Modeling of the edge plasma of MAST Upgrade with a Super-X divertor including drifts and an edge transport barrier

Rozhansky, V.; Molchanov, P.; Veselova, I.; Voskoboynikov, S.; Kirk, A.; Fishpool, G.; Boerner, P.; Reiter, D.; Coster, D.

doi:10.1088/0741-3335/55/3/035005

Cited by 17 publications

(18 citation statements)

References 7 publications

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“…14, the asymmetry resulting from the drift effects would cause that the predicted L at which the transition to the detachment occurs would be longer in the bottom divertor, while an earlier transition (at shorter L ) would be found at the top target. In [17], the effect is quantified for SXD in MAST-U for low target temperatures of approximately 4 eV. One can see a drop of the peak T e at the top from 4 to 1.8 eV and only a little rise of T e at the bottom from 4 to 4.8 eV.…”

Section: Scan At Lower Temperaturementioning

confidence: 97%

Benchmarking of a 1D scrape-off layer code SOLF1D with SOLPS and its use in modelling long-legged divertors

Havlickova¹,

Fundamenski²,

Subba³

et al. 2013

Plasma Phys. Control. Fusion

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Abstract. A 1D code modelling SOL transport parallel to the magnetic field (SOLF1D) is benchmarked with 2D simulations of MAST-U SOL performed via the SOLPS code for two different collisionalities. Based on this comparison, SOLF1D is then used to model the effects of divertor leg stretching in 1D, in support of the planned Super-X divertor on MAST. The aim is to separate magnetic flux expansion from volumetric power losses due to recycling neutrals by stretching the divertor leg either vertically (∇B = 0 in the divertor) or radially (B ∝ 1/R).

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Section: Scan At Lower Temperaturementioning

confidence: 97%

Benchmarking of a 1D scrape-off layer code SOLF1D with SOLPS and its use in modelling long-legged divertors

Havlickova¹,

Fundamenski²,

Subba³

et al. 2013

Plasma Phys. Control. Fusion

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“…2) which are otherwise poloidally uniform. These diffusivities are based on [11] and an earlier benchmarking of SOLPS with experiment [13].…”

Section: Simulation Setupmentioning

confidence: 99%

“…The effect of the Super-X divertor was preliminarily investigated also in [7,8] by SOLPS5.0 and in [9] by a 1D code SOLF1D. Some of the latest results also concentrate on drift effects [10,11].…”

Section: Introductionmentioning

confidence: 99%

Investigation of conventional and Super-X divertor configurations of MAST Upgrade using scrape-off layer plasma simulation

Havlickova

Fundamenski

Wischmeier

et al. 2014

Plasma Phys. Control. Fusion

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One of the first studies of MAST Upgrade divertor configurations with SOLPS5.0 are presented. We focus on understanding main prospects associated with the novel geometry of the Super-X divertor (SXD). This includes a discussion of the effect of magnetic flux expansion and volumetric power losses on the reduction of target power loads, the effect of divertor geometry on the divertor closure and distribution of neutral species and radiation in the divertor, the role of the connection length in broadening the target wetted area. A comparison in conditions typical for MAST inter-ELM H-mode plasmas confirms improved performance of the Super-X topology resulting in significantly better divertor closure with respect to neutrals (the atomic flux from the target increased by a factor of 6, but the atomic flux from the divertor to the upper SOL reduced by a factor of 2), increased radiation volume and increased total power loss (a factor of 2) and a reduction of target power loads through both magnetic flux expansion and larger volumetric power loss in the divertor (a factor of 5-10 in attached plasmas). The reduction of the target power load by SXD further increases with collisionality (high density or detached regimes) thanks to larger importance of volumetric power losses. It is found that a cold divertor plasma leads to stronger parallel temperature gradients in the SOL which drive more parallel heat flux, meaning that the effectiveness of perpendicular transport in spreading the power at the target can be reduced, and this needs to be taken into account in any optimisation.

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“…For example, the St. Petersburg group has improved the numerical solution of the drift terms and the electric potential equation [4,10]. These enhancements have reached a level of maturity at which it makes sense to merge them all.…”

Section: Introductionmentioning

confidence: 99%

Presentation of the New SOLPS-ITER Code Package for Tokamak Plasma Edge Modelling

Bonnin¹,

Dekeyser²,

Pitts³

et al. 2016

Plasma and Fusion Research

224

200

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We present in this paper the code package SOLPS-ITER, initially introduced by S. Wiesen et al. [J. Nucl. Mater. 463, 480 (2015)], dedicated to simulations of plasmas in the edge region of fusion devices. This package brings together previously existing SOLPS implementations and aims to become the new standard SOLPS version. We summarize the benchmarking work done to ensure backward compatibility with previous work, with a strong requirement on maintaining the viability and usability of the already extensive database of SOLPS runs used for the ITER divertor design and edge plasma physics studies worldwide over the years. The SOLPS-ITER package includes not only the plasma (B2.5) and neutral (Eirene) transport solvers, but also a large set of software tools for input file build-up, conversion of old runs, inline run analysis, and post-processing, all within a standardized portable run environment and version control system. Ongoing and planned upgrades to the code, such as extending the computational domain to the full vacuum vessel wall and a new graphical user interface, are also discussed.

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Modeling of the edge plasma of MAST Upgrade with a Super-X divertor including drifts and an edge transport barrier

Cited by 17 publications

References 7 publications

Benchmarking of a 1D scrape-off layer code SOLF1D with SOLPS and its use in modelling long-legged divertors

Benchmarking of a 1D scrape-off layer code SOLF1D with SOLPS and its use in modelling long-legged divertors

Investigation of conventional and Super-X divertor configurations of MAST Upgrade using scrape-off layer plasma simulation

Presentation of the New SOLPS-ITER Code Package for Tokamak Plasma Edge Modelling

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