Anisotropic diffusion as a proxy model for the estimation of heat-loads on plasma-facing components

Knieps, A.; Liang, Yun-Feng; Drews, P.; Endler, M.; Gao, Yu; Geiger, J.; Jakubowski, M.; König, R.; Niemann, H.; Wang, Fuqiong; Xu, Shuai; Zhou, Song

doi:10.1088/1361-6587/ac757d

Cited by 4 publications

(4 citation statements)

References 15 publications

(20 reference statements)

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“…Plasma beta effects on the divertor heat load have been predicted previously with the equilibrium code VMEC + EXTENDER [35] coupled with a simple diffusive field line tracing (DFLT) code [36], where the second strike line has been predicted to be present with ⟨β⟩ of 2% [37, figure 4.2(b) therein]. Due to the missing physics in the simple DFLT [20], an anisotropic diffusion model [38] was proposed and coupled with equilibria calculated with HINT code. This simulation shows again a clear second strike line with central beta β ax of 5% [17, figure 8 therein].…”

Section: Plasma Beta Effect On the Power Loadmentioning

confidence: 99%

Heat and particle exhaust in high-performance plasmas in Wendelstein 7-X

Gao,

Geiger,

Jakubowski

et al. 2024

Nucl. Fusion

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The paper reports for the first time the heat and particle exhaust at the plasma boundary through various edge diagnostics for the high-performance plasma obtained after pellet injection on Wendelstein 7-X. The plasma density at the edge is found to be reduced by a factor of 2 in the high-performance phase, supporting the previously reported density peaking at the plasma centre. The plasma beta effect on the magnetic topology is reflected by the appearance of the second strike line, which is well understood with simulation. However, during the rapid decay phase of the enhanced confinement, a transient localized heat flow of up to 16 MW m-2 is observed at the leading edge of a poorly cooled divertor component, which has not been understood but raises concerns about machine safety.

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Section: Plasma Beta Effect On the Power Loadmentioning

confidence: 99%

Heat and particle exhaust in high-performance plasmas in Wendelstein 7-X

Gao,

Geiger,

Jakubowski

et al. 2024

Nucl. Fusion

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“…An update of forward modelling (FM) modules in Bayesian analyses for W7-X was given [53]. Vignetting of camera views in x-ray tomography systems were needed to correct for systematic errors.…”

Section: Synthetic Diagnostics Integration Verification and Validatio...mentioning

confidence: 99%

Summary report of the 4th IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis (FDPVA)

Vicente

Mazon

et al. 2023

Nucl. Fusion

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The objective of the fourth Technical Meeting on Fusion Data Processing, Validation and Analysis was to provide a platform during which a set of topics relevant to fusion data processing, validation and analysis are discussed with the view of extrapolating needs to next step fusion devices such as ITER. The validation and analysis of experimental data obtained from diagnostics used to characterize fusion plasmas are crucial for a knowledge-based understanding of the physical processes governing the dynamics of these plasmas. This paper presents the recent progress and achievements in the domain of plasma diagnostics and synthetic diagnostics data analysis (including image processing, regression analysis, inverse problems, deep learning, machine learning, big data and physics-based models for control) reported at the meeting. The progress in these areas highlight trends observed in current major fusion confinement devices. A special focus is dedicated on data analysis requirements for ITER and DEMO with a particular attention paid to Artificial Intelligence for automatization and improving reliability of control processes.

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“…To remedy these issues, a purpose-built Monte Carlo proxy model was realized based on simple anisotropic diffusion (with parallel/perpendicular diffusion coefficient ratios of about 10 6 -10 7 ) [49]. The linearity of this model implies that all test packets could be traced independently, eliminating the need for any sort of accumulation grid.…”

Section: D Plasma and Impurity Transport Modelingmentioning

confidence: 99%

Towards advanced divertor configurations on the J-TEXT tokamak

Liang¹,

Chen²,

Cheng³

et al. 2022

Plasma Sci. Technol.

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Developing advanced magnetic divertor configurations to address the coupling of heat and particle exhaust with impurity control is one of the major challenges currently constraining the further development of fusion research, and therefore has become the focus of extensive attention in recent years. In J-TEXT, several new divertor configurations, including the high-field-side single-null poloidal divertor and the island divertor, as well as their associated fundamental edge divertor plasma physics have recently been investigated. The purpose of this paper is to briefly summarize the latest progress and achievements in this relevant research field on J-TEXT in the past few years.

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Anisotropic diffusion as a proxy model for the estimation of heat-loads on plasma-facing components

Cited by 4 publications

References 15 publications

Heat and particle exhaust in high-performance plasmas in Wendelstein 7-X

Heat and particle exhaust in high-performance plasmas in Wendelstein 7-X

Summary report of the 4th IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis (FDPVA)

Towards advanced divertor configurations on the J-TEXT tokamak

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