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Time resolved collection and characterization of dust particles moving in the TEXTOR scrape-off layer
KTH, School of Electrical Engineering (EES), Fusion Plasma Physics. (Association EURATOM-VR)
KTH, School of Electrical Engineering (EES), Fusion Plasma Physics. (Association EURATOM-VR)
KTH, School of Electrical Engineering (EES), Space and Plasma Physics. (Association EURATOM-VR)ORCID iD: 0000-0002-6712-3625
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2013 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 438, no Suppl., S681-S685 p.Article in journal (Refereed) Published
Abstract [en]

Moving dust has been collected in the SOL of TEXTOR in a time-resolved way with silica aerogel collectors [1-3]. The collectors were exposed to the toroidal particle flux in NBI heated discharges during the startup and flat top phase. Intrinsic dust was collected in several discharges. Other discharges were accompanied with injection of known amounts of pre-characterized dust (W, C flakes and C microspheres) from a position toroidally 120° away from the collector. Particle flux, composition and dust size distribution have been determined with SEM and EDX. Calibration allowed particle velocity estimates to be made. Upper limits for the deuterium content of individual dust grains have been determined by NRA.

Place, publisher, year, edition, pages
2013. Vol. 438, no Suppl., S681-S685 p.
Keyword [en]
Deuterium content, Dust size distribution, Heated discharges, Particle fluxes, Particle velocities, Scrape-off layer, Silica aerogels, Time-resolved, Silica gel, Sols, Dust
National Category
Fusion, Plasma and Space Physics
Identifiers
URN: urn:nbn:se:kth:diva-140094DOI: 10.1016/j.jnucmat.2013.01.144ISI: 000330795300143Scopus ID: 2-s2.0-84885469754OAI: oai:DiVA.org:kth-140094DiVA: diva2:688711
Conference
20th International Conference on Plasma-Surface Interactions in Controlled Fusion Devices (PSI), Forschungszentrum Julich, Aachen, Germany, May 21-25, 2012
Note

QC 20140117

Available from: 2014-01-17 Created: 2014-01-17 Last updated: 2017-12-06Bibliographically approved
In thesis
1. Experimental studies of materials migration in magnetic confinement fusion devices: Novel methods for measurement of macro particle migration, transport of atomic impurities and characterization of exposed surfaces
Open this publication in new window or tab >>Experimental studies of materials migration in magnetic confinement fusion devices: Novel methods for measurement of macro particle migration, transport of atomic impurities and characterization of exposed surfaces
2014 (English)Doctoral thesis, comprehensive summary (Other academic)
Abstract [en]

During several decades of research and development in the field of Magnetically Confined Fusion (MCF) the preferred selection of materials for Plasma Facing Components (PFC) has changed repeatedly. Without doubt, endurance of the first wall will decide research availability and lifespan of the first International Thermonuclear Research Reactor (ITER). Materials erosion, redeposition and mixing in the reactor are the critical processes responsible for modification of materials properties under plasma impact. This thesis presents several diagnostic techniques and their applications for studies of materials transport in fusion devices. The measurements were made at the EXTRAP T2R Reversed Field Pinch operated in Alfvén laboratory at KTH (Sweden), the TEXTOR tokamak, recently shut down at Forschungszentrum Jülich (Germany) and in the JET tokamak at CCFE (UK). The main outcomes of the work are:

  • Development and application of a method for non-destructive capture and characterization of fast dust particles moving in the edge plasma of fusion devices, as well as particles generated upon laser-assisted cleaning of plasma exposed surfaces. 
  • Advancement of conventional broad beam and micro ion beam techniques to include measurement of tritium in the surfaces exposed in future D-T experiments. 
  • Adaption of the micro ion beam method for precision mapping of non uniform elements concentrations on irregular surfaces. 
  • Implementation of an isotopic marker to study the large scale materials migration in a tokamak and development of a method for fast non destructive sampling of the marker on surfaces of PFCs.
Place, publisher, year, edition, pages
Stockholm: KTH Royal Institute of Technology, 2014. iv, 84 p.
Series
TRITA-EE, ISSN 1653-5146 ; 2014:024
Keyword
fusion, tokamak, RFP, divertor, limiter, SOL, transport, migration, surface analysis, IBA, ion micro beam, beryllium, tritium
National Category
Fusion, Plasma and Space Physics
Research subject
Physics
Identifiers
urn:nbn:se:kth:diva-145045 (URN)978-91-7595-147-8 (ISBN)
Public defence
2014-05-16, F3, Lindstedsvägen 26, KTH, Stockholm, 14:00 (English)
Opponent
Supervisors
Note

QC 20140508

Available from: 2014-05-08 Created: 2014-05-07 Last updated: 2014-05-08Bibliographically approved

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Ratynskaia, Svetlana

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