Abstract
A low/negative magnetic shear profile is maintained in
the Joint European Torus in a plasma target with plasma
current of 2.4 MA using 2.2 MW of lower hybrid (LH) power
combined with neutral beam injection and ion cyclotron
radiofrequency heating. In this scenario, an internal
transport barrier (ITB) with time duration up to about 4
s is produced. The fraction of LH driven current is about
25% the total plasma current. During LH power
application, the layer with reversed shear q-profile can
be maintained in a suitable radial position to inhibit
the onset of turbulence, which might otherwise drive the
ITB to collapse. LH power could be used as a tool to
drive moderate amounts of noninductive off-axis current
and sustain high performance ITBs at high plasma current.
Original language | English |
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Pages (from-to) | 3205-3208 |
Journal | Physics of Plasmas |
Volume | 9 |
Issue number | 8 |
DOIs | |
Publication status | Published - 2002 |
MoE publication type | A1 Journal article-refereed |
Keywords
- Tokamak devices
- Tokamak
- JET
- plasma
- plasma toroidal confinement
- plasma transport processes
- plasma hybrid waves
- plasma beam injection heating
- plasma radiofrequency heating
- plasma turbulence