Optical diagnostic design for measuring the radiation front with a mid-leg pumped divertor on DIII-D

The design of an optical diagnostic system to localize the radiation front in a mid-leg pumped divertor configuration on DIII-D is presented. Divertor detachment is a key mechanism for handling power exhaust in tokamaks, and mid-leg pumping offers a promising approach to radiatively dissipate power while maintaining acceptable core performance. To predict the location of the radiation front and design a spectroscopic diagnostic to measure its position, a database of SOLPS-ITER simulations across a range of input powers and gas puffing rates representative of DIII-D operation was employed. These simulations provide self-consistent plasma backgrounds for a Cherab-Raysect synthetic diagnostic framework, which incorporates detailed tokamak geometry and physically accurate ray-tracing. Synthetic simulations of optical sightlines and viewing cone geometry were used to calculate line-integrated emission from the plasma, particularly of the C III 465 nm line, to serve as a proxy for the Te ≈ 7-10$ eV temperature region associated with the onset and evolution of divertor detachment. Neutral deuterium emission is also evaluated for comparison. The synthetic diagnostic is used to assess the performance of existing DIII-D optical systems, including filterscopes and the Multichord Divertor Spectrometer, and to optimize line-of-sight placement within mechanical and installation constraints. The results provide quantitative guidance for diagnostic implementation on DIII-D and demonstrate the advantage of integrated synthetic diagnostics for divertor design studies and future advanced divertor concepts.

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Publication Details

Journal
Fusion Engineering and Design
Published
2026-08-14
DOI
https://doi.org/10.1016/j.fusengdes.2026.115993
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
0.00

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article

Optical diagnostic design for measuring the radiation front with a mid-leg pumped divertor on DIII-D

A. Holm, A.G. McLean, G. Ronchi, F. Scotti et al.
Fusion Engineering and Design
Magnetic confinement fusion research
article

Optical diagnostic design for measuring the radiation front with a mid-leg pumped divertor on DIII-D

A. Holm, A.G. McLean, G. Ronchi, F. Scotti, M.W. Shafer, J.H. Yu, R.S. Wilcox, Tyler Elsey, Joshua Hicok
article en

Abstract

The design of an optical diagnostic system to localize the radiation front in a mid-leg pumped divertor configuration on DIII-D is presented. Divertor detachment is a key mechanism for handling power exhaust in tokamaks, and mid-leg pumping offers a promising approach to radiatively dissipate power while maintaining acceptable core performance. To predict the location of the radiation front and design a spectroscopic diagnostic to measure its position, a database of SOLPS-ITER simulations across a range of input powers and gas puffing rates representative of DIII-D operation was employed. These simulations provide self-consistent plasma backgrounds for a Cherab-Raysect synthetic diagnostic framework, which incorporates detailed tokamak geometry and physically accurate ray-tracing. Synthetic simulations of optical sightlines and viewing cone geometry were used to calculate line-integrated emission from the plasma, particularly of the C III 465 nm line, to serve as a proxy for the Te ≈ 7-10$ eV temperature region associated with the onset and evolution of divertor detachment. Neutral deuterium emission is also evaluated for comparison. The synthetic diagnostic is used to assess the performance of existing DIII-D optical systems, including filterscopes and the Multichord Divertor Spectrometer, and to optimize line-of-sight placement within mechanical and installation constraints. The results provide quantitative guidance for diagnostic implementation on DIII-D and demonstrate the advantage of integrated synthetic diagnostics for divertor design studies and future advanced divertor concepts.

Fusion Engineering and DesignVol. 232
Lawrence Livermore National Laboratory (US), Oak Ridge National Laboratory (US), General Atomics (United States) (US)
U.S. Department of Energy, Battelle, UT-Battelle, Office of Science, Fusion Energy Sciences
Openalex Percentile: Top 39%
Magnetic confinement fusion research
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