Tokamak scenario development requires an understanding of the properties that determine
the kinetic profiles in non-steady plasma phases and of the self-consistent evolution of the …

The present DEMO breeding blanked design heat load capability is limited to≈ 1 MW/m 2
for steady state plasma loading, due to the specific requirements on high neutron irradiation …

Self-consistent transport simulation of ITER scenarios is a very important tool for the
exploration of the operational space and for scenario optimization. It also provides an …

Electron cyclotron resonance heating (ECRH)-assisted plasma breakdown is foreseen with
full and half magnetic field in ITER. As reported earlier, the corresponding O1-and X2 …

The present work demonstrates the capabilities of the transport code RAPTOR as a fast and
reliable simulator of plasma profiles for the entire plasma discharge, ie from ramp-up to ramp …

One of the three goals of the ITER project is to demonstrate fusion gain Q≥ 5 in steady-state
operation (SSO). A reassessment of the necessary conditions for Q≥ 5 SSO in ITER has …

Stable, high-performance operation of a tokamak requires several plasma control problems
to be handled simultaneously. Moreover, the complex physics which governs the tokamak …

To understand the L–H transition, one has to identify the modes to be stabilized at the edge
of L-mode plasmas, roughly from ρ= 0.7 to the last closed flux surface. To address this issue …

One of the main problems of fusion energy is to achieve longer pulse duration by avoiding
the premature reaction decay due to plasma instabilities. The control of the plasma …

Previous studies of DIII-D L-mode plasmas have shown that a transport shortfall exists in that
our current models of turbulent transport can significantly underestimate the energy transport …