Overview of material migration and erosion experiments in the full-tungsten WEST tokamak during Phase 1 and Phase 2 operations
Abstract
Abstract This paper gives an overview of erosion and migration studies of tungsten (W) in the WEST tokamak during its Phase 1 (2016–2021) and Phase 2 (from 2022) experimental campaigns with a focus on plasma-facing components (PFCs) at the divertor. In Phase 1, gross erosion of PFCs is in line with observations from other major fusion devices and attributed to low- Z impurities in the plasma. In addition, a strong asymmetry is observed between the high- (inner) and low-field (outer) side divertor targets, in favour of the inner side. Net erosion at rates of
Fields of Study & Subjects
Fusion materials and technologies
Magnetic confinement fusion research
Vacuum and Plasma Arcs
Publication details
- Journal / source
- Nuclear Fusion
- Publisher
- IOP Publishing
- Volume
- 66
- Issue
- 8
- Pages
- 086041–086041
- Publication date
- 2 July 2026
- Language
- EN