SOLPS modelling of ASDEX upgrade H-mode plasma

Chankin, A.; Coster, D.; Dux, R.; Fuchs, C.; Haas, G.; Herrmann, A.; Horton, L.D.; Kallenbach, A.; Kaufmann, Michael; Konz, C.; Lackner, K.; Maggi, C. F.; Müller, Hans; Neuhäuser, J.; Pugno, R.; Reich, M.; Schneider, W.

doi:10.1088/0741-3335/48/6/010

Cited by 98 publications

(128 citation statements)

References 28 publications

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“…This is consistent with the observation in ASDEX-U (Chankin et al, 2006) and DIII-D (Callen et al, 2010) that ion thermal transport is near neoclassical at the plasma boundary in deuterium Hmode plasmas, and with the general result of substantially improved particle confinement in deuterium H-modes.…”

Section: Drift-based Sol Particle Widthsupporting

confidence: 90%

Heuristic Drift-based Model of the Power Scrape-off width in H-mode Tokamaks

Goldston¹

2011

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An heuristic model for the plasma scrape-off width in H-mode plasmas is introduced. Grad B and curv B drifts into the SOL are balanced against sonic parallel flows out of the SOL, to the divertor plates. The overall particle flow pattern posited is a modification for open field lines of Pfirsch-Shlüter flows to include sinks to the divertors. These assumptions result in an estimated SOL width of ~ 2aρ p /R. They also result in a first-principles calculation of the particle confinement time of H-mode plasmas, qualitatively consistent with experimental observations. It is next assumed that anomalous perpendicular electron thermal diffusivity is the dominant source of heat flux across the separatrix, investing the SOL width, defined above, with heat from the main plasma. The separatrix temperature is calculated based on a two-point model balancing power input to the SOL with Spitzer-Härm parallel thermal conduction losses to the divertor. This results in a heuristic closed-form prediction for the power scrape-off width that is in reasonable quantitative agreement both in absolute magnitude and in scaling with recent experimental data from deuterium plasmas. Further work should include full numerical calculations, including all magnetic and electric drifts, as well as more thorough comparison with experimental data.

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Section: Drift-based Sol Particle Widthsupporting

confidence: 90%

Heuristic Drift-based Model of the Power Scrape-off width in H-mode Tokamaks

Goldston¹

2011

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“…In recent years, their capability to reproduce experimental observations has been questioned, particularly for plasmas with at least one of the divertor legs approaching detachment (see e.g. [4,5] and references therein). Partial divertor detachment is mandatory for achieving tolerable target power loads in a reactor.…”

Section: Introductionmentioning

confidence: 99%

L-mode radiative plasma edge studies for model validation in ASDEX Upgrade and JET

Aho-Mantila

Bernert

Coenen³

et al. 2013

Journal of Nuclear Materials

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The presently favoured option for reactor power handling combines metallic plasma-facing components and impurity seeding to achieve highly radiative scrape-off layer and divertor plasmas. It is uncertain whether tolerable divertor power loads will be obtained in this scenario, necessitating the development of predictive modelling tools. L-mode experiments with N 2 seeding have been conducted at both ASDEX Upgrade and JET for benchmarking the critically important impurity radiation models in edge fluid codes. In both machines, a roll-over in ion fluxes and a reduction in target power load is observed first in the inner divertor. The outer divertor evolves from low-recycling to conduction-limited conditions once a reduction of inner target particle load is observed. First comparisons between SOLPS5.0 simulations and N 2 seeded experiment support the observed in-out asymmetry in the effect of seeding.

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“…Severe discrepancies have been observed, for example, when simulating divertor detachment [6] or SOL plasmas with medium collisionality [7]. Despite efforts made to include new physics, by introducing various mock-up models [8] or e.g.…”

Section: Introductionmentioning

confidence: 99%

Outer divertor of ASDEX Upgrade in low-density L-mode discharges in forward and reversed magnetic field: I. Comparison between measured plasma conditions and SOLPS5.0 code calculations

et al. 2012

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Abstract. The scrape-off layer and divertor plasma conditions have been carefully analysed in dedicated ASDEX Upgrade experiments consisting of lowdensity L-mode discharges, with both forward and reversed toroidal magnetic field and plasma current. In forward field, the outer divertor plasma is in a lowrecycling regime with peak target temperature above 25 eV. In reversed field with similar main plasma parameters, the target temperature is below 15 eV and the density is 5 times as high as in forward field, indicating a higher recycling regime in the outer divertor. The SOLPS5.0 code package is used to model these divertor plasmas. Specifically, it is tested whether a combination of input assumptions exists that enables matching the code solution to all outer divertor diagnostic measurements, and whether these assumptions are compatible with constraints imposed by measurements outside the outer divertor. In forward field, a good level of agreement with multiple outer target measurements is found with assumptions that simultaneously match the measured density and temperature profiles at the outer midplane, where the uncertainty in radial position of the separatrix is ±0.5 cm. Similar approaches made previously for higher recycling regimes have not led to such a good consistency between all modelled and measured outer divertor parameters. In reversed field with higher recycling in the outer divertor, a solution consistent with the outer target Langmuir probe measurements cannot be obtained, at least not without significantly compromising the match to the upstream profile measurements. Significant mismatches are observed also between the modelled and measured upstream Mach number in forward field. These discrepancies question the global validity of the plasma solutions, and their origin is not yet clear. In Part II, the analysis of outer divertor conditions is complemented by local impurity migration studies, using the divertor plasma solutions presented in this paper.

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SOLPS modelling of ASDEX upgrade H-mode plasma

Cited by 98 publications

References 28 publications

Heuristic Drift-based Model of the Power Scrape-off width in H-mode Tokamaks

Heuristic Drift-based Model of the Power Scrape-off width in H-mode Tokamaks

L-mode radiative plasma edge studies for model validation in ASDEX Upgrade and JET

Outer divertor of ASDEX Upgrade in low-density L-mode discharges in forward and reversed magnetic field: I. Comparison between measured plasma conditions and SOLPS5.0 code calculations

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