Abstract
A dedicated series of L-mode deuterium discharges were performed in WEST in which a broad parameter space in terms of divertor plasma temperature (inner divertor at <10 eV, outer divertor up to 50 eV) and impurity flux density was achieved by variation of X point elevation, upstream plasma density and fuelling position and rate. Density steps provided stable reference plasma conditions whilst density scans up to the point of detachment revealed the sputtering threshold behaviour of the dominant sputtering species. Tungsten gross erosion was quantified via the common WI 400.9 nm line and correlated with the residual gas content.
Original language | English |
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Article number | 014060 |
Number of pages | 4 |
Journal | Physica Scripta |
Volume | 2020 |
Issue number | T171 |
DOIs | |
Publication status | Published - 16 Mar 2020 |
Event | 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications, PFMC 2019 - Eindhoven, Netherlands Duration: 20 May 2019 → 24 May 2019 |
Keywords
- Nuclear fusion
- Optical emission spectroscopy
- Plasma-surface interaction
- Tungsten erosion
- West