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Overview of long-term fuel inventory and co-deposition in castellated beryllium limiters at JET
KTH, School of Electrical Engineering (EES), Fusion Plasma Physics.ORCID iD: 0000-0001-9901-6296
2009 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 386, p. 729-732Article in journal (Refereed) Published
Abstract [en]

Morphology of castellated Be tiles from the belt limiter exposed to the JET plasma for 56,000 s was examined on both sides of castellated grooves, on plasma-facing and side surfaces of the tiles. The essential results are (i) deuterium retention in the castellated grooves and in other locations is associated with co-deposition of carbon; (ii) the decay length of deposition in the castellation is around 1.5 mm; (iii) no deuterium is detected in bulk Be; (iv) bridging of gaps by molten beryllium occurred but gaps were not filled with Be; (v) on side surfaces of the tiles the formation of BeO layer was detected at a distance of 20 mm and more from the plasma-facing surface. The consequences for a long-term operation of a reactor-class device with several different plasma-facing materials are addressed.

Place, publisher, year, edition, pages
2009. Vol. 386, p. 729-732
National Category
Fusion, Plasma and Space Physics
Identifiers
URN: urn:nbn:se:kth:diva-25585DOI: 10.1016/j.jnucmat.2008.12.287ISI: 000266386900182Scopus ID: 2-s2.0-64649094807OAI: oai:DiVA.org:kth-25585DiVA, id: diva2:370525
Conference
13th International Conference on Fusion Reactor Materials (ICFRM-13) Nice, FRANCE, DEC 10-14, 2007
Note
QC 20101117Available from: 2010-11-17 Created: 2010-10-27 Last updated: 2017-12-12Bibliographically approved

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Rubel, Marek J.

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