Multi machine scaling of fuel retention in 4 carbon dominated tokamaks

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

Research output: Contribution to journalArticleScientificpeer-review

12 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 languageEnglish
Pages (from-to)S735-S739
Number of pages5
JournalJournal of Nuclear Materials
Volume415
Issue number1
DOIs
Publication statusPublished - 2011
MoE publication typeA1 Journal article-refereed
Event19th International Conference on Plasma Surface Interactions in Controlled Fusion Devices, PSI-19 - San Diego, United States
Duration: 24 May 201028 May 2010

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Carbon
scaling
Erosion
carbon
estimates
Fluxes
erosion
Tritium
Limiters
tritium
predictions
vessels
configurations

Cite this

Tsitrone, E. ; Pégourié, B. ; Marandet, Y. ; Likonen, Jari. / Multi machine scaling of fuel retention in 4 carbon dominated tokamaks. In: Journal of Nuclear Materials. 2011 ; Vol. 415, No. 1. pp. S735-S739.
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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.",
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Multi machine scaling of fuel retention in 4 carbon dominated tokamaks. / Tsitrone, E. (Corresponding Author); Pégourié, B.; Marandet, Y.; Likonen, Jari.

In: Journal of Nuclear Materials, Vol. 415, No. 1, 2011, p. S735-S739.

Research output: Contribution to journalArticleScientificpeer-review

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

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JF - Journal of Nuclear Materials

SN - 0022-3115

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