The ITER magnet procurement is now well underway. The magnet systems consist of 4
superconducting coil sets (toroidal field (TF), poloidal field (PF), central solenoid (CS) and …

Abstract The Chinese Fusion Engineering Test Reactor (CFETR) superconducting magnet
system was designed by the National Integration Design Group for Magnetic Confinement …

Abstract The Divertor Tokamak Test (DTT) facility, construction starting at Frascati, Italy, is
designed to test different solutions for divertor in view of DEMO. A preliminary analysis of the …

This paper presents a multi-machine, multi-parameter scaling law for the n= 2 core resonant
error field threshold that leads to field penetration, locked modes, and disruptions. Here, n is …

We have designed in-vessel coils for a correction of magnetic error fields in JT-60SA. In
order to design the in-vessel coils, namely, error field correction coils (EFCCs), error fields …

The tracking of magnetic field lines can be very expensive, in terms of computational burden,
when the field sources are numerous and have complex geometries, especially when …

This paper presents the subtleties of obtaining robust experimental scaling laws for the core
resonant error field threshold that leads to field penetration, locked modes, and disruptions …

The fusion plasma is sensitive to the penetration of the toroidal mode numbers 𝑛 harmonic
components of the error fields (EFs), and the toroidal mode components of the EFs are …

Homogeneity of the toroidal magnetic field is a critical aspect of the tokamak fusion device. It
is affected by the design of toroidal magnetic field coils and their manufacturing and …

The present paper is focused on the sensitivity analysis of the diamagnetic sensor
measurements of ITER against several kinds of error sources, with the aim of compensating …