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Assessment of erosion, deposition and fuel retention in the JET-ILW divertor from ion beam analysis data
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2017 (English)In: NUCLEAR MATERIALS AND ENERGY, ISSN 2352-1791, Vol. 12, p. 559-563Article in journal (Refereed) Published
Abstract [en]

Post-mortem analyses of individual components provide relevant information on plasma-surface interactions like tungsten erosion, beryllium deposition and plasma fuel retention with divertor tiles via implantation or co-deposition. Ion Beam techniques are ideal tools for such purposes and have been extensively used for post-mortem analyses of selected tiles from JET following each campaign. In this contribution results from tiles removed from the JET ITER-Like Wall (JET-ILW) divertor following the 2013-2014 campaign are presented. The results summarize erosion, deposition and fuel retention along the poloidal cross section of the divertor surface and provide data for comparison with the first JET-ILW campaign, showing a similar pattern of material migration with the exception of Tile 6 where the strike point time on the tile was similar to 4 times longer in 2013-2014 than in 2011-2012, which is likely to account for more material migration to this region. The W deposition on top of the Mo marker coating of Tile 4 shows that the enrichment takes place at the strike point location.

Place, publisher, year, edition, pages
Elsevier, 2017. Vol. 12, p. 559-563
National Category
Fusion, Plasma and Space Physics
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URN: urn:nbn:se:kth:diva-220641DOI: 10.1016/j.nme.2016.10.027ISI: 000417293300088Scopus ID: 2-s2.0-85006922988OAI: oai:DiVA.org:kth-220641DiVA, id: diva2:1173130
Note

QC 20180111

Available from: 2018-01-11 Created: 2018-01-11 Last updated: 2018-03-12Bibliographically approved

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Rubel, Marek

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