High density internal transport barriers for burning plasma operation

A tokamak plasma with internal transport barriers (ITBs) is the best candidate for a steady ITER operation, since the high energy confinement allows working at plasma currents (I-P) lower than the reference scenario. To build and sustain an ITB at the ITER high density (>= 10(20) m(-3)) and largely dominant electron (e(-)) heating is not trivial in most existing tokamaks. FTU can instead meet both requests, thanks to its radiofrequency heating systems, lower hybrid (LH, up to 1.9 MW) and electron cyclotron (EC up to 1.2 MW). By the combined use of them, ITBs are obtained up to peak densities n(e0) > 1.3 x 10(20) m(-3), with central e- temperatures T-e0 approximate to 5.5 keV, and are sustained for as long as the heating pulse is applied (> 35 confinement times, tau(E)). At n(e0) 0.8 x 10(20) m(-3) T-e0 can be larger than 11 keV Almost full current drive (CD) and an overall good steadiness is attained within about one tau(E), 20 times faster than the ohmic current relaxation time. The ITB extends over a central region with an almost flat or slightly reversed q profile and q(min) approximate to 1.3 that is fully sustained by off-axis lower hybrid current drive. Consequent to this is the beneficial good alignment of the bootstrap current, generated by the ITB large pressure gradients, with the LH driven current. Reflectometry shows a clear change in the turbulence close to the ITB radius, consistent with the reduced e(-) transport. Ions (i(+)) are significantly heated via collisions, but thermal equilibrium with electrons cannot be attained since the e(-) -i(+) equipartition time is always 4-5 times longer than tau(E). No degradation of the overall ion transport, rather a reduction of the i(+) heat diffusivity, is observed inside the ITB. The global confinement has been improved up to 1.6 times over the scaling predictions. The ITB radius can be controlled by adjusting the LH power deposition profile that is affected mostly by the q value of the discharge, while the ITB strength can be varied through central EC heating. FTU experiments have shown that ITER-like e-ITBs are achievable.