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Multi machine scaling of fuel retention in 4 carbon dominated tokamaks
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2011 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 415, no 1, S735-S739 p.Article in journal (Refereed) Published
Abstract [en]

In order to benchmark predictions for the in vessel tritium inventory in ITER, a survey of fuel retention measured in 4 carbon dominated tokamaks (TEXTOR, ASDEX Upgrade in the 2002-2003 carbon configuration, Tore Supra and JET) was performed, showing retention rates from similar to 1 g D/h in TEXTOR (L mode, limiter machine) up to similar to 6-12 g D/h in AUG (H mode, divertor machine). A simple scaling used for ITER predictions is applied for comparison with experimental values: (1) estimate of wall fluxes, (2) estimate of the gross carbon erosion, (3) estimate of the net erosion/redeposition assuming a redeposition fraction and (4) estimate of the retention rate using D/C ratio scalings. The validity of each step is discussed, showing that this approach yields the right order of magnitude, but tends to underestimate the experimental values unless a high wall flux, a low local redeposition fraction and/or a high D/C ratio are used.

Place, publisher, year, edition, pages
2011. Vol. 415, no 1, S735-S739 p.
National Category
Fusion, Plasma and Space Physics
URN: urn:nbn:se:kth:diva-90679DOI: 10.1016/j.jnucmat.2011.01.132ISI: 000298128100168ScopusID: 2-s2.0-80054840239OAI: diva2:506014
QC 20120227Available from: 2012-02-27 Created: 2012-02-27 Last updated: 2012-02-27Bibliographically approved

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Rubel, Marek
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Fusion Plasma PhysicsAlfvén Laboratory Centre for Space and Fusion Plasma Physics
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