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Comparison of JET main chamber erosion with dust collected in the divertor
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2013 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 436, no Suppl., 827-832 p.Article in journal (Refereed) Published
Abstract [en]

A complete global balance for carbon in JET requires knowledge of the net erosion in the main chamber, net deposition in the divertor and the amount of dust and flakes collecting in the divertor region. This paper describes a number of measurements on aspects of this global picture. Profiler measurements and cross section microscopy on tiles that were removed in the 2009 JET intervention are used to evaluate the net erosion in the main chamber and net deposition in the divertor. In addition the mass of dust and flakes collected from the JET divertor during the same intervention is also reported and included as part of the balance. Spectroscopic measurements of carbon erosion from the main chamber are presented and compared with the erosion measurements for the main chamber.

Place, publisher, year, edition, pages
2013. Vol. 436, no Suppl., 827-832 p.
Keyword [en]
Carbon erosion, Divertor region, Dust collected, Erosion measurements, Jet Divertors, Profiler measurements, Spectroscopic measurements
National Category
Fusion, Plasma and Space Physics
Identifiers
URN: urn:nbn:se:kth:diva-105157DOI: 10.1016/j.jnucmat.2013.01.179ISI: 000330795300177Scopus ID: 2-s2.0-84885483967OAI: oai:DiVA.org:kth-105157DiVA: diva2:570130
Conference
20th International Conference on Plasma-Surface Interactions in Controlled Fusion Devices (PSI), Forschungszentrum Julich, Aachen, Germany, May 21-25, 2012
Note

Updated from "Submitted" to "Published". QC 20140120

Available from: 2012-11-16 Created: 2012-11-16 Last updated: 2017-12-07Bibliographically 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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