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Experimental investigations of castellated monoblock structures in TEXTOR
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2005 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 337-39, no 1-3, 917-921 p.Article in journal (Refereed) Published
Abstract [en]

To insure the thermo-mechanical durability of ITER it is planned to manufacture the castellated armour of the divertor i.e. to split the armour into cells [W. Daener et al., Fusion Eng. Des. 61T62 (2002) 61]. This will cause an increase of the surface area and may lead to carbon deposition and tritium accumulation in the gaps in between cells. To investigate the processes of deposition and fuel accumulation in gaps, a castellated test-limiter was exposed to the SOL plasma of TEXTOR. The geometry of castellation used was the same as proposed for the vertical divertor target in ITER [W. Daener et al., Fusion Eng. Des. 61T62 (2002) 61]. After exposure the limiter was investigated with various surface diagnostic techniques. Deposited layers containing carbon, hydrogen, deuterium and boron were found both on top plasma-facing surfaces and in the gaps. The amount of deuterium in the gaps was at least 30% of that found on the top surfaces.

Place, publisher, year, edition, pages
2005. Vol. 337-39, no 1-3, 917-921 p.
Keyword [en]
ITER, castellation, TEXTOR, erosion/deposition, deuterium inventory, diii-d, deposition, components, retention, deuterium, tokamak, tiles, jet
National Category
Materials Engineering
URN: urn:nbn:se:kth:diva-14620DOI: 10.1016/j.jnucmat.2004.09.064ISI: 000227789500180ScopusID: 2-s2.0-13844321000OAI: diva2:332661
QC 20100525 QC 20111012. 16th International Conference on Plasma Surface Interactions in Controlled Fusion Devices. Portland, ME. MAY 24-28, 2004 Available from: 2010-08-05 Created: 2010-08-05 Last updated: 2011-10-12Bibliographically approved

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Emmoth, BirgerRubel, Marek J.
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Microelectronics and Information Technology, IMITFusion Plasma Physics
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