Samenvatting
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.
Originele taal-2 | Engels |
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Artikelnummer | 014060 |
Aantal pagina's | 4 |
Tijdschrift | Physica Scripta |
Volume | 2020 |
Nummer van het tijdschrift | T171 |
DOI's | |
Status | Gepubliceerd - 16 mrt. 2020 |
Evenement | 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications, PFMC 2019 - Eindhoven, Nederland Duur: 20 mei 2019 → 24 mei 2019 |
Financiering
Financiers | Financiernummer |
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Horizon 2020 Framework Programme | 633053 |