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Time resolved collection and characterization of dust particles moving in the TEXTOR scrape-off layer
KTH, Skolan för elektro- och systemteknik (EES), Fusionsplasmafysik. (Association EURATOM-VR)
KTH, Skolan för elektro- och systemteknik (EES), Fusionsplasmafysik. (Association EURATOM-VR)
KTH, Skolan för elektro- och systemteknik (EES), Rymd- och plasmafysik. (Association EURATOM-VR)ORCID-id: 0000-0002-6712-3625
Vise andre og tillknytning
2013 (engelsk)Inngår i: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 438, nr Suppl., s. S681-S685Artikkel i tidsskrift (Fagfellevurdert) 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.

sted, utgiver, år, opplag, sider
2013. Vol. 438, nr Suppl., s. S681-S685
Emneord [en]
Deuterium content, Dust size distribution, Heated discharges, Particle fluxes, Particle velocities, Scrape-off layer, Silica aerogels, Time-resolved, Silica gel, Sols, Dust
HSV kategori
Identifikatorer
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, id: diva2:688711
Konferanse
20th International Conference on Plasma-Surface Interactions in Controlled Fusion Devices (PSI), Forschungszentrum Julich, Aachen, Germany, May 21-25, 2012
Merknad

QC 20140117

Tilgjengelig fra: 2014-01-17 Laget: 2014-01-17 Sist oppdatert: 2017-12-06bibliografisk kontrollert
Inngår i avhandling
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
Åpne denne publikasjonen i ny fane eller vindu >>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 (engelsk)Doktoravhandling, med artikler (Annet vitenskapelig)
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.
sted, utgiver, år, opplag, sider
Stockholm: KTH Royal Institute of Technology, 2014. s. iv, 84
Serie
TRITA-EE, ISSN 1653-5146 ; 2014:024
Emneord
fusion, tokamak, RFP, divertor, limiter, SOL, transport, migration, surface analysis, IBA, ion micro beam, beryllium, tritium
HSV kategori
Forskningsprogram
Fysik
Identifikatorer
urn:nbn:se:kth:diva-145045 (URN)978-91-7595-147-8 (ISBN)
Disputas
2014-05-16, F3, Lindstedsvägen 26, KTH, Stockholm, 14:00 (engelsk)
Opponent
Veileder
Merknad

QC 20140508

Tilgjengelig fra: 2014-05-08 Laget: 2014-05-07 Sist oppdatert: 2014-05-08bibliografisk kontrollert

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