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Assessment of cleaning methods for rst mirrors tested in JET for ITER
KTH, Skolan för elektro- och systemteknik (EES), Fusionsplasmafysik.
CCFE/EURATOM Fusion Association, Culham Science Centre.
Association EURATOM–TEKES, VTT, Espoo.
Department of Physics, University of Basel.
Vise andre og tillknytning
(engelsk)Artikkel i tidsskrift (Annet vitenskapelig) Submitted
HSV kategori
Identifikatorer
URN: urn:nbn:se:kth:diva-105161OAI: oai:DiVA.org:kth-105161DiVA, id: diva2:570137
Merknad

QS 2012

Tilgjengelig fra: 2012-11-16 Laget: 2012-11-16 Sist oppdatert: 2012-11-16bibliografisk kontrollert
Inngår i avhandling
1. Plasma-Facing Components in Tokamaks: Material Modification and Fuel Retention
Åpne denne publikasjonen i ny fane eller vindu >>Plasma-Facing Components in Tokamaks: Material Modification and Fuel Retention
2012 (engelsk)Doktoravhandling, med artikler (Annet vitenskapelig)
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.

sted, utgiver, år, opplag, sider
Stockholm: KTH Royal Institute of Technology, 2012. s. xiv, 58
Serie
Trita-EE, ISSN 1653-5146 ; 2012:058
Emneord
magnetic confinement fusion, plasma-facing components, plasma-facing materials, fuel inventory, erosion and deposition
HSV kategori
Identifikatorer
urn:nbn:se:kth:diva-105099 (URN)978-91-7501-567-5 (ISBN)
Disputas
2012-12-12, F3, Lindstedtsvagen 26, KTH, Stockholm, 10:00 (engelsk)
Opponent
Veileder
Merknad

QC 20121116

Tilgjengelig fra: 2012-11-16 Laget: 2012-11-16 Sist oppdatert: 2012-11-16bibliografisk kontrollert

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