Engineering considerations for optical diagnostics of European DEMO

Optical diagnostics measurements were identified as necessary for plasma control in the initial concept for the plasma diagnostic and control (D&C) system of European DEMO. The protection of the first mirror is identified as a critical subject for future large sized fusion devices. Radio Frequency Plasma Discharge mirror cleaning solutions proposed for ITER have been discarded for fusion power plant environment. Erosion and deposition processes can be mitigated by neutral gas between the aperture and the front mirror. Currently 3 optical diagnostics are being developed for EU-DEMO. The Divertor Monitoring Diagnostic had the highest priority thus that was selected for conceptual development. Three optomechanical layout configurations were analyzed, with the optimal candidate further refined for improved integration and performance. The design emphasized the optical duct geometry, revealing that a shorter duct simplifies mechanical integration. Preliminary Monte Carlo N-Particle (MCNP) neutronics simulations estimated the diagnostic module's nuclear load, providing key insights for further refinement. This iterative workflow enables systematic optimization of the optical and mechanical structure to meet stakeholder requirements, yielding a robust, integrated diagnostic module design. The methodology offers a transferable framework for other optical diagnostics under development for EU-DEMO and future fusion power plants.

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Publication Details

Journal
Fusion Engineering and Design
Published
2025-07-01
DOI
https://doi.org/10.1016/j.fusengdes.2025.115292
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
0.00

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article

Engineering considerations for optical diagnostics of European DEMO

Imre Katona, D. Dunai
Fusion Engineering and Design
Magnetic confinement fusion research
article

Engineering considerations for optical diagnostics of European DEMO

Imre Katona, D. Dunai
article en

Abstract

Optical diagnostics measurements were identified as necessary for plasma control in the initial concept for the plasma diagnostic and control (D&C) system of European DEMO. The protection of the first mirror is identified as a critical subject for future large sized fusion devices. Radio Frequency Plasma Discharge mirror cleaning solutions proposed for ITER have been discarded for fusion power plant environment. Erosion and deposition processes can be mitigated by neutral gas between the aperture and the front mirror. Currently 3 optical diagnostics are being developed for EU-DEMO. The Divertor Monitoring Diagnostic had the highest priority thus that was selected for conceptual development. Three optomechanical layout configurations were analyzed, with the optimal candidate further refined for improved integration and performance. The design emphasized the optical duct geometry, revealing that a shorter duct simplifies mechanical integration. Preliminary Monte Carlo N-Particle (MCNP) neutronics simulations estimated the diagnostic module's nuclear load, providing key insights for further refinement. This iterative workflow enables systematic optimization of the optical and mechanical structure to meet stakeholder requirements, yielding a robust, integrated diagnostic module design. The methodology offers a transferable framework for other optical diagnostics under development for EU-DEMO and future fusion power plants.

Fusion Engineering and DesignVol. 219
Budapest University of Technology and Economics (HU), HUN-REN Centre for Energy Research (HU)
EUROfusion, European Commission
Openalex Percentile: Top 93%
Magnetic confinement fusion research
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