Benchmarking Tokamak edge modelling codes

Coster, D.; Bonnin, X.; Corrigan, G.; Kirnev, G.; Matthews, G. F.; Spence, James

doi:10.1016/j.jnucmat.2004.10.013

Cited by 43 publications

(40 citation statements)

References 14 publications

(10 reference statements)

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“…Almost no difference is seen in the profiles of the H α emission at the outer target, while the peak target T e is lower by ≈ 2 eV for the case with the detailed neutral model. A weak influence of the choice of a pumping model on divertor parameters has been found earlier in [24].…”

Section: (I) Use Of a More Realistic Neutral Description In The Vacuumentioning

confidence: 75%

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SOLPS modelling of ASDEX upgrade H-mode plasma

Chankin¹,

Coster²,

Dux³

et al. 2006

Plasma Phys. Control. Fusion

116

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A low density H-mode plasma has been selected for detailed inter-ELM modelling by the SOLPS code package, with the coupled treatment of its plasma (fluid code B2) and neutral (Monte-Carlo code Eirene) parts. Good quality measured midplane density and temperature profiles, covering the pedestal region and stretching far into the SOL, as well as several other parameters and profiles measured in the divertor, have enabled testing the consistency of code solutions with experiment. Once the upstream, midplane profiles, have been fitted, and the global parameters (e.g. input power into the computational grid, radiated power) matched, the code reproduced experimental profiles and control parameters in the divertor with the accuracy within a factor 2. Deviations of modelled parameters from the experiment were found around the strike point position where most of the power was deposited on the target. The deviations are consistent among themselves and all point to one common problem with the modelling: the predicted divertor electron temperature is too low, and the density too high, compared with the experiment. The largest inconsistency between the code and experiment was in the magnitude of the peak H α radiation in the outer divertor, which was larger by a factor of 2 in the code simulations. In addition, the code predicts a somewhat higher sub-divertor neutral flux, but lower carbon impurity content in the edge plasma than in the experiment, as well as lower CIII emission. The discrepancy between H α profiles can to a large degree be attributed to profile effects: the simulated H α emission profiles are narrower than in the experiment, reflecting the tendency for the neutral-plasma mix to congregate excessively around the strike point in the modelling. At the same time, the integrated H α emission matches very well with the experiment.Extensive sensitivity studies of the influence of variations in input parameters and assumptions of the code on the modelled divertor conditions have been conducted. They have not resulted in an identification of any SOLPS input/control parameters capable of removing the main disagreement between the code output and experiment. A possibility for parallel transport effects related to low collisionality to increase the effective plasma temperature near the strike point position, or for increased perpendicular transport by neutrals (due to some missing reactions in Eirene) to widen the target profiles, will be explored in the future.2

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Section: (I) Use Of a More Realistic Neutral Description In The Vacuumentioning

confidence: 75%

“…The choice of the ion flux limiter also had a very little impact on the T i in the divertor; further upstream, in the main SOL, however, the ion heat flux limiter was found to affect poloidal T i profiles quite significantly [24].…”

Section: (B) Variation Of Electron and Ion Heat Flux Limitersmentioning

confidence: 99%

SOLPS modelling of ASDEX upgrade H-mode plasma

Chankin¹,

Coster²,

Dux³

et al. 2006

Plasma Phys. Control. Fusion

116

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“…The applied set of atomic and molecular processes includes ionization and charge-exchange of D atoms, ionization and dissociation of D 2 molecules and their elastic collisions with D + ions, radiative and 3-body volume recombination of D + ions. The standard JET test case [10] was used for the benchmark. It has magnetic equilibrium and geometry of the discharge #50401, SOL input power 2.5 MW (this corresponds to ohmic discharges).…”

Section: Code-code Benchmarkingmentioning

confidence: 99%

“…Numerical values of the coefficients which enter (10) and (11) calculated by the code are shown in Figure 2 for a selected flux tube in the inner divertor. This is a flux tube where the target incident ion flux attains its maximum (radial grid index 9).…”

Section: Wwwcpp-journalorg 4 Two-point Analysis Of the B2-eirene Somentioning

confidence: 99%

“…To focus discussion on the divertor region the upstream surface is chosen slightly above the X-point (divertor throat, poloidal grid index 29). To check the consistency of the parallel momentum and energy balance together with implementation of the boundary conditions the simulation results can be put to (10), (11) and (12). For the example considered here they hold with maximum relative error of 0.3 %.…”

Section: Wwwcpp-journalorg 4 Two-point Analysis Of the B2-eirene Somentioning

confidence: 99%

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Verification of the 2D Tokamak Edge Modelling Codes for Conditions of Detached Divertor Plasma

Kotov

Reiter

Coster

et al. 2010

Contrib. Plasma Phys.

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The paper discusses verification of the ITER edge modelling code SOLPS 4.3 (B2-EIRENE). Results of the benchmark against SOLPS 5.0 are shown for standard JET test cases. Special two-point formulas are employed in SOLPS 4.3 to analyze the results of numerical simulations. The applied relations are exact in frame of the equations solved by the B2 code. This enables simultaneous check of the parallel momentum and energy balances and boundary conditions. Transition to divertor detachment is analyzed quantitatively as it appears in the simulations in terms of the coupled momentum and energy balance.

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3D Edge Transport Studies with EMC3‐EIRENE for the Dynamic Ergodic Divertor (DED) at TEXTOR

Harting

Reiter

Feng

et al. 2008

Contrib. Plasma Phys.

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In this paper we introduce some model extensions to the energy balances of the 3D fluid Monte-Carlo code EMC3 and study their influence on the simulation results for TEXTOR-DED. We implemented local kinetic corrections to the classical parallel heat conductivity of electrons (heat flux limit). Depending on the DED configuration, a cooling effect in the outermost SOL region, resulting from the heat flux limit, can be observed. In addition, also the adiabatic cooling term 1 2 mnV 2 V , which was neglected before, was implemented into the energy iterations. This term causes a localized cooling of the ions in front of the wall, where the plasma is accelerated towards the first wall.

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Benchmarking Tokamak edge modelling codes

Cited by 43 publications

References 14 publications

SOLPS modelling of ASDEX upgrade H-mode plasma

SOLPS modelling of ASDEX upgrade H-mode plasma

Verification of the 2D Tokamak Edge Modelling Codes for Conditions of Detached Divertor Plasma

3D Edge Transport Studies with EMC3‐EIRENE for the Dynamic Ergodic Divertor (DED) at TEXTOR

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