Abstract
The International Thermonuclear Experimental Reactor (ITER) tokamak superconducting magnet system is designed to confine and control a 21 MA plasma during the various phases of pulsed operation. The central solenoid (CS) and poloidal coils are independently powered with currents that cycle during the pulse. The reference magnet system design includes a layer-wound 12 meter long CS that only allows one current density distribution. In an alternative design, which shows advantages for plasma shape control, the CS consists of three independently powered modules. In this paper the configurations are compared from the structural point of view.
| Original language | English (US) |
|---|---|
| Pages | 681-684 |
| Number of pages | 4 |
| State | Published - 1998 |
| Externally published | Yes |
| Event | Proceedings of the 1997 17th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2) - San Diego, CA, USA Duration: Oct 6 1997 → Oct 10 1997 |
Other
| Other | Proceedings of the 1997 17th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2) |
|---|---|
| City | San Diego, CA, USA |
| Period | 10/6/97 → 10/10/97 |
All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering