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Collection of mobile dust in the T2R reversed field pinch
KTH, Skolan för elektro- och systemteknik (EES), Fusionsplasmafysik.
KTH, Skolan för elektro- och systemteknik (EES), Fusionsplasmafysik.
KTH, Skolan för elektro- och systemteknik (EES), Fusionsplasmafysik.
KTH, Skolan för elektro- och systemteknik (EES), Fusionsplasmafysik.
Visa övriga samt affilieringar
2012 (Engelska)Ingår i: Nukleonika, ISSN 0029-5922, E-ISSN 1508-5791, Vol. 57, nr 1, s. 55-60Artikel i tidskrift (Refereegranskat) Published
Abstract [en]

Intensive plasma-wall interactions in fusion devices result in the impurity production and the formation of films of redeposited material, debris and dust. In present day devices, with short pulses, the mobile dust does not pose any serious operational problems, but it is a matter of serious concern for ITER and for later power producing devices with a high duty cycle. We report results of a dust collection experiment carried out at the T2R reversed field pinch device and related heavy impurity flux measurements. Dust and impurities were collected on passive Si surface probes and on ultralow density silica aerogel collectors. The advantage of the latter method is the possibility of nondestructive capture of the micron- and submicron-sized dust particles. The toroidal and radial deposition fluxes of dust particles and impurities are estimated and discussed in the light of the dominant forces acting on the dust.

Ort, förlag, år, upplaga, sidor
2012. Vol. 57, nr 1, s. 55-60
Nyckelord [en]
aerogel, dust, collection
Nationell ämneskategori
Fysik
Identifikatorer
URN: urn:nbn:se:kth:diva-98029ISI: 000304237300008Scopus ID: 2-s2.0-84865330015OAI: oai:DiVA.org:kth-98029DiVA, id: diva2:534587
Konferens
10th International Workshop and Summer School on Towards Fusion Energy, JUN 12-18, 2010, Kudowa Zdroj, POLAND
Anmärkning

QC 20120618

Tillgänglig från: 2012-06-18 Skapad: 2012-06-18 Senast uppdaterad: 2017-12-07Bibliografiskt granskad
Ingår 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
Öppna denna publikation i ny flik eller fönster >>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 (Engelska)Doktorsavhandling, sammanläggning (Övrigt vetenskapligt)
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.
Ort, förlag, år, upplaga, sidor
Stockholm: KTH Royal Institute of Technology, 2014. s. iv, 84
Serie
TRITA-EE, ISSN 1653-5146 ; 2014:024
Nyckelord
fusion, tokamak, RFP, divertor, limiter, SOL, transport, migration, surface analysis, IBA, ion micro beam, beryllium, tritium
Nationell ämneskategori
Fusion, plasma och rymdfysik
Forskningsämne
Fysik
Identifikatorer
urn:nbn:se:kth:diva-145045 (URN)978-91-7595-147-8 (ISBN)
Disputation
2014-05-16, F3, Lindstedsvägen 26, KTH, Stockholm, 14:00 (Engelska)
Opponent
Handledare
Anmärkning

QC 20140508

Tillgänglig från: 2014-05-08 Skapad: 2014-05-07 Senast uppdaterad: 2014-05-08Bibliografiskt granskad

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Bykov, IgorBergsåker, HenricOgata, DouglasPetersson, PerRatynskaia, Svetlana
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