Multi machine scaling of fuel retention in 4 carbon dominated tokamaks

E. Tsitrone; B. Pégourié; Y. Marandet; Jari Likonen

doi:10.1016/j.jnucmat.2011.01.132

Multi machine scaling of fuel retention in 4 carbon dominated tokamaks

E. Tsitrone (Corresponding Author), B. Pégourié, Y. Marandet, Jari Likonen

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Abstract

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 language	English
Pages (from-to)	S735-S739
Number of pages	5
Journal	Journal of Nuclear Materials
Volume	415
Issue number	1
DOIs	https://doi.org/10.1016/j.jnucmat.2011.01.132
Publication status	Published - 2011
MoE publication type	A1 Journal article-refereed
Event	19th International Conference on Plasma Surface Interactions in Controlled Fusion Devices, PSI-19 - San Diego, United States Duration: 24 May 2010 → 28 May 2010

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10.1016/j.jnucmat.2011.01.132

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title = "Multi machine scaling of fuel retention in 4 carbon dominated tokamaks",

abstract = "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.",

author = "E. Tsitrone and B. P{\'e}gouri{\'e} and Y. Marandet and Jari Likonen",

year = "2011",

doi = "10.1016/j.jnucmat.2011.01.132",

language = "English",

volume = "415",

pages = "S735--S739",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier B.V.",

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note = "19th International Conference on Plasma Surface Interactions in Controlled Fusion Devices, PSI-19 ; Conference date: 24-05-2010 Through 28-05-2010",

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TY - JOUR

T1 - Multi machine scaling of fuel retention in 4 carbon dominated tokamaks

AU - Tsitrone, E.

AU - Pégourié, B.

AU - Marandet, Y.

AU - Likonen, Jari

PY - 2011

Y1 - 2011

N2 - 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.

AB - 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.

U2 - 10.1016/j.jnucmat.2011.01.132

DO - 10.1016/j.jnucmat.2011.01.132

M3 - Article

SN - 0022-3115

VL - 415

SP - S735-S739

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - 1

T2 - 19th International Conference on Plasma Surface Interactions in Controlled Fusion Devices, PSI-19

Y2 - 24 May 2010 through 28 May 2010

ER -

Multi machine scaling of fuel retention in 4 carbon dominated tokamaks

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