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Assessment of cleaning methods for rst mirrors tested in JET for ITER
KTH, School of Electrical Engineering (EES), Fusion Plasma Physics.
CCFE/EURATOM Fusion Association, Culham Science Centre.
Association EURATOM–TEKES, VTT, Espoo.
Department of Physics, University of Basel.
Show others and affiliations
(English)Article in journal (Other academic) Submitted
National Category
Fusion, Plasma and Space Physics
Identifiers
URN: urn:nbn:se:kth:diva-105161OAI: oai:DiVA.org:kth-105161DiVA: diva2:570137
Note

QS 2012

Available from: 2012-11-16 Created: 2012-11-16 Last updated: 2012-11-16Bibliographically approved
In thesis
1. Plasma-Facing Components in Tokamaks: Material Modification and Fuel Retention
Open this publication in new window or tab >>Plasma-Facing Components in Tokamaks: Material Modification and Fuel Retention
2012 (English)Doctoral thesis, comprehensive summary (Other academic)
Abstract [en]

Fuel inventory and generation of carbon and metal dust in a tokamak are perceived to be serious safety and economy issues for the steady-state operation of a fusion reactor, e.g. ITER. These topics have been explored in this thesis in order to contribute to a better understanding and the development of methods for controlling and curtailing fuel accumulation and dust formation in controlled fusion devices. The work was carried out with material facing fusion plasmas in three tokamaks: TEXTOR in Forschungszentrum Jülich (Germany), Tore Supra in the Nuclear Research Center Cadarache (France) and JET in Culham Centre for Fusion Energy (United Kingdom). Following issues were addressed: (a) properties of material migration products, i.e. co-deposited layers and dust particles; (b) impact of fuel removal methods on dust generation and on modification of plasma-facing components; (c) efficiency of fuel and deposit removal techniques; (d) degradation mechanism of diagnostic components - mirrors - and methods of their regeneration.

Place, publisher, year, edition, pages
Stockholm: KTH Royal Institute of Technology, 2012. xiv, 58 p.
Series
Trita-EE, ISSN 1653-5146 ; 2012:058
Keyword
magnetic confinement fusion, plasma-facing components, plasma-facing materials, fuel inventory, erosion and deposition
National Category
Fusion, Plasma and Space Physics
Identifiers
urn:nbn:se:kth:diva-105099 (URN)978-91-7501-567-5 (ISBN)
Public defence
2012-12-12, F3, Lindstedtsvagen 26, KTH, Stockholm, 10:00 (English)
Opponent
Supervisors
Note

QC 20121116

Available from: 2012-11-16 Created: 2012-11-16 Last updated: 2012-11-16Bibliographically approved

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Citation style
  • apa
  • harvard1
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Language
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Output format
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