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Be ITER-like wall at the JET tokamak under plasma
KTH, Skolan för elektro- och systemteknik (EES), Fusionsplasmafysik.ORCID-id: 0000-0001-9901-6296
Vise andre og tillknytning
2017 (engelsk)Inngår i: Physica Scripta, ISSN 0031-8949, E-ISSN 1402-4896, Vol. T170, artikkel-id 014049Artikkel i tidsskrift (Fagfellevurdert) Published
Abstract [en]

The JET tokamak is operated with beryllium and tungsten plasma-facing components to prepare for the exploitation of ITER. To determine beryllium erosion and migration in JET a set of markers were installed. Specimens from different beryllium marker tiles of the main wall of the ITER-like wall (ILW) JET tokamak from the first and the second D-D campaign were analyzed with nuclear reaction analysis, x-ray fluorescence spectroscopy, scanning electron microscopy and x-ray diffraction (XRD). Emphasis was on the determination of carbon plasma impurities deposited on beryllium surfaces. The C-12(d, p(0))C-13 reaction was used to quantify carbon deposition and to determine depth profiles. Carbon quantities on the surface of the Be tiles are low, varying from (0.35 +/- 0.07) x 10(17) to (11.8 +/- 0.6) x 10(17) at cm(-2) in the deposition depth from 0.4 to 6.7 mu m, respectively. In the 0.4-0.5 mm wide grooves of castellation sides the carbon content is found up to (14.3 +/- 2.5) x 10(17) at cm(-2) while it is higher (up to (38 +/- 4) x 10(17) at cm(-2)) in wider gaps (0.8 mm) separating tile segments. Oxygen (O), titanium (Ti), chromium (Cr), manganese (Mn), iron (Fe), nickel (Ni) and tungsten (W) were detected in all samples exposed to plasma and the reference one but at lower quantities at the latter. In the central part of the Inner Wall Guard Limiter from the first ILW campaign and in the Outer Poloidal Limiter from the second ILW campaign the Ni interlayer has been completely eroded. XRD shows the formation of BeNi in most specimens.

sted, utgiver, år, opplag, sider
IOP PUBLISHING LTD , 2017. Vol. T170, artikkel-id 014049
Emneord [en]
beryllium, JET tokamak, ITER like wall, plasma, nuclear reaction analysis, erosiond-eposition
HSV kategori
Identifikatorer
URN: urn:nbn:se:kth:diva-217725DOI: 10.1088/1402-4896/aa8ff4ISI: 000414120500049OAI: oai:DiVA.org:kth-217725DiVA, id: diva2:1159558
Konferanse
16th International Conference on Plasma-Facing Materials and Components for Fusion Applications, MAY 16-19, 2017, GERMANY
Merknad

QC 20171123

Tilgjengelig fra: 2017-11-23 Laget: 2017-11-23 Sist oppdatert: 2017-11-23bibliografisk kontrollert

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