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 (H89.βN/q295) 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 |
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Pages (from-to) | 626 - 634 |
Number of pages | 9 |
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