Abstract
In 2010, all the plasma-facing components were removed from JET so that the carbon-based surfaces could be replaced with beryllium (Be) or tungsten as part of the ITER-like wall (ILW) project. This gives unprecedented opportunities for post-mortem analyses of these plasma-facing surfaces; this paper reviews the data obtained so far and relates the information to studies of tiles removed during previous JET shutdowns. The general pattern of erosion/deposition at the JET divertor has been maintained, with deposition of impurities in the scrape-off layer (SOL) at the inner divertor and preferential removal of carbon and transport into the corner. However, the remaining films in the SOL contain very high Be/C ratios at the surface. The first measurements of erosion using a tile profiler have been completed, with up to 200 microns erosion being recorded at points on the inner wall guard limiters.
| Original language | English |
|---|---|
| Article number | 014003 |
| Number of pages | 6 |
| Journal | Physica Scripta |
| Volume | 2011 |
| Issue number | T145 |
| DOIs | |
| Publication status | Published - 2011 |
| MoE publication type | A4 Article in a conference publication |
| Event | 13th International Workshop on Plasma-Facing Materials and Components for Fusion Applications, PFMC-13 - Rosenheim, Germany Duration: 9 May 2011 → 13 May 2011 |
UN SDGs
This output contributes to the following UN Sustainable Development Goals (SDGs)
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SDG 7 Affordable and Clean Energy
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