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Investigation of probe surfaces after ion cyclotron wall conditioning in ASDEX Upgrade
KTH, Skolan för elektro- och systemteknik (EES), Fusionsplasmafysik.ORCID-id: 0000-0001-5603-8559
(Engelska)Manuskript (preprint) (Övrigt vetenskapligt)
Abstract [en]

For the first time, material analysis techniques have been applied to study the effect of ion cyclotron wall conditioning (ICWC) on probe surfaces in a metal-wall machine. ICWC is a technique envisaged to contribute to the removal of fuel and impurities from the first wall of ITER. The objective of this work was to assess impurity migration under the ICWC operation. Tungsten probes were exposed in ASDEX Upgrade to discharges in helium. After wall conditioning, the probes were covered with a co-deposited layer containing D, B, C, N, O and relatively high amount of He on virgin W substrates. The concentration ratio He/C+B was 0.7. The formation of the co-deposited layer indicates that a fraction of the impurities desorbed from the wall under ICWC operation are transported by plasma and deposited away from their original location.

Nyckelord [en]
ICWC, Erosion-deposition, fuel removal, ion beam analysis, ASDEX Upgrade
Nationell ämneskategori
Fysik
Forskningsämne
Fysik
Identifikatorer
URN: urn:nbn:se:kth:diva-190898OAI: oai:DiVA.org:kth-190898DiVA, id: diva2:953636
Anmärkning

QC 20160819

Tillgänglig från: 2016-08-18 Skapad: 2016-08-18 Senast uppdaterad: 2016-09-02Bibliografiskt granskad
Ingår i avhandling
1. Impact of material migration on plasma-facing components in tokamaks
Öppna denna publikation i ny flik eller fönster >>Impact of material migration on plasma-facing components in tokamaks
2016 (Engelska)Doktorsavhandling, sammanläggning (Övrigt vetenskapligt)
Abstract [en]

Plasma-wall interaction plays an essential role in the performance and safety of a fusion reactor. This thesis focuses on the impact of material migration on plasma-facing components. It is based on experiments performed in tokamaks: JET, TEXTOR and ASDEX Upgrade. The objectives of the experiments were to assess fuel and impurity removal under ion cyclotron wall conditioning (ICWC) and plasma impact on diagnostic mirrors.

In wall conditioning studies, tracer techniques based on the injection of rare isotopes (15N, 18O) were used to determine conclusively the impact of the respective gases. For the first time, probe surfaces and wall components exposed to ICWC were examined by surface analysis methods. Discharges in hydrogen were the most efficient to erode carbon co-deposits, resulting in a reduction of the initial deuterium content by a factor of two. It was also found that impurities desorbed under ICWC are partly re-deposited on the wall.

Plasma impact on diagnostic mirrors was determined by surface analysis of test mirrors exposed at JET. Reflectivity of mirrors from the divertor region was severely decreased due to deposits of beryllium, deuterium, carbon and other impurities. This result points out the need to develop mirror maintenance procedures. Neutron damage on mirrors was simulated by ion irradiation in an ion implanter. It was shown that damage levels similar to those expected in the first wall of a fusion reactor do not produce a significant change in reflectivity.

Ort, förlag, år, upplaga, sidor
Stockholm: KTH Royal Institute of Technology, 2016. s. 54
Serie
TRITA-EE, ISSN 1653-5146
Nyckelord
Fusion, material migration, wall conditioning, diagnostic mirrors, plasma-facing materials
Nationell ämneskategori
Fusion, plasma och rymdfysik
Forskningsämne
Fysik
Identifikatorer
urn:nbn:se:kth:diva-190903 (URN)978-91-7729-046-9 (ISBN)
Disputation
2016-09-15, Kollegiesalen, Brinellvägen 8, Stockholm, 10:00 (Engelska)
Opponent
Handledare
Anmärkning

QC 20160819

Tillgänglig från: 2016-08-19 Skapad: 2016-08-18 Senast uppdaterad: 2016-08-19Bibliografiskt granskad

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Garcia Carrasco, Alvaro

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