<scp>SOLEDGE3X</scp> full vessel plasma simulations for computation of <scp>ITER</scp> first‐wall fluxes

Rivals, N.; Tamain, P.; Marandet, Y.; Bonnin, X.; Bufferand, Hugo; Pitts, R.A.; Falchetto, G.; Yang, Hao; Ciraolo, Guido

doi:10.1002/ctpp.202100182

Cited by 3 publications

(2 citation statements)

References 16 publications

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“…The threshold level is also expected to be affected by cross-field drifts, which generally cause asymmetry in the inner and outer divertor fluxes and may lead to rapid transitions in the divertor state [23,24], although at higher levels of detachment (high p div ) the effect drifts on the divertor fluxes is reduced [19]. The impact of the validity of the plasmaneutral reaction rate coefficients at low T e values, including treatment of extrapolation, can also affect the convergence behaviour and steady-state solutions [25,26]. Radiation transport (not included here), has also been shown to affect stability for detached plasma simulations [18].…”

Section: Extension Of the Primary Databasementioning

confidence: 99%

High gas throughput SOLPS-ITER simulations extending the ITER database to strong detachment

et al. 2022

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SOLPS-ITER simulations performed for $Q_{DT}$ = 10, $P_{SOL}$ = 100 MW burning plasmas on ITER extend the existing database to high values of separatrix averaged neon impurity concentration ($\cne$ $\approx$ 6\%) and divertor neutral pressure ($\pdiv$ $>$ 25 Pa) in order to determine the heat flux mitigation capability of these scenarios and whether strongly detached states are accessible. In the existing database of ITER simulations, the level of detachment was limited to cases where the integral ion flux to the outer target was greater than 80\% of the value at rollover, with the impurity radiation localized near the target. With the possibility of narrow heat flux channels and increased deposited power due to tile shaping, it is important to explore operation at a higher degree of detachment. Two series of simulations were explored to extend the database of SOLPS simulations. By increasing the deuterium and neon puff rates proportionally, the peak divertor energy flux ($\qpm$) is decreased from 5 to 3 $\mathrm{MW/m^2}$ while $\pdiv$ increased from 11 to 27 Pa. By increasing only the neon puff, $q_{\perp,max}$ can be reduced to $\mathrm{< 1 MW/m^2}$ while $\pdiv$ is maintained at $\sim 11$ Pa. As the neon puff level is increased, the position of the impurity radiation peak is shifted towards the X-point. At the highest neon puff levels with steady-state solutions, the electron temperature is reduced below 1 eV across 50 cm of each divertor target. The new cases extend previously observed tight relationships in power and momentum loss factors to low electron temperature.

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Section: Extension Of the Primary Databasementioning

confidence: 99%

High gas throughput SOLPS-ITER simulations extending the ITER database to strong detachment

et al. 2022

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“…The edge and scrape-off layer (SOL) regions of a tokamak plasma are turbulent mainly owing to the drift/ interchange instability driven by density/pressure inhomogeneity. Several authors have studied plasma turbulence theoretically and numerically in the presence [1][2][3][4][5][6][7][8][9][10][11][12] and absence of the finite ion temperature gradient [13][14][15][16][17][18][19][20]. In the presence of the ion temperature, the state variable with a background gradient acting as a free energy source can drive the plasma into unstable and hence into turbulent.…”

Section: Introductionmentioning

confidence: 99%

Ion temperature dynamics for the edge and scrape-off layer plasma turbulence: role of gyro-viscosity and vorticity

Bisai

2024

Phys. Scr.

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In the presence of magnetic curvature and density/pressure inhomogeneity, the edge and scrape-off layer (SOL) regions of a tokamak plasma are highly turbulent mainly because of drift/interchange instability mechanisms. The divergence of ion polarization drift contains the ion diamagnetic drift and ExB drift velocity to define the plasma vorticity and convection of fluid, which can be approximated in several ways using various combinations of these two drifts. Here, in this work, three different approximations are used to represent three different models and are solved numerically. The numerical results indicate basic turbulence features are widely different from the three different models. As these models provide different results, therefore, one must be careful to use these approximations for the description of turbulence. This work may be useful in choosing appropriate approximations to include ion temperature gradients for the turbulence studies on tokamaks/stellarators. The role of gyro-viscosity for plasma turbulence has been identified in this work.

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Self‐organization of plasma edge turbulence in interaction with recycling neutrals

Quadri,

Tamain,

Marandet

et al. 2024

Contrib. Plasma Phys

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Experimental results from several tokamaks suggest a strong impact of divertor density regimes on turbulent transport in the edge plasma. Reciprocally, the change in transverse transport and SOL width affects the access to density regimes, making it a fundamental topic for heat exhaust issue. Such phenomenology is highly nonlinear and can only be approached quantitatively using numerical simulations treating turbulence and neutrals recycling physics self‐consistently. In this study, the SOLEDGE3X edge multi‐fluid code is used to investigate the mutual interaction between edge plasma turbulence and neutrals recycling. A fluid neutrals model based on the assumption of a charge‐exchange‐dominated plasma‐neutral interaction has been implemented. Two simulations in circular geometry are compared: one without neutrals, where the particle flux is driven by a constant in flux from the core region, and the other one with neutrals recycling included in which the particle input to the system is self‐consistently injected by a gas puff from the midplane. The presence of the neutrals triggers three types of perturbations on the plasma: a local and non‐axisymmetric one driven by the gas puff, a global perturbation affecting both profiles and turbulence properties in the whole domain, and a local one in the vicinity of the limiter where recycling occurs. The largest effect of the inclusion of self‐consistent neutrals recycling is a large‐scale reorganization of the plasma profiles and turbulence properties due to the dissociation of particle and energy fluxes. These effects are expected to be more important at higher densities regimes or in diverted configuration.

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SOLEDGE3X full vessel plasma simulations for computation of ITER first‐wall fluxes

Cited by 3 publications

References 16 publications

High gas throughput SOLPS-ITER simulations extending the ITER database to strong detachment

High gas throughput SOLPS-ITER simulations extending the ITER database to strong detachment

Ion temperature dynamics for the edge and scrape-off layer plasma turbulence: role of gyro-viscosity and vorticity

Self‐organization of plasma edge turbulence in interaction with recycling neutrals

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