Ion cyclotron heating of JET D-D and D-T optimized shear plasmas
The unique roles played by ICRH in the preparation, formation and sustainment of internal transport barriers in high fusion performance JET optimized shear experiments using the Mark II poloidal divertor are discussed. Together with LHCD, low power ICRH is applied during the early ramp-up phase of the plasma current, 'freezing in' a hollow or flat current density profile. In combination with up to ~20 MW of NBI, the ICRH power is stepped up to ~6MW during the main low confinement heating phase.
Bibliographic Reference: Article: Nuclear Fusion, 39 (1999)3, 389-405
Record Number: 199911572 / Last updated on: 1999-11-13
Original language: en
Available languages: en