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Collection of mobile dust in the T2R reversed field pinch
KTH, School of Electrical Engineering (EES), Fusion Plasma Physics.
KTH, School of Electrical Engineering (EES), Fusion Plasma Physics.
KTH, School of Electrical Engineering (EES), Fusion Plasma Physics.
KTH, School of Electrical Engineering (EES), Fusion Plasma Physics.
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2012 (English)In: Nukleonika, ISSN 0029-5922, E-ISSN 1508-5791, Vol. 57, no 1, 55-60 p.Article in journal (Refereed) 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.

Place, publisher, year, edition, pages
2012. Vol. 57, no 1, 55-60 p.
Keyword [en]
aerogel, dust, collection
National Category
Physical Sciences
Identifiers
URN: urn:nbn:se:kth:diva-98029ISI: 000304237300008Scopus ID: 2-s2.0-84865330015OAI: oai:DiVA.org:kth-98029DiVA: diva2:534587
Conference
10th International Workshop and Summer School on Towards Fusion Energy, JUN 12-18, 2010, Kudowa Zdroj, POLAND
Note

QC 20120618

Available from: 2012-06-18 Created: 2012-06-18 Last updated: 2017-12-07Bibliographically 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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