Modelling of the material transport and layer formation in the divertor of JET: Comparison of ITER-like wall with full carbon wall conditions

A. Kirschner, D. Matveev, D. Borodin, M. Airila, S. Brezinsek, M. Groth, S. Wiesen, A. Widdowson, J. Beal, H. G. Esser, J. Likonen, N. Bekris, R. Ding

Research output: Contribution to journalArticleScientificpeer-review

19 Citations (Scopus)

Abstract

Abstract Impurity transport within the inner JET divertor has been modelled with ERO to estimate the transport to and the resulting deposition at remote areas. Various parametric studies involving divertor plasma conditions and strike point position have been performed. In JET-ILW (beryllium main chamber and tungsten divertor) beryllium, flowing from the main chamber into the divertor and then effectively reflected at the tungsten divertor tiles, is transported to remote areas. The tungsten flux to remote areas in L-Mode is in comparison to the beryllium flux negligible due to small sputtering. However, tungsten is sputtered during ELMs in H-Mode conditions. Nevertheless, depending on the plasma conditions, strike point position and the location of the remote area, the maximum resulting tungsten flux to remote areas is at least ∼3 times lower than the corresponding beryllium flux. Modelled beryllium and tungsten deposition on a rotating collector probe located below tile 5 is in good agreement with measurements if the beryllium influx into the inner divertor is assumed to be in the range of 0.1% relative to the deuterium ion flux and erosion due to fast charge exchange neutrals is considered. Comparison between JET-ILW and JET-C is presented.

Original languageEnglish
Article number48569
Pages (from-to)116-122
Number of pages7
JournalJournal of Nuclear Materials
Volume463
DOIs
Publication statusPublished - 22 Jul 2015
MoE publication typeA1 Journal article-refereed

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Beryllium
Tungsten
beryllium
tungsten
Carbon
Fluxes
carbon
tiles
Tile
chambers
Plasmas
Deuterium
charge exchange
accumulators
erosion
Sputtering
deuterium
Erosion
Ion exchange
sputtering

Cite this

Kirschner, A. ; Matveev, D. ; Borodin, D. ; Airila, M. ; Brezinsek, S. ; Groth, M. ; Wiesen, S. ; Widdowson, A. ; Beal, J. ; Esser, H. G. ; Likonen, J. ; Bekris, N. ; Ding, R. / Modelling of the material transport and layer formation in the divertor of JET : Comparison of ITER-like wall with full carbon wall conditions. In: Journal of Nuclear Materials. 2015 ; Vol. 463. pp. 116-122.
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abstract = "Abstract Impurity transport within the inner JET divertor has been modelled with ERO to estimate the transport to and the resulting deposition at remote areas. Various parametric studies involving divertor plasma conditions and strike point position have been performed. In JET-ILW (beryllium main chamber and tungsten divertor) beryllium, flowing from the main chamber into the divertor and then effectively reflected at the tungsten divertor tiles, is transported to remote areas. The tungsten flux to remote areas in L-Mode is in comparison to the beryllium flux negligible due to small sputtering. However, tungsten is sputtered during ELMs in H-Mode conditions. Nevertheless, depending on the plasma conditions, strike point position and the location of the remote area, the maximum resulting tungsten flux to remote areas is at least ∼3 times lower than the corresponding beryllium flux. Modelled beryllium and tungsten deposition on a rotating collector probe located below tile 5 is in good agreement with measurements if the beryllium influx into the inner divertor is assumed to be in the range of 0.1{\%} relative to the deuterium ion flux and erosion due to fast charge exchange neutrals is considered. Comparison between JET-ILW and JET-C is presented.",
author = "A. Kirschner and D. Matveev and D. Borodin and M. Airila and S. Brezinsek and M. Groth and S. Wiesen and A. Widdowson and J. Beal and Esser, {H. G.} and J. Likonen and N. Bekris and R. Ding",
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Kirschner, A, Matveev, D, Borodin, D, Airila, M, Brezinsek, S, Groth, M, Wiesen, S, Widdowson, A, Beal, J, Esser, HG, Likonen, J, Bekris, N & Ding, R 2015, 'Modelling of the material transport and layer formation in the divertor of JET: Comparison of ITER-like wall with full carbon wall conditions', Journal of Nuclear Materials, vol. 463, 48569, pp. 116-122. https://doi.org/10.1016/j.jnucmat.2014.10.072

Modelling of the material transport and layer formation in the divertor of JET : Comparison of ITER-like wall with full carbon wall conditions. / Kirschner, A.; Matveev, D.; Borodin, D.; Airila, M.; Brezinsek, S.; Groth, M.; Wiesen, S.; Widdowson, A.; Beal, J.; Esser, H. G.; Likonen, J.; Bekris, N.; Ding, R.

In: Journal of Nuclear Materials, Vol. 463, 48569, 22.07.2015, p. 116-122.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Modelling of the material transport and layer formation in the divertor of JET

T2 - Comparison of ITER-like wall with full carbon wall conditions

AU - Kirschner, A.

AU - Matveev, D.

AU - Borodin, D.

AU - Airila, M.

AU - Brezinsek, S.

AU - Groth, M.

AU - Wiesen, S.

AU - Widdowson, A.

AU - Beal, J.

AU - Esser, H. G.

AU - Likonen, J.

AU - Bekris, N.

AU - Ding, R.

PY - 2015/7/22

Y1 - 2015/7/22

N2 - Abstract Impurity transport within the inner JET divertor has been modelled with ERO to estimate the transport to and the resulting deposition at remote areas. Various parametric studies involving divertor plasma conditions and strike point position have been performed. In JET-ILW (beryllium main chamber and tungsten divertor) beryllium, flowing from the main chamber into the divertor and then effectively reflected at the tungsten divertor tiles, is transported to remote areas. The tungsten flux to remote areas in L-Mode is in comparison to the beryllium flux negligible due to small sputtering. However, tungsten is sputtered during ELMs in H-Mode conditions. Nevertheless, depending on the plasma conditions, strike point position and the location of the remote area, the maximum resulting tungsten flux to remote areas is at least ∼3 times lower than the corresponding beryllium flux. Modelled beryllium and tungsten deposition on a rotating collector probe located below tile 5 is in good agreement with measurements if the beryllium influx into the inner divertor is assumed to be in the range of 0.1% relative to the deuterium ion flux and erosion due to fast charge exchange neutrals is considered. Comparison between JET-ILW and JET-C is presented.

AB - Abstract Impurity transport within the inner JET divertor has been modelled with ERO to estimate the transport to and the resulting deposition at remote areas. Various parametric studies involving divertor plasma conditions and strike point position have been performed. In JET-ILW (beryllium main chamber and tungsten divertor) beryllium, flowing from the main chamber into the divertor and then effectively reflected at the tungsten divertor tiles, is transported to remote areas. The tungsten flux to remote areas in L-Mode is in comparison to the beryllium flux negligible due to small sputtering. However, tungsten is sputtered during ELMs in H-Mode conditions. Nevertheless, depending on the plasma conditions, strike point position and the location of the remote area, the maximum resulting tungsten flux to remote areas is at least ∼3 times lower than the corresponding beryllium flux. Modelled beryllium and tungsten deposition on a rotating collector probe located below tile 5 is in good agreement with measurements if the beryllium influx into the inner divertor is assumed to be in the range of 0.1% relative to the deuterium ion flux and erosion due to fast charge exchange neutrals is considered. Comparison between JET-ILW and JET-C is presented.

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U2 - 10.1016/j.jnucmat.2014.10.072

DO - 10.1016/j.jnucmat.2014.10.072

M3 - Article

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JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

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