savoldi (Politecnico di Torino)
- Hideki Kajitani (National Institutes for Quantum and Radiological Science and Te)
Presentation materials
The SPARC Toroidal Field Model Coil (TFMC) Project seeks to design, build, and test in a two-year time period a first-in-class, high-field, large-scale fusion magnet using Rare Earth Yttrium Barium Copper Oxide (REBCO) superconductor. The principal objective of the project is to retire the operational and manufacturing risks of REBCO toroidal field magnet technology at-scale for the SPARC...
The plasma confinement of the International Tokamak Experimental Rector (ITER) is provided by the magnetic field generated by 18 toroidal field (TF) coils while 6 poloidal field (PF) and 6 central solenoid coils have the function to drive, shape and pre-heat the plasma. Fusion for Energy (F4E), the European Domestic Agency for ITER, is responsible for the supply of 10 TFC and 5 PFC to the ITER...
QST, as Japan Domestic Agency (JADA) in ITER, has responsibility to procure 9 ITER Toroidal Field (TF) coils and all 19 TF Coil Cases (CC). The 9 TF coils are procured by two suppliers to accelerate their production. In the first supplier, four TF coils have been fabricated and three of them has been delivered to the ITER site. On the other hand, the second supplier fabricates the forth TF...
The Central Solenoid (CS) is a key element of the ITER Magnet system, including six identical coils, called modules, assembled together to form a 4 m outer diameter, 13 m high solenoid. It is a superconducting magnet, using a 45 kA Nb3Sn conductor internally cooled by circulation of supercritical helium at 4.5 K with a peak field up to 13 T. It is enclosed inside a structure providing...
The poloidal magnetic field of ITER is provided by 6 Niobium–Titanium (NbTi) coils mainly for plasma shaping and position control. The fabrication of the two lower coils PF6 from China ASIPP and PF5 from European F4E has been completed and the coils installed in the bottom of the Tokamak pit in 2021. This paper presents the challenge of the manufacturing process, which involves manufacturing...
The ITER Poloidal Field (PF) coils consists of six coils, PF1 through PF6 that serve to stabilize the position and control the shape of the plasma in the tokamak. PF1 coil, which is one of six PF coils, is procured by the Russian domestic agencies (RFDA) under procurement arrangement between ITER and RFDA. After signing the PAs, for the supplier of PF1 Coil, RFDA has selected Efremov institute...
The Wendelstein 7-X (W7-X) stellarator equipped with a large cryogenic magnet system (MS) [1] has been extended for the long pulse operation at the Max-Planck-Institute for Plasma Physics in Greifswald, Germany. If the main focus of mechanical engineers during first two experimental campaigns was on the static structural strength of the MS, the issue of component cyclic behavior is addressed...
