3D fluid modelling of the edge plasma by means of a Monte Carlo technique

Feng, Y.; Sardei, F.; Kißlinger, J.

doi:10.1016/s0022-3115(98)00844-7

Cited by 130 publications

(142 citation statements)

References 3 publications

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“…The EMC3 code [14,15,16] applies a Monte Carlo method [16] to solve these equations for the edge plasma. Interactions with neutral particles are taken into account by sources (or sinks) in the balance equations S p , S m , S ee and S ei , which are calculated by the kinetic neutral transport code EIRENE [17].…”

Section: D Transport Model For the Edge Plasmamentioning

confidence: 99%

Three-dimensional edge transport simulations for DIII-D plasmas with resonant magnetic perturbations

et al. 2010

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Abstract. In the plasma scenarios currently envisaged for ITER, edge localized modes (ELMs) are a critical issue for the wall lifetime of ITER. However, a promising technique as been found to mitigate ELMs: the application of resonant magnetic perturbations (RMPs) at the plasma edge. These introduce a complex magnetic field structure in the plasma edge, affecting also plasma transport. So far, numerical models for edge plasma transport in ELM control scenarios at DIII-D include only averaged effects of RMPs or include only heat transport. Our approach includes a self-consistent fluid treatment of particle, parallel momentum and energy transport as well as kinetic neutral production and transport. This model is implemented in the EMC3-EIRENE code which is a powerful tool to investigate 3D effects of RMPs on edge transport. In the present paper we apply the EMC3-EIRENE code to conditions at the DIII-D tokamak in the presence of RMPs. We demonstrate that the magnetic field structure is reflected in the plasma structure as well, in particular we investigate the pattern of particle and heat loads on the divertor target and a 3D modulation of plasma parameter in the X-point region and near the midplane on the high field side (HFS). These findings are consistent with earlier heat transport modeling results at DIII-D as well as observations and modeling results at TEXTOR.

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Section: D Transport Model For the Edge Plasmamentioning

confidence: 99%

Three-dimensional edge transport simulations for DIII-D plasmas with resonant magnetic perturbations

et al. 2010

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“…The present studies have been performed with the 3D transport code package EMC3-EIRENE, which is a coupled version of the 3D fluid edge plasma transport code EMC3 [25,26] and the 3D kinetic neutral particle transport code EIRENE [27]. An outline of the model equations solved by the code is given in section 3.…”

Section: Introductionmentioning

confidence: 99%

Numerical analysis of particle recycling in the TEXTOR helical divertor

et al. 2012

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Abstract. The TEXTOR helical divertor is a magnetic configuration created by the application of external resonant magnetic perturbations (RMPs) with the intention to control plasma edge transport and the resulting particle and heat fluxes to the divertor target. It is confirmed by 3D computer simulations that no high-recyclinglike regime is established under TEXTOR relevant conditions, despite the fact that a transition to detachment (i.e. a saturation or even a roll-over of the recycling flux) is observed at high densities. The driving mechanisms are, distinct from apparently similar observations in poloidal divertors and stellarator divertors, a combination of volumetric power losses and enhanced upstream-to-downstream heat transport, but with no significant role of the momentum balance.

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“…1. The common SOL region for EMC3 [4] and EIRENE [5] starts from a closed flux surface just inside the inner separatrix and extends radially beyond the target to ensure that the target intercepts most of the energy and ions flowing in the SOL. The choice of the boundary condition on the outermost SOL boundary should not influence the results.…”

Section: Computational Set-upmentioning

confidence: 99%

Numerical study on CX-neutral transport and wall-sputtering in W7-AS diverted plasmas

Feng

Sardei

Grigull

et al. 2007

Journal of Nuclear Materials

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Using the 3D SOL transport code EMC3/EIRENE, the paper presents a parameter study on CX-neutral transport and Fe-release from the wall due to physical sputtering in W7-AS diverted plasmas. The studies are restricted to the CX-neutrals induced by divertor and wall recycling processes. SOL plasma and divertor and wall recycling process are self-consistently calculated by the EMC3/EIRENE code. Island density is scanned across different confinement regimes. Cross-field transport coefficients are varied to cover an appropriate uncertainty range.Core plasma is prescribed, with the density profile, however, being switched between a peaked and a flat form typically measured for low and high density diverted plasmas. Studied are the sensitivities of the flux, energy spectrum and origin of the CX-neutrals to these parameters. In particular, it is aimed to identify under what condition and to what extent the edge islands can protect the wall from physical sputtering of the CX-neutrals.

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3D fluid modelling of the edge plasma by means of a Monte Carlo technique

Cited by 130 publications

References 3 publications

Three-dimensional edge transport simulations for DIII-D plasmas with resonant magnetic perturbations

Three-dimensional edge transport simulations for DIII-D plasmas with resonant magnetic perturbations

Numerical analysis of particle recycling in the TEXTOR helical divertor

Numerical study on CX-neutral transport and wall-sputtering in W7-AS diverted plasmas

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