Abstract
Fast wave current drive (FWCD) experiments have been performed in JET
plasmas with electron internal transport barriers produced with LHCD.
Because of a large fraction of parasitic absorption, owing to weak
single pass damping, the inductive nature of the plasma current and the
interplay between the RF-driven current and the bootstrap current only
small changes are seen in the central current profiles. The measured
difference in the central current density for co- and counter-current
drive is larger than the response expected from current diffusion
calculations, but smaller than the driven currents, suggesting a faster
current diffusion than that given by neo-classical resistivity. A large
fraction of the power is absorbed by cyclotron damping on residual 3He
ions while a significant fraction appears not to have been deposited in
the plasma. The strong degradation of heating and current drive occurs
simultaneously with strong increases in the Be II and C IV line
intensities in the divertor. The degradation depends on the phasing of
the antennas and increases with reduced single pass damping which is
consistent with RF-power being lost by dissipation of rectified
RF-sheath potentials at the antennas and walls. Asymmetries in direct
electron heating, lost power and production of impurities, fast ions and
gamma-rays are seen for co- and counter-current drive. These
differences are consistent with the differences in the absorption on
residual 3He ions owing to the RF-induced pinch. Effective
direct electron heating, comparable to the indirect electron heating
with H-minority heating, occurs for dipole phasing of the antennas
without producing a significant fast ion pressure and with low impurity
content in the divertor plasma.
Original language | English |
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Pages (from-to) | 706 - 720 |
Number of pages | 15 |
Journal | Nuclear Fusion |
Volume | 45 |
Issue number | 7 |
DOIs | |
Publication status | Published - 2005 |
MoE publication type | A1 Journal article-refereed |
Keywords
- JET
- plasma
- fusion energy
- fusion reactors
- ITER
- Tokamak
- internal transport barriers