Deuterium retention on the tungsten-coated divertor tiles of JET ITER-like wall in 2015–2016 campaign

A. Lahtinen*, J. Likonen, S. Koivuranta, E. Alves, A. Baron-Wiechec, N. Catarino, J. P. Coad, K. Heinola, J. Räisänen, A. Widdowson

*Corresponding author for this work

Research output: Contribution to journalArticlepeer-review

7 Scopus citations


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 languageEnglish
Pages (from-to)1979-1982
Number of pages4
JournalFusion Engineering and Design
StatePublished - Sep 2019
Externally publishedYes


  • Deposition
  • Erosion
  • Fuel retention
  • JET


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