Abstract
Tungsten-coated divertor tiles exposed during the third JET ITER-Like Wall (ILW)campaign in 2015–2016 (ILW-3)were studied with Secondary Ion Mass Spectrometry (SIMS). ILW-3 campaign contained more high-power plasma discharges and longer plasma time than the earlier ILW campaigns. Measurements showed increased beryllium (Be)deposition on the upper inner divertor, whereas on the outer divertor, Be deposition was lower than during the second campaign in 2013–2014 (ILW-2). Increased intensities of nickel, molybdenum and tungsten were observed at the surface layer of the inner divertor Be dominated deposits. These layers are probably formed during the high-power plasma discharge phase near the end of the ILW-3 campaign. Compared to the earlier campaigns, D retention on the upper inner divertor was observed to on a similar level than after ILW-2, whereas at the lower inner divertor and most parts of the outer divertor, D retention was lower for ILW-3 than ILW-2. D retention was increased at lower part of outer divertor Tile 7, where Be deposition was slightly increased. Probable reason for the reduction is the higher surface temperature of the tiles due to higher powers used.
Original language | English |
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Pages (from-to) | 1979-1982 |
Journal | Fusion Engineering and Design |
Volume | 146 |
Early online date | 27 Apr 2019 |
DOIs | |
Publication status | Published - 1 Sept 2019 |
MoE publication type | A1 Journal article-refereed |
Funding
This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 under grant agreement No. 633053 . The views and opinions expressed herein do not necessarily reflect those of the European Commission.
Keywords
- Deposition
- Erosion
- Fuel retention
- JET
- EURATOM