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Microanalysis of deposited layers in the divertor of JET following operations with carbon wall
KTH, Skolan för elektro- och systemteknik (EES), Fusionsplasmafysik. (Association EURATOM-VR)
KTH, Skolan för elektro- och systemteknik (EES), Fusionsplasmafysik. (Association EURATOM-VR)
KTH, Skolan för elektro- och systemteknik (EES), Fusionsplasmafysik. (Association EURATOM-VR)
Visa övriga samt affilieringar
2013 (Engelska)Ingår i: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 438, nr Suppl., s. S668-S672Artikel i tidskrift (Refereegranskat) Published
Abstract [en]

Elemental mapping of cross sections of deposited layers on inboard tiles in the JET divertor after exposure to plasma operations with carbon wall are presented. The study was made using microbeam ion beam analysis methods in combination with optical microscopy and SEM. The surfaces had been exposed to plasma through different periods of operation (1998-2007, 2007-2009 and 1998-2009). The texture and composition of the layers are non-uniform. The physical structures include columnar, lamellar and disordered globular appearances. The distribution of trapped deuterium was frequently found to be lamellar, with well-defined sub layers with higher deuterium concentration. However, 3D regions with dimensions of about 100 μm with enhanced deuterium content were also found, both at the layer surfaces and in the layer cross sections. The distributions of beryllium and Inconel components were lamellar but did not otherwise show large non-uniformity on the same scale length as the deuterium.

Ort, förlag, år, upplaga, sidor
2013. Vol. 438, nr Suppl., s. S668-S672
Nyckelord [en]
Deposited layer, Deuterium content, Elemental mapping, Following operation, Ion beam analysis, Nonuniformity, Physical structures, Plasma operations, Carbon, D region, Deuterium, Lamellar structures
Nationell ämneskategori
Fusion, plasma och rymdfysik
Identifikatorer
URN: urn:nbn:se:kth:diva-140096DOI: 10.1016/j.jnucmat.2013.01.141ISI: 000330795300140Scopus ID: 2-s2.0-84885474506OAI: oai:DiVA.org:kth-140096DiVA, id: diva2:688706
Konferens
20th International Conference on Plasma-Surface Interactions in Controlled Fusion Devices (PSI), Forschungszentrum Julich, Aachen, Germany, May 21-25, 2012
Anmärkning

QC 20140117

Tillgänglig från: 2014-01-17 Skapad: 2014-01-17 Senast uppdaterad: 2017-12-06Bibliografiskt 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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Bergsåker, HenricPetersson, PerBykov, Igor
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Fusionsplasmafysik
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Journal of Nuclear Materials
Fusion, plasma och rymdfysik

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Totalt: 207 träffar
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