Abstract
In 2003, the performance of the 'hybrid' regime was successfully
validated in JET experiments up to βN = 2.8 at low
toroidal field (1.7 T), with plasma triangularity and normalized Larmor
radius (ρ*) corresponding to identical ASDEX Upgrade
discharges. Stationary conditions have been achieved with the fusion
figure of merit ( H_{89}.\beta_N/q_{95}^{2} ) reaching 0.42 at
q95 = 3.9. The JET discharges show similar MHD, edge and
current profile behaviour, when compared with the ASDEX Upgrade. In
addition, the JET experiments have extended the hybrid scenario
operation at higher toroidal field of 2.4 T and lower ρ*
towards the projected ITER values. Using this database, transport and
confinement properties are characterized with respect to the standard
H-mode regime. Moreover, trace tritium has been injected to assess the
diffusion and convective coefficients of the fusion fuel. The
maximization of confinement and stability properties provides, to this
scenario, a good probability of achieving a high fusion gain at reduced
plasma current for durations of up to 2000 s in ITER.
Original language | English |
---|---|
Pages (from-to) | 626-634 |
Journal | Nuclear Fusion |
Volume | 45 |
Issue number | 7 |
DOIs | |
Publication status | Published - 1 Jul 2005 |
Externally published | Yes |