WEST is an MA class superconducting, actively cooled, full tungsten (W) tokamak, designed
to operate in long pulses up to 1000 s. In support of ITER operation and DEMO conceptual …

METIS is a numerical code aiming at fast full tokamak plasma analyses and predictions. It
combines 0D scaling-law normalised heat and particle transport with 1D current diffusion …

A two-equation model to self-consistently determine cross-field fluxes in the edge and
scrape-off layer (SOL) region of diverted plasma is used to complete 2D mean-field edge …

Materials for the next generation of electric power infrastructure will be subject to harsh
service environments featuring extreme levels of stress, temperature, irradiation, and …

Pulsed injections of boron carbide granules into Wendelstein 7-X stellarator (W7-X) plasmas
transiently increase the plasma stored energy and core ion temperatures above the …

Three identical new WEST ion cyclotron resonance heating (ICRH) antennas have been
designed, assembled then commissioned on plasma from 2013 to 2019. The WEST ICRH …

The net erosion and deposition patterns in the inner and outer divertor of WEST were
determined after different experimental campaigns (C3 and C4) of the first operational phase …

The design of the Langmuir probes for the lower divertor of the WEST tokamak is presented,
in which uncooled, tungsten-coated graphite targets were installed for the first phase of …

Since tungsten (W) has been selected as material for the ITER divertor target the knowledge
of the emissivity in the infrared (IR) wavelength range becomes mandatory. A dedicated …

Gross and net erosion of tungsten (W) and other plasma-facing materials in the divertor
region have been investigated in deuterium (D) and helium (He) plasmas during dedicated …