The performance on plasma of the antennas of the proposed ITER ICRF system is evaluated by means of the antenna 24 × 24 impedance matrix provided by the TOPICA code and confirmed and interpreted by the semi-analytical code ANTITER II (summarized in an appendix). From this analysis the following system characteristics can be derived: (1) a roughly constant power capability in the entire 40–55 MHz frequency band with the same maximum voltage in the eight feeding lines is obtained for all the considered heating and current drive phasings on account of the broadbanding effect of service stubs. (2) The power capability of the array significantly depends on the distance of the antenna to the separatrix, the density profile in the scrape-off layer (SOL) and on the strap current toroidal and poloidal phasings. The dependence on phasing is stronger for wider SOL. (3) To exceed a radiated power capability of 20 MW per antenna array in the upper part of the frequency band, with a separatrix–wall distance of 17 cm and a conservative short decay plasma edge density profile, the system voltage stand-off must be 45 kV and well chosen combinations of toroidal and poloidal phasing are needed. (4) On account of the plasma gyrotropy and of poloidal magnetic field, special care must be taken in choosing the optimal toroidal current drive and poloidal phasings. The ANTITER II analysis shows furthermore that important coaxial and surface mode excitation can only be expected in the monopole toroidal phasing, that strong wave reflection from a steep density profile significantly reduces the coupling even if the separatrix is closer to the antenna and that the part of the edge density profile having a density lower than the cut-off density pertaining to the considered phasing does not significantly contribute to the coupling.

Intermittent convective transport has been investigated in the edge and the scrape-off layer (SOL) of TEXTOR using Langmuir probe signals. The probability distribution function (PDF) of the density fluctuations and the turbulence-induced flux are all positively skewed, while a Gaussian shape is recorded for the negative fluctuations. The deviation of the signals from Gaussian statistics clearly increases from the plasma edge to the SOL. Conditional averaging reveals that in the SOL region the waveform of intermittent structures is asymmetric in time and the burst events move radially outwards with E θ × B T /B 2 velocities of ∼450 m s −1 . It is found that the large burst fluctuations ( 2.5 × rms) account for nearly 40% of the total transport in the SOL. Statistics of the waiting-time between successive bursts indicate that the PDF of the time interval follows a Poisson-distribution for small-duration events (selected by size 2.5×rms) and changes into a power-law form for larger ones. Moreover, the intermittency density fluctuation data clearly show self-similar characters and long-range time correlations through the presence of (1) sandpile-like frequency spectra and existence of the f −1 region; (2) a long tail in the autocorrelation function and (3) Hurst exponents H > 0.5 from R/S analysis, suggesting a possible role of avalanche-like transport in the turbulence intermittency.

A model for the transition to the radiatively improved (RI) mode triggered in tokamaks by seeding of impurities is proposed. This model takes into account that with increasing plasma effective charge the growth rate of the toroidal ion temperature gradient (ITG) instability, considered nowadays as the dominant source of anomalous energy losses in low-confinement (L) mode, decreases. As a result the plasma density profile peaks due to an inward convection generated by trapped electron turbulence. This completely quenches ITG induced transport and a bifurcation to the RI mode occurs. Conditions necessary for the L-RI transition are investigated.

Positive radial electric fields have been created at the edge of the TEXTOR tokamak plasma using an electrode. The electric field induces a thin (δr ∼ 1.5 cm), E × B driven layer at the edge rotating poloidally at 12-20 km/s and featuring high shear. Concomitant changes in the density and poloidal electric field fluctuations and their cross-phase in the shear layer result in suppression of radial turbulent particle transport, even at low radial electric field strength. Temperature fluctuations are reduced, resulting in diminished turbulent heat flux. As turbulent particle transport is quenched, the particle confinement time τp increases by a factor of 2 and the energy confinement time τE by 20%. Turbulent transport accounts for ∼50% of the total particle flux. Both the cross-phase and the density fluctuations are sensitive to the sign of ∇Er.

The ITER Ion Cyclotron Heating and Current Drive system will deliver 20MW of radio frequency power to the plasma in quasi continuous operation during the different phases of the experimental programme. The system also has to perform conditioning of the tokamak first wall at low power between main plasma discharges. This broad range of reqiurements imposes a high flexibility and a high availabiUty. The paper highlights the physics and design reqiurements on the IC system, the main features of its subsystems, the predicted performance, and the current procurement and installation schedide.