FusionPapers
図版検索AI要約wiki日本の研究装置ジャーナルChatGPTAbout
© 2026 FUSIONPAPERS
About法務情報
トップに戻る

Progress in DIII-D towards validating divertor power exhaust predictions

A.E. Jaervinen, S.L. Allen, D. Eldon, M.E. Fenstermacher, M. Groth, D.N. Hill, C.J. Lasnier, A.W. Leonard, A.G. McLean, A.L. Moser2020年被引用 10Nuclear FusionIF 3出版社

UEDGE simulations highlight the role of cross-field drifts on the onset of detached conditions, and new calibrated divertor vacuum ultra violet (VUV) spectroscopy is used to challenge the predictions of radiative constituents in these simulations. UEDGE simulations for DIII-D H-mode plasmas with the open divertor with the ion ∇B-drift towards the X-point show a bifurcated onset of the low field side (LFS) divertor detachment, consistent with experimentally observed step-like detachment onset (Jaervinen A.E. et al 2018 Phys. Rev. Lett.121 075001). The divertor plasma in the simulations exhibits hysteresis in upstream separatrix density between attached and detached solution branches. Reducing the drift magnitude by a factor of 3 eliminates the step-like detachment onset in the simulations, confirming the strong role of drifts in the bifurcated detachment onset. When measured local plasma densities and temperatures are within proximity of predicted values in the simulations, there is no shortfall of the local emission of the dominant resonant radiating lines. However, the simulations systematically predict a factor of two lower total integrated radiated power than measured by the bolometer with the difference lost through radial heat flow out of the computational domain. Even though there is no shortfall in the emission of the dominant lines, a shortfall of total radiated power can be caused by underpredicted spatial extent of the radiation front, indicating a potential upstream or divertor transport physics origin for the radiation shortfall, or shortfall of radiated power in the spectrum between the dominant lines. In addition to the underpredicted spatial extent, in detached conditions, the simulations overpredict the peak radiation and dominant carbon lines near the X-point, which can be alleviated by manually increasing divertor diffusivity in the simulations, highlighting the ad hoc cross-field transport as one of the key limitations of the predictive capability of these divertor fluid codes.

装置

diii-d高精度(タイトル一致)

wiki

DivertorDIII-DPower exhaust
この論文にはまだAI要約がありません。

関連論文

High performance power handling in the absence of an H-mode edge in negative triangularity DIII-D plasmas

2024Nuclear Fusion

Divertor detachment in MAST-U’s Super-X Double Null plasmas: SOLPS-ITER modeling and experiment

2025Plasma Physics and Controlled Fusion

Energy and particle balance during plasma detachment in a long-leg divertor configuration

2023Nuclear Fusion

E × B flow driven electron temperature bifurcation in a closed slot divertor with ion B × ∇B away from the X-point in the DIII-D tokamak

2022Nuclear Fusion

Predictions of radiation pattern and in–out asymmetries in the DEMO scrape-off layer using fluid neutrals

2022Nuclear Fusion

Effect of cross-field drifts on flows in the main scrape-off-layer of DIII-D L-mode plasmas

2009Nuclear Fusion

Divertor detachment and asymmetry in H-mode operation with an ITER-like tungsten divertor in EAST

2019Nuclear Fusion

Influence of atomic physics on EDGE2D-EIRENE simulations of JET divertor detachment with carbon and beryllium/tungsten plasma-facing components

2014Nuclear Fusion

First experimental tests of a new small angle slot divertor on DIII-D

2019Nuclear Fusion

Understanding detachment of the W7-X island divertor

2021Nuclear Fusion