Multi machine scaling of fuel retention in 4 carbon dominated tokamaks

E. Tsitrone, B. Pégourié, J.F. Artaud, C. Brosset, J. Bucalossi, Y. Corre, T. Dittmar, E. Gauthier, P. Languille, F. Linez, T. Loarer, Y. Marandet, C. Martin, P. Roubin, A. Kallenbach, K. Krieger, M. Mayer, R. Neu, V. Rohde, J. RothS. Brezinsek, A. Kirschner, A. Kreter, A. Litnovsky, V. Philipps, P. Wienhold, M. Rubel, J. Likonen, P. Coad, B. Lipschultz, R. Doerner

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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 ∼1 g D/h in TEXTOR (L mode, limiter machine) up 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.
Original languageEnglish
JournalJournal of Nuclear Materials
Issue number1 SUPPL
Publication statusPublished - 1 Aug 2011

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