We use an integrated modeling workflow with the transport code ASTRA coupled with the quasi-linear transport model TGLF-SAT2, the neoclassical model NCLASS, the FACIT model for the neoclassical impurity transport and the IMEP routines for the pedestal calculations, in order to predict the evolution of the plasma profiles for the Divertor Tokamak Test facility (DTT) tokamak main scenarios. The simulations cover the whole confined plasma radius, up to the separatrix, and the time evolution of the plasma including the early phase in limiter configuration, the whole current ramp-up phase in L-mode divertor configuration, the L–H transition and part of the stationary H-mode phase. Six fields are predicted, i.e. the ion and electron temperatures, the electron density, two impurity densities and the plasma current. The simulations indicate that the main DTT scenarios are within the technical capabilities of the machine. They also indicate that the DTT full power, full current, full field scenario will be able to operate in H-mode with a duration of the flat-top phase of the order of ∼ 30 s, and plasma parameters allowing a core-edge integrated study of the power exhaust, which is the main mission of the device. The simulations show also a strong flexibility of the DTT plasmas, that allows DTT to study reactor-relevant conditions unexplored by existing tokamaks.
This paper presents an integrated modeling workflow to predict the evolution of plasma profiles in the Divertor Tokamak Test (DTT) facility. The simulations cover the entire confined plasma radius and the time evolution, including the early limiter phase, current ramp-up, L-H transition, and H-mode operation. The results indicate that the DTT will be able to operate in H-mode with a long flat-top phase, allowing the study of power exhaust, which is the main mission of the device.