Stability margins of elongated plasmas in TCV and implications for ITER
During the operation of the TCV tokamak an extremely wide variety of plasma shapes has been controlled with elongation's up to ??= 2.5, beyond the present designs for ITER. Summarizes the operational regime explored by TCV, using a representative sample of discharges. Growth rates for these discharges were estimated using a rigid current displacement model. The Poloidal Field coil voltages required for plasma control, using the slow external coils and the fast internal coils have also been inspected.
Bibliographic Reference: Article: 26th EPS Conference on Controlled Fusion and Plasma Physics, (1999)
Record Number: 199911079 / Last updated on: 1999-08-06
Original language: en
Available languages: en