CEA
Author in the following contributions
- Latest results of EUROfusion plasma-facing components research in the areas of power loading, material erosion and fuel retention
- A Validated Multi-Physics Modeling Approach to Predicting Erosion, Re-deposition and Gas Retention in Fusion Tokamak Divertors
- Gross and net erosion balance of plasma-facing components in full-W tokamaks
- Interpretative modeling of impurity transport and tungsten sources in WEST boundary plasma
- Measuring and modeling helium accumulation in single crystal tungsten specimens exposed to He plasma discharges in the WEST reciprocating collector probe
- Long discharges in steady state with D2 and N2 on the actively cooled tungsten upper divertor in WEST
- Investigation of plasma wall interactions between tungsten plasma facing components and helium plasmas in the WEST tokamak
- Divertor power loads and scrape off layer width in the large aspect ratio full tungsten tokamak WEST
- Observation of tungsten plasma-facing components after the first phase of operation of the WEST tokamak
- [REGULAR POSTER TWIN] A Validated Multi-Physics Modeling Approach to Predicting Erosion, Re-deposition and Gas Retention in Fusion Tokamak Divertors
