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Distribution of hydrogen isotopes, carbon and beryllium on in-vessel surfaces in the various jet divertors
KTH, School of Electrical Engineering (EES), Fusion Plasma Physics. KTH, School of Electrical Engineering (EES), Centres, Alfvén Laboratory Centre for Space and Fusion Plasma Physics.ORCID iD: 0000-0001-9901-6296
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2005 (English)In: Fusion science and technology, ISSN 1536-1055, E-ISSN 1943-7641, Vol. 48, no 1, 551-556 p.Article in journal (Refereed) Published
Abstract [en]

JET has operated with divertors of differing geometries since 1994. Impurities accumulated in the inner leg of all the divertors, and operation of the first (Mk I) divertor with beryllium tiles demonstrated that most are eroded from the main chamber walls and swept along the scrape-off layer to the inner divertor. Carbon deposited at the inner divertor is then locally transported to shadowed regions such as the inner louvres, where, for example, most of the tritium was trapped during the deuterium-tritium experiment (DTE1). Factors affecting these transport processes (e.g. temperature) are important for ITER, but are not well understood.

Place, publisher, year, edition, pages
2005. Vol. 48, no 1, 551-556 p.
Keyword [en]
tritium inventory, retention, erosion/deposition, tokamaks, issues
National Category
Physical Sciences
Identifiers
URN: urn:nbn:se:kth:diva-14905ISI: 000230433300119Scopus ID: 2-s2.0-23144451742OAI: oai:DiVA.org:kth-14905DiVA: diva2:332946
Note
QC 20100525 QC 20111011Available from: 2010-08-05 Created: 2010-08-05 Last updated: 2017-12-12Bibliographically approved

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Rubel, Marek J.

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