Abstract
In JET discharges where lower hybrid heating and current
drive (LHCD) is applied early during the current ramp, a
region of the plasma with zero current density is formed
near the axis. At the boundary of this region the current
density is large and B increases rapidly over a small
distance. In the central region the safety factor, q, is
effectively infinite, but this falls steeply in the
boundary region. Outside the boundary region q reaches a
minimum, where the magnetic shear sr/q (dq/dr) becomes
zero. The formation of this region of zero current is
dependent on both the heating and the current drive
effects of the LHCD. When LHCD is switched off the
current profile begins to relax towards the resistive
peaked current distribution of fully inductive tokamak
operation. If LHCD is not used in the current rise then
these current profiles are not established. Although the
physical mechanism exists to drive the central plasma
current below zero, in most cases it appears to be
prevented from going negative. At least one MHD mechanism
has been identified which could be responsible for this.
The presence of the zero central current is closely
linked to the periodic relaxation events seen in these
discharges. In these discharges, internal transport
barriers have been observed with additional heating
powers substantially below the values required to obtain
barriers in monotonic q profile cases.
Original language | English |
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Pages (from-to) | 1105-1125 |
Journal | Plasma Physics and Controlled Fusion |
Volume | 44 |
Issue number | 7 |
DOIs | |
Publication status | Published - 2002 |
MoE publication type | A1 Journal article-refereed |
Keywords
- JET
- plasma
- fusion energy
- fusion reactors
- tokamak
- internal transport barriers
- lower hybrid current drive