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Overview of material re-deposition and fuel retention studies at JET with the Gas Box divertor
KTH, Skolan för elektro- och systemteknik (EES), Fusionsplasmafysik.ORCID-id: 0000-0001-9901-6296
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2006 (Engelska)Ingår i: Nuclear Fusion, ISSN 0029-5515, E-ISSN 1741-4326, Vol. 46, nr 2, s. 350-366Artikel i tidskrift (Refereegranskat) Published
Abstract [en]

in the period 1998-2001 the JET tokamak was operated with the MkII Gas Box divertor. On two occasions during that period a number of limiter and divertor tiles were retrieved from the torus and then examined ex situ with surface sensitive techniques. Erosion and deposition patterns were determined in order to assess the material erosion, material migration and fuel inventory on plasma facing components. Tracer techniques, e.g. injection of C-13 labelled methane and tiles coated with a low-Z and high-Z marker layer, were used to enhance the volume of information on the material transport. The results show significant asymmetry in the distribution of fuel and plasma impurity species between the inner (net deposition area) and the outer (net erosion) divertor channels. No significant formation of highly hydrogenated carbon films has been found in the Gas Box structure. The important processes for material migration, and the influence of operation scenarios on the morphology of the deposits are discussed. Comparison is also made with results obtained following previous divertor campaigns.

Ort, förlag, år, upplaga, sidor
2006. Vol. 46, nr 2, s. 350-366
Nyckelord [en]
tritium depth profiles, fusion experiments, inner divertor, asdex upgrade, tokamaks, tiles, erosion/deposition, redeposition, operation, layers
Identifikatorer
URN: urn:nbn:se:kth:diva-15455DOI: 10.1088/0029-5515/46/2/018ISI: 000235600500018Scopus ID: 2-s2.0-31344461692OAI: oai:DiVA.org:kth-15455DiVA, id: diva2:333496
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QC 20100525Tillgänglig från: 2010-08-05 Skapad: 2010-08-05 Senast uppdaterad: 2017-12-12Bibliografiskt granskad

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Rubel, Marek J.

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