The design of a breakdown scenario in a modern tokamak requires the optimization of
Poloidal Field coils voltages and currents to guarantee a desired electric field and a low …

The information coming from the diagnostic system is of vital importance for the correct
functioning of many electromagnetic devices. In particular, for nuclear fusion devices, the …

A new boundary reconstruction procedure is presented and validated against ITER nominal
equilibria. An approximation of the plasma with an equivalent filamentary current model is …

The paper presents a method to identify the plasma magnetic contour in fusion machines,
when eddy currents are present in the conducting structures surrounding the plasma. The …

Purpose–Inverse problems are usually ill‐conditioned, requiring the adoption of
regularization techniques to obtain reliable results. The choice of the regularization method …

The problem of reconstructing the current profile in regions not directly accessible by
sensors is tackled, with reference to current profile reconstruction in cable in conduit …

The research in the thermonuclear fusion area has entered the design phase of ITER, the
first experimental Tokamak reactor. In the ITER device, the plasma shape and position are …

In this paper, the Proper Orthogonal Decomposition approach is exploited to obtain a
Reduced Order Model for the plasma magnetic equilibrium problem, described by the Grad …

The paper proposes an approach for the identification of magnetic surfaces, and particularly
of the Last Closed Magnetic Surface, in nuclear fusion devices. The proposed method is …

In fusion devices, the accurate reconstruction of the boundary location and shape from
magnetic diagnostics is of paramount importance for the efficient control of the plasma …