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Overview of JET post-mortem results following the 2007-9 operational period, and comparisons with previous campaigns
Vise andre og tillknytning
2011 (engelsk)Inngår i: Physica Scripta, ISSN 0031-8949, E-ISSN 1402-4896, Vol. T145, s. 014003-Artikkel i tidsskrift (Fagfellevurdert) Published
Abstract [en]

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.

sted, utgiver, år, opplag, sider
Institute of Physics Publishing (IOPP), 2011. Vol. T145, s. 014003-
Emneord [en]
DIVERTOR, EROSION/DEPOSITION, TRANSPORT
HSV kategori
Identifikatorer
URN: urn:nbn:se:kth:diva-70033DOI: 10.1088/0031-8949/2011/T145/014003ISI: 000298475200004Scopus ID: 2-s2.0-84857551025OAI: oai:DiVA.org:kth-70033DiVA, id: diva2:486043
Merknad
13th International Workshop on Plasma-Facing Materials and Components for Fusion Applications (PFMC)/1st International Conference on Fusion Energy Materials Science (FEMaS), Rosenheim, GERMANY, MAY 09-13, 2011 Qc 20120130Tilgjengelig fra: 2012-01-30 Laget: 2012-01-30 Sist oppdatert: 2017-12-08bibliografisk kontrollert

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