Modeling of ITER Edge Plasma in the Presence of Resonant Magnetic Perturbations

Rozhansky, V.; Veselova, I.; Voskoboynikov, S.; Coster, D.

doi:10.1002/ctpp.201610056

Cited by 6 publications

(5 citation statements)

References 12 publications

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“…In the confined region, the radial electric field, as shown in figure 4, is close to its neoclassical value computed analytically according to the expression in [3], which is typical for simulations with SOLPS5.2 for existing tokamaks [3] and for ITER [23]. For Case #1b at lower divertor pressure and lower separatrix density, the radial electric field in the pedestal region is stronger due to the larger neoclassical contribution associated with the density gradient, figure 5(a).…”

Section: Electrostatic Potentialsupporting

confidence: 73%

SOLPS-ITER modelling of ITER edge plasma with drifts and currents

et al. 2020

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Using the new version of the SOLPS plasma boundary code package, SOLPS-ITER, the paper presents the first ever simulations of the ITER burning baseline H-mode edge plasma with drifts and currents activated. Neon (Ne) seeded discharges for divertor power dissipation are considered. The results for divertor and scrape-off layer (SOL) parameters with and without drifts are compared, both for the SOLPS-ITER simulations and against the earlier SOLPS-4.3 modelling (which did not include a drift description) constituting the bulk of the existing ITER divertor simulation database. Whereas the drift effect on the equatorial midplane (main chamber) density and temperature profiles is moderate, drifts increase the peak heat flow to the outer divertor target. This effect is more pronounced for regimes with low sub-divertor neutral pressure, when even drift-free SOLPS4.3 simulations find strong out-in target power asymmetries. An important conclusion is thus that if ITER operates as expected with partially detached divertor targets, drifts should not influence the power handling, but that in the case of divertor reattachment, they will act to worsen the target loading, increasing the need for vigilance in detachment control. Comparing SOLPS-4.3 and SOLPS-ITER results for the key peak target heat flux versus sub-divertor neutral pressure operating domain, SOLPS-ITER with drifts predicts a narrower operational window for the divertor pressure.

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Section: Electrostatic Potentialsupporting

confidence: 73%

SOLPS-ITER modelling of ITER edge plasma with drifts and currents

et al. 2020

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“…Similar to results from simulations with SOLPS5.2 [17,27] and SOLPS-ITER [28] for present tokamaks [17] and for ITER [27,28], radial electric field (E r ) in the outer core is found to be close to its neoclassical value, as shown in figure 4. According to equation (42) in [17], neoclassical value of E r depends on the parallel velocity (  V ), radial density ( / ¶ ¶ n r) and temperature ( / ¶ ¶ T r) gradients.…”

Section: Electrostatic Potential and Fieldsupporting

confidence: 83%

SOLPS-ITER drift modeling of neon impurity seeded plasmas in EAST with favorable and unfavorable toroidal magnetic field direction

Wang

Liang

et al. 2023

Plasma Sci. Technol.

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To better understand divertor detachment and asymmetry in EAST, SOLPS-ITER drift modeling of neon impurity seeded plasmas in favorable/unfavorable toroidal magnetic field (BT) has been performed. Firstly, electrostatic potential/field (ϕ/E) distribution has been analyzed, to make sure that ϕ and E are correctly described and to better understand drift-driven processes. After that, drift effects on divertor detachment and asymmetry have been focused on. In accordance with the corresponding experimental observations, simulation results demonstrate that in favorable BT the onset of detachment is highly asymmetric between the inner and outer divertors; and reversing BT can significantly decrease the magnitude of in-out asymmetry in the onset of detachment, physics reasons for which have been explored. It is found that, apart from the well-known EB drift particle flow from one divertor to the other through the private flux region (PFR), SOL heat flow, which is much more asymmetrically distributed between the HFS and LFS for favorable BT than that for unfavorable BT, is also a critical parameter affecting divertor detachment and asymmetry. During detachment, upstream pressure (Pu) reduction occurs and tends to be more dramatical in the colder side than that in the hotter side. The convective SOL heat flow, emerging due to in-out asymmetry in Pu reduction, is found to be critical for understanding divertor detachment and asymmetry observed in EAST. To better understand the calculated drastic power radiation in the core and SOL, drift effects on divertor leakage/retention of neon in EAST with both BT directions have been addressed for the first time, by analyzing profile of poloidal neon velocity and that of neon ionization source from atoms. This work can be a reference for future numeric simulations performed more closely related to experimental regimes.

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“…The test calculation was made to confirm applicability of this code for beryllium transport. Earlier the SOLPS-ITER code was used for modeling of different tokamaks with different sorts of impurities (such as He, N, Ne, C) such as ITER [3], Globus-M [4], ASDEX Upgrade [5], JET [6], DIII-D [7], Alcator C-Mod [8] and others.…”

Section: Introductionmentioning

confidence: 99%

SOLPS-ITER modeling of beryllium trace impurity in ITER

Makarov

2018

MATEC Web Conf.

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Beryllium transport modeling was carried out in the trace impurity regime by SOLPS-ITER code for tokamak ITER. It is valuable for developing of diagnostics protection from beryllium deposition. TRIM reflection model and Bogdanskii formula sputtering model were applied. The idea is to show possibility of using this code for beryllium transport. This code has key advantage comparing to other codes, which study beryllium transport, because in it the main plasma and impurities are described self-consistently. Therefore, if beryllium affect the background plasma, only this code can take this effect into account. Test calculations were performed with suppressed sputtering yield by 10 times, to reach trace impurity regime. Main features of behavior of beryllium in the tokamak were studied, however under restriction of static wall conditions. Sources, sinks, fluxes and density distribution were determined. In this test calculation plasma state kept unchanged as expected. Distribution of impinging and absorbed fluxes on the outer divertor plate were established in the position of divertor diagnostics. Main ways for the further improvement are suggested.

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Modeling of ITER Edge Plasma in the Presence of Resonant Magnetic Perturbations

Cited by 6 publications

References 12 publications

SOLPS-ITER modelling of ITER edge plasma with drifts and currents

SOLPS-ITER modelling of ITER edge plasma with drifts and currents

SOLPS-ITER drift modeling of neon impurity seeded plasmas in EAST with favorable and unfavorable toroidal magnetic field direction

SOLPS-ITER modeling of beryllium trace impurity in ITER

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