The magnet system of the stellarator fusion device Wendelstein 7-X (W7-X) is composed of three different groups of coil systems. The main magnetic field is created by a superconducting magnet system that is accompanied by two sets of normal conducting coil groups, the trim coils positioned outside of the cryostat and the control coils inside the plasma vessel.
The control coil system consists...
The fabrication of the modules for the ITER Central Solenoid (CS) is in progress at General Atomics (GA) in Poway, California, USA. This purpose built facility has been established with the requisite tools and machines to fabricate the seven 110 tonne CS modules (six required plus one spare). GA’s project responsibility is completing the fabrication design, developing and qualifying the...
CFETR (China Fusion Engineering Test Reactor) concept design work was started in 2012. It is developed in two stage. CFETR-Phase I is designed with major radius R=5.7m, minor radius a=1.6m and magnetic field at plasma region BT=4-5T. 16 toroidal field coils and 6 central solenoid coils were designed using Nb3Sn CICC conductor with maximum operation current of 64 kA and 50 kA, respectively....
In the framework of prospective activities for a demonstration power plant, DEMO will be the next step for fusion energy following ITER tokamak. Some of the key design top-level questions can be addressed using macroscopic system-level codes. Those system codes aim to model the whole plant with all its subsystems and identify the impact of their interactions on the design choices. The SYCOMORE...
The central solenoid modules for the ITER project are powered by a complex system of busbars, feeders, lead extensions, electrical joints and integral coil terminals. The leads carry time-varying module currents through predominantly poloidal fields, and thus develop substantial toroidally-oriented, cyclic, Lorentz loads. The support of such loading requires a robust structure which can...
The US Domestic Agency is one of the six suppliers of the Toroidal Field (TF) conductor for ITER. In order to qualify conductors according to the ITER requirements, we prepared or provided to the Swiss Plasma Center (SPC) eight test articles, sixteen conductors total, that were tested in the SULTAN facility at SPC in the ITER relevant conditions. We also fully characterized the strands that...
