Multi machine scaling of fuel retention in 4 carbon dominated tokamaks

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

doi:10.1016/j.jnucmat.2011.01.132

Multi machine scaling of fuel retention in 4 carbon dominated tokamaks

E. Tsitrone^*
, B. Pégourié
, Y. Marandet
, Jari Likonen
, et al.

^*Corresponding author for this work

French National Center for Scientific Research (CNRS)
Max-Planck-Institut für Plasmaphysik (IPP)
Forschungszentrum Jülich GmbH (FZJ)
KTH Royal Institute of Technology
Culham Science Centre
MIT Massachusetts Institute of Technology
University of California System
Institut de Recherche sur la Fusion par Confinement Magnétique (IRFM)
Aix-Marseille Université

Research output: Contribution to journal › Article › Scientific › peer-review

19 Citations (Scopus)

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
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

Cite this

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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 and \{et al.\}",

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

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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

AU - et al.

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

Abstract

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