The Central Solenoid Model Coil (CSMC) project of China Fusion Engineering Test Reactor (CFETR) began in 2014 and the purpose is to develop and verify the related manufacture technology of the larger-scalar superconducting magnet. The CICC (Cable-in-Conduit-Conductor) is chosen for CFETR CSMC as the best conductor type because of 12 T field and 1.5 m inner diameter design requirement. The...
After agreement on the general and detailed design of the JT-60SA TF coil system by all the Voluntary Contributors in the project, CEA, ENEA and F4E, the manufacturing phase was engaged. The French part including the supply of 9 + 1 spare of the 18 TF winding packs and their integration in casings was entrusted mid-2011 to Alstom (France), now General Electric. Years up to 2013 were devoted to...
In summer 2015 a new reference baseline is issued for the DEMO EUROfusion tokamak. Thereafter, the toroidal field (TF) coils have been updated with the new layout of the react-and-wind conductor proposed by the Swiss Plasma Center (SPC). Each TF coil consists of 12 single layers of graded Nb3Sn conductors connected in series by “invisible” inter-layer joints fully embedded in the winding pack....
July 2014 has seen the establishment of MIFI (Magnet Infrastructure Facilities for ITER), a collaboration agreement to provide technical and logistic support from CEA to ITER Magnet Division. The implementation of the agreement led to the creation of 4 laboratories in the areas of: High Voltage; Low Voltage and Instrumentation;Machining and Assembly; Insulation Manufacturing & Cryogenics. In...
It is important to achieve sufficiently low joint resistance (RJ), such as order of nano ohm, in ITER TF coils. However, a huge equipment is necessary to measure RJ at 4 K because of huge mass and size of TF coil. On the other hand, according to experiences by the authors, good RJ could be successfully achieved in ITER EDA model coils. In addition, severe process control is being done in ITER...
The Pre Compression Ring (PCR) is an important element of the ITER magnetic system since it improves the force distribution among the Toroidal Field magnets during plasma operation. An experimental campaign has been planned at Iter Organization (IO) to characterize the mechanical behaviour of the ring in a test rig able to simulate the ITER assembly conditions. In particular the testing...
National Institutes for Quantum and Radiological Science and Technology (QST) which has been Japan Atomic Energy Agency up to March 2016, as Japan Domestic Agency, has responsibility to procure 19 coil cases for ITER Toroidal Field Coils (TFCs) as in-kind components. The TFC Case is a large welded structure having a D-shape with a height of 16.5 m, a width of 9 m, and a weight of about 200...
The Poloidal Field (PF1) coil is one of six PF coils of the ITER magnet system. It represents a stack of eight double pancakes (DP). Each DP is wounded from niobium-titanium “cable-in-conduit” conductors (CICC). All DPs are connected into a single electric circuit using electrical joints, which have a ‘shaking hands’ configuration. The new joint design was agreed by the ITER Organization (IO)....
National Institutes for Quantum and Radiological Science and Technology (QST) has responsibility as Japanese domestic agency (JADA) to procure 9 Toroidal Field (TF) coils in the ITER project. The high mechanical and electrical reliabilities have to be ensured for the operation of the ITER for 20 years. For this objective, the Radial Plate (RP) structure is employed to avoid accumulating the...
The central solenoid (CS) model coil is being developed to verify the large-scalar superconducting coil manufacture technology for China Fusion Engineering Test Reactor (CFETR) in ASIPP (Institute of Plasma Physics). The CS model coil composed of Nb3Sn (inner and outer coils) and NbTi (upper, middle and lower coils) hybrid superconducting magnet can reach to 12 T maximum magnetic field. All of...