On the role of finite grid extent in SOLPS-ITER edge plasma simulations for JET H-mode discharges with metallic wall

Wiesen, S.; Brezinsek, S.; Bonnin, X.; Delabie, E.; Frassinetti, L.; Groth, M.; Guillemaut, C.; Harrison, J.; Harting, D.; Henderson, S.; Huber, A.; Kruezi, U.; Pitts, R. A.; Wischmeier, M.

doi:10.1016/j.nme.2018.10.013

Title: On the role of finite grid extent in SOLPS-ITER edge plasma simulations for JET H-mode discharges with metallic wall

Journal Article · Tue Nov 06 00:00:00 EST 2018 · Nuclear Materials and Energy

DOI:https://doi.org/10.1016/j.nme.2018.10.013· OSTI ID:1648929

Wiesen, S. ^[1];

^[1];

^[2]; Delabie, E. ^[3]; Frassinetti, L. ^[4]; Groth, M. ^[5];

^[6]; Harrison, J. ^[7]; Harting, D. ^[7];

^[7]; Huber, A. ^[1]; Kruezi, U. ^[2]; Pitts, R. A. ^[2]; Wischmeier, M. ^[8]

Forschungszentrum Juelich (Germany). Inst. fur Energie- und Klimaforschung (IEK)
ITER Organization, St. Paul Lez Durance (France)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
KTH Royal Inst. of Technology, Stockholm (Sweden). Association VR, Fusion Plasma Physics
Aalto Univ., Espoo (Finland)
Univ. de Lisboa (Portugal). Inst. de Plasmas e Fusão Nuclear, IST
Culham Science Centre, Abingdon (United Kingdom). Culham Centre for Fusion Energy (CCFE)
Max-Planck-Inst. für Plasmaphysik, Garching (Germany)

The impact of the finite grid size in SOLPS-ITER edge plasma simulations is assessed for JET H-mode discharges with a metal wall. For a semi-horizontal divertor configuration it is shown that the separatrix density is at least 30% higher when a narrow scrape-off layer (SOL) grid width is chosen in SOLPS-ITER compared to the case for which the SOL grid width is maximised. The density increase is caused by kinetic neutrals being not confined inside the divertor region because of the reduced extent of the plasma grid. In this case, an enhanced level of reflections of energetic neutrals at the low-field side (LFS) metal divertor wall is observed. This leads to a shift of the ionisation source further upstream which must be accounted for as a numerical artefact. An overestimate in the cooling at the divertor entrance is observed in this case, identified by a reduced heat flux decay parameters λ_q^div. Otherwise and further upstream the mid-plane heat decay length λ_q parameter is not affected by any change in divertor dissipation. This confirms the assumptions made for the ITER divertor design studies, i.e. that λ_q upstream is essentially set by the assumptions for the ratio radial to parallel heat conductivity. It is also shown that even for attached conditions the decay length relations λ_ne > λ_Te > λ_q hold in the near-SOL upstream. Thus for interpretative edge plasma simulations one must take the (experimental) value of λ_ne into account, rather than λ_q, as the former actually defines the required minimum upstream SOL grid extent.

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Research Organization:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE; Euratom

Grant/Contract Number:: AC05-00OR22725; 633053

OSTI ID:: 1648929

Journal Information:: Nuclear Materials and Energy, Vol. 17; ISSN 2352-1791

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 5 works

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References (14)

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Title: On the role of finite grid extent in SOLPS-ITER edge plasma simulations for JET H-mode discharges with metallic wall

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