SOLPS-ITER modeling of ASDEX Upgrade L-mode detachment states

Wu, Haosheng; Subba, F.; Wischmeier, M.; Cavedon, M.; Zanino, Roberto

doi:10.1088/1361-6587/ac1568

Cited by 15 publications

(15 citation statements)

References 18 publications

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“…This finding implies a potential lack of a transport mechanism in SOLPS-ITER or, perhaps, the diffusion coefficients used in the simulations are too low or spatially dependent. The latter concurs with other works using spatially varying transport coefficients to capture detached plasmas [35][36][37].…”

Section: Electron Density Temperature and Neutral Atomic Density Comp...supporting

confidence: 90%

A spectroscopic inference and SOLPS-ITER comparison of flux-resolved edge plasma parameters in detachment experiments on TCV

et al. 2022

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This work presents the use of a collisional-radiative model to infer plasma parameters from 2D emissivities of several deuterium Balmer lines. The emissivities were obtained by MANTIS, an absolutely calibrated, 10-camera imaging polychromator with < 5 mm spatial resolution, up to 800 Hz frame rate, viewing the lower divertor tangentially. Our analysis of those image frames generates 2D maps of plasma parameters such as electron density, temperature, neutral atomic density and the reaction rates for ionisation, recombination and charge exchange as a function of time. The analysis is compared and validated against a SOLPS-ITER simulation accounting for drifts. The results are compared against the simulation in 2D, radial and poloidal profiles to probe the numerous effects of particle transport in the Scrape- Off Layer, in particular in the approach to detached divertor leg conditions. The inferred inner divertor leg radial profiles of the electron density and temperature were consistent with the SOLPS-ITER predictions. A significant transport of particles to the private flux region is found experimentally, that is not captured in the simulation. The simulation diverges from the experiment at the outer divertor target, where the plasma emission appears to be consistent with the emission driven by plasma-molecule interactions. Our analysis also shows prospects for aiding the power exhaust control efforts by potentially providing an optical tracking of the particle balance in the divertor.

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Section: Electron Density Temperature and Neutral Atomic Density Comp...supporting

confidence: 90%

A spectroscopic inference and SOLPS-ITER comparison of flux-resolved edge plasma parameters in detachment experiments on TCV

et al. 2022

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“…SOLPS is a boundary plasma code composed of two coupled codes, i.e. B2.5 (a multi-fluid code for plasma transport calculation) and EIRENE (a Monte-Carlo code for neutral transport calculation) [55], and widely applied to many tokamaks to study the divertor physics and boundary plasma transport [8,10,39,[56][57][58][59][60][61][62][63][64][65][66][67][68][69]. The latest version SOLPS-ITER introduces advanced models for the drift effect and neutral transport [70] and has been recognized as an effective tool for studying the effect of drift on the SOL plasma [42,43,45].…”

Section: Simulation Schemementioning

confidence: 99%

Simulation study of the influence of E× B drift on tungsten impurity transport in the scrape-off layer

Guo,

Xu,

Mao

et al. 2023

Nucl. Fusion

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Future fusion reactors such as ITER have adopted tungsten (W) as the plasma-facing materials (PFMs) in the divertor region. It is crucial to keep the W concentration in the core plasma at an extremely low level. Great efforts have been put forward on understanding the W transport in the scrape-off layer (SOL), which is related to the source of the core W contamination. In this work, the influence of E×B drift on the W impurity transport in the SOL is studied by numerical simulations for a model case based on EAST upper single-null configuration with high recycling divertor plasma. The W transport is simulated using DIVIMP on the background plasma obtained from SOLPS-ITER simulation including drifts. The E×B drift of the W ions is introduced according to the background electric field. Therefore, both the direct E×B drift effect of W ion itself and the indirect effect via background plasma on the W transport process in the SOL can be studied. We focus on the influence on the flux of W impurities entering confined plasma across the last closed flux surface Γenter, which is expected to be proportional to the core W concentration. It is found that Γenter is mainly from the outer (inner) target under favorable (unfavorable) toroidal field BT, and can be increased by more than one order of magnitude compared with the case without drifts. It reflects the significant influence of E×B drift effects. The detailed effects due to the background plasma and the poloidal and radial E×B drift of W ion, as well as the related mechanisms, are analyzed for the three stages of W transport in the SOL, including the effective sputtering from the target, the leakage from the divertor and the entry into the confined plasma.

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“…In SOLPS-ITER, the particle balance equation in steady state for ions is calculated by [32,33,35,44,45]…”

Section: Simulation Modelmentioning

confidence: 99%

“…In this work, the main plasma is D + . The poloidal (Γ D + x ) and radial D + flux (Γ D + y ) are given by [32,33,35,45,46]…”

Section: Simulation Modelmentioning

confidence: 99%

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The influence of full drifts on density shoulder formation at the midplane by numerical modeling

et al. 2022

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The density shoulder at midplane may influence core plasma confinement during H-mode discharge, thus affecting long-pulse steady-state discharge. The drifts in the edge plasma plays remarkable role in the plasma transport and divertor operation regime, which determine the density shoulder formation (DSF). In this work, the SOLPS-ITER code package is used to evaluate the influence of full drifts on DSF in poloidal- and radial- coordinates. The open divertor of DIII-D like geometry with weak neutral compression is chosen for the modeling. Cases without drifts, with only E×B drifts in forward Bt, and with full drifts in both forward and reversed Bt are simulated for comparison. It is confirmed that the high upstream density promotes DSF when the drift is not considered, which has also been observed by various investigations. When the drifts are taken into account, the divertor in-out asymmetry (or upstream ionization source) is determined by the direction of Bt due to the variation of particle transport, thus the shoulder can be facilitated or suppressed. Two mechanisms of DSF with full drifts are elucidated: (1) the E×B and B×∇B drifts promote DSF at inner midplane (IMP) via raising ionization source (at IMP) in forward Bt; (2) the drifts contribute to DSF at outer midplane (OMP) by enhancing the radial transport in reversed Bt. In high recycling regime, the ionization is the dominant term for DSF, while in low recycling regime the enhanced radial transport by B×∇B drift plays more important role in DSF. Comprehensively understanding the DSF mechanisms is of great importance for the improvement of core-edge compatibility in the fusion reactor.

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SOLPS-ITER modeling of ASDEX Upgrade L-mode detachment states

Cited by 15 publications

References 18 publications

A spectroscopic inference and SOLPS-ITER comparison of flux-resolved edge plasma parameters in detachment experiments on TCV

A spectroscopic inference and SOLPS-ITER comparison of flux-resolved edge plasma parameters in detachment experiments on TCV

Simulation study of the influence of E× B drift on tungsten impurity transport in the scrape-off layer

The influence of full drifts on density shoulder formation at the midplane by numerical modeling

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