Plasma start-up is typically achieved manipulating poloidal magnetic fields, gas injection
and possibly auxiliary heating. Model-based design techniques have been gaining …

Tokamaks are the most promising devices to prove the feasibility of energy production using
nuclear fusion on Earth which is foreseen as a possible source of energy for the next …

Abstract The Divertor Tokamak Test (DTT) facility is equipped with auxiliary heating systems
in order to be able to load the divertor with a power flux relevant to study the power exhaust …

The as-built stiffness in the ITER central solenoid (CS) modules (CSM1 thorough to CSM4
are currently manufactured) determines the range of vertical compression forces that can be …

Power exhaust is a critical challenge for spherical tokamak reactors, making the design,
optimisation and control of advanced divertor configurations crucial. These tasks are greatly …

The Plant Electrical System (PES) of the European DEMOnstration fusion power plant
(DEMO), presently under conceptual design, shall supply power to the loads and deliver net …

Plasma initiation is an important phase in a tokamak discharge and its design and
optimization is getting more and more attention in view of the operation of large tokamaks …

Magnetic control for plasma initiation in a toka-mak is mainly achieved with a feedforward
voltage control action pre-computed on the basis of a model of the plant. In medium/large …