Abstract
The Tokamak Fusion Test Reactor (TFTR) employs feedback control systems for four plasma parameters, i. e. for plasma current, for plasma major radius, for plasma vertical position, and for plasma density. The plasma current is controlled by adjusting the rate of change of current in the Ohmic Heating coil system. The plasma position is controlled by adjusting the currents in Equilibrium Field and Horizontal Field coil systems, which respectively determine the vertical and radial external magnetic fields producing J X B forces on the plasma current. Plasma density is controlled by adjusting the amout of gas injected into the vacuum vessel.
| Original language | English (US) |
|---|---|
| Pages (from-to) | 1807-1812 |
| Number of pages | 6 |
| Journal | Fusion Technology |
| Volume | 8 |
| Issue number | 1 pt 2(B) |
| DOIs | |
| State | Published - 1985 |
| Event | Proc of the 6th Top Meeting on the Technol of Fusion Energy - San Francisco, CA, USA Duration: Mar 3 1985 → Mar 7 1985 |
All Science Journal Classification (ASJC) codes
- General Engineering