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Microanalysis of deposited layers in the inner divertor of JET with ITER-like wall
Royal Inst Technol, Sch Elect Engn, Dept Fus Plasma Phys, S-10405 Stockholm, Sweden..
Royal Inst Technol, Sch Elect Engn, Dept Fus Plasma Phys, S-10405 Stockholm, Sweden..
Royal Inst Technol, Sch Elect Engn, Dept Fus Plasma Phys, S-10405 Stockholm, Sweden..
Royal Inst Technol, Sch Elect Engn, Dept Fus Plasma Phys, S-10405 Stockholm, Sweden..
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2017 (engelsk)Inngår i: NUCLEAR MATERIALS AND ENERGY, ISSN 2352-1791, Vol. 12, nr SI, s. 412-417Artikkel i tidsskrift (Fagfellevurdert) Published
Abstract [en]

In JET with ITER-like wall, beryllium eroded in the main chamber is transported to the divertor and deposited mainly at the horizontal surfaces of tiles 1 and 0 (high field gap closure, HFGC). These surfaces are tungsten coated carbon fibre composite (CFC). Surface sampleswere collected following the plasma operations in 2011-2012 and 2013-2014 respectively. The surfaces, as well as polished cross sections of the deposited layers at the surfaces have been studied with micro ion beam analysis methods (mu-IBA). Deposition of Beand other impurities, and retention of D is microscopically inhomogeneous. Impurities and trapped deuterium accumulate preferentially in cracks, pits and depressed regions, and at the sides of large pits in the substrate (e.g. arc tracks where the W coating has been removed). With careful overlaying of mu-NRA elemental maps with optical microscopy images, it is possible to separate surface roughness effects from depth profiles at microscopically flat surface regions.

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2017. Vol. 12, nr SI, s. 412-417
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URN: urn:nbn:se:uu:diva-344535DOI: 10.1016/j.nme.2017.02.015ISI: 000417293300062OAI: oai:DiVA.org:uu-344535DiVA, id: diva2:1188412
Tilgjengelig fra: 2018-03-07 Laget: 2018-03-07 Sist oppdatert: 2018-03-07bibliografisk kontrollert

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