Abstract
Transport calculations illustrate that the lower hybrid
current drive (LHCD) and off-axis electron cyclotron
current drive (ECCD) are the only preheating methods that
can create a wide, deeply reversed q-profile, i.e. large
negative magnetic shear, on the JET tokamak. Off-axis
neutral beam injection (NBI) and off-axis ion cyclotron
resonance heating (ICRH) preheating yields a weakly
reversed q-profile (small negative magnetic shear),
whereas NBI and ICRH on-axis heating as well as ohmic
preheating produce a monotonic q-profile in the
preheating phase. Here, on-axis power deposition and
current drive refers to heating and current drive at or
close to magnetic axis and correspondingly, off-axis
refers to heating and current drive deposited typically
around the half minor radius (r/a = 0.3-0.6). The results
on LHCD, ICRH and ohmic preheating have been verified in
the recent JET experiments. The current drive efficiency
scan shows that in the case of LHCD, ECCD and off-axis
NBI, the driven current is absolutely crucial to obtain a
reversed q-profile and to modify the current profile
evolution drastically in the preheating phase. Taking
into account only the direct electron heating effect,
LHCD does not create a reversed q-profile. The timing
scans indicate that the radial location of qmin at the
end of the preheating phase is generally quite
insensitive to the start time of the preheating, once
started 0-2 s after the plasma initiation if the method
relies upon the driven current. On the other hand,
methods relying only upon electron heating are very
sensitive to that. In both cases, the magnitude of the
negative magnetic shear, however, seems to be very
sensitive to the start time of the preheating.
Original language | English |
---|---|
Pages (from-to) | 1181-1202 |
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
- magnetic shear