Abstract
The physics parameters and operational modes of the CIT (Compact Ignition Tokamak), are set by a combination of detailed analysis and extrapolation from the existing tokamak database, are described. Some of the innovations being incorporated into the CIT design include sweeping of the separatrix across the divertor plates to spread the heat load, two-timescale radial position control utilizing both internal and external poloidal-field (PF) coils, optimized plasma shape control using a digital controller, and fusion burn control by modulating the heat source. Models of disrupting plasmas, developed to compute structural loads, are described. The models include the effects of induced currents in the plasma halo region in which field lines intersect the vessel walls.
| Original language | English (US) |
|---|---|
| Pages | 1265-1270 |
| Number of pages | 6 |
| State | Published - 1989 |
| Event | Proceedings - IEEE Thirteenth Symposium on Fusion Engineering Part 2 (of 2) - Knoxville, TN, USA Duration: Oct 2 1989 → Oct 6 1989 |
Conference
| Conference | Proceedings - IEEE Thirteenth Symposium on Fusion Engineering Part 2 (of 2) |
|---|---|
| City | Knoxville, TN, USA |
| Period | 10/2/89 → 10/6/89 |
All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering