Assessment of erosion, deposition and fuel retention in the JET-ILW divertor from ion beam analysis dataShow others and affiliations
Number of Authors: 11142017 (English)In: Nuclear Materials and Energy, E-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. (C) 2016 The Authors. Published by Elsevier Ltd.
Place, publisher, year, edition, pages
ELSEVIER , 2017. Vol. 12, p. 559-563
Keywords [en]
JET, ITER-like wall, Plasma facing components, Erosion, Deposition, Ion beam analysis
National Category
Fusion, Plasma and Space Physics
Identifiers
URN: urn:nbn:se:uu:diva-398916DOI: 10.1016/j.nme.2016.10.027ISI: 000417293300088OAI: oai:DiVA.org:uu-398916DiVA, id: diva2:1379651
Note
For complete list of authors see http://dx.doi.org/10.1016/j.nme.2016.10.027
2019-12-172019-12-172019-12-17Bibliographically approved