Abstract
The free-boundary equilibrium code VEQ provides equilibrium data that are used by the Tokamak Simulation Code (TSC) in designing and analyzing the poloidal-field (PF) system for the Compact Ignition Tokamak (CIT). VEQ serves as an important design tool for locating the PF coils and defining coil current trajectories and control systems for the TSC. VEQ and its role in the TSC analysis of the CIT PF system are described.
| Original language | English (US) |
|---|---|
| Pages | 898-904 |
| Number of pages | 7 |
| State | Published - 1989 |
| Externally published | Yes |
| 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