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Treatment of ITER plasma facing components: Current status and remaining open issues before ITER implementation
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2007 (English)In: Fusion engineering and design, ISSN 0920-3796, E-ISSN 1873-7196, Vol. 82, no 15-24, 2390-2398 p.Article in journal (Refereed) Published
Abstract [en]

The in-vessel tritium inventory control is one of the most ITER challenging issues which has to be resolved to fulfil safety requirements. This is due mainly to the presence of carbon as a constituent of plasma facing components (PFCs) which leads to a high fuel permanent retention. For several years now, physics studies and technological developments have been undertaken worldwide in order to develop reliable techniques which could be used in ITER severe environment (magnetic field, vacuum, high temperature) for in situ tritium recovery. The scope of this contribution is to review the present status of these achievements and define the remaining work to be done in order to propose a dedicated work program. Different treatment techniques (chemical treatments, photonic cleaning) will be reviewed. In the frame of ITER, they will be compared in terms of fuel removal rate as well as surface accessibility, type of production (gas or particulates), ability to clean mixed material. And lastly, consequences of bulk trapping observed in tokamak on the techniques currently under development will be addressed.

Place, publisher, year, edition, pages
2007. Vol. 82, no 15-24, 2390-2398 p.
Keyword [en]
detritiation techniques, fuel cycle, ITER, nitrogen injection, fusion machines, asdex-upgrade, tore-supra, 1st wall, removal, carbon, jet, tiles, retention
Identifiers
URN: urn:nbn:se:kth:diva-17119DOI: 10.1016/j.fusengdes.2007.05.047ISI: 000250980100114Scopus ID: 2-s2.0-35148849784OAI: oai:DiVA.org:kth-17119DiVA: diva2:335162
Note
QC 20100525Available 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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