Laser heated emissive probe (LHEP) for plasma potential measurement in the ADITYA-U tokamak

This article reports the first direct measurement of plasma potential, ϕ p l in the Last Closed Flux Surface (LCFS) of Ohmically heated Hydrogen plasma of ADITYA-U tokamak using Laser heated emissive probe (LHEP). Experiments have been conducted using the especially developed reciprocating diagnostic system with probe-holder assembly containing two identical planar disk-probes, one is heated with an IR laser (carbon-dioxide laser) and serves as an emissive probe, and the other is used as a cold Langmuir probe to facilitate statistical comparison of the measured parameters. The engineering design has been optimized with careful considerations of technical challenges, space constraints for the laser placement near the tokamak port and the alignment of the laser beam onto the probe-tip. The system is portable, compact, and can measure plasma potential at different radial locations in the Scrape Off-Layer (SOL)/edge region and LCFS of the Aditya-U tokamak on a shot-to-shot basis. Design, installation and evolution of the LHEP diagnostic system on the Aditya-U tokamak is presented in this paper. This work represents significant progress in plasma diagnostics by demonstrating the reliable operation of LHEP and the direct measurement of plasma potential in a tokamak environment.

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Publication Details

Journal
Fusion Engineering and Design
Published
2026-10-06
DOI
https://doi.org/10.1016/j.fusengdes.2026.116080
Primary Topic
Magnetic confinement fusion research
Type
article
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article

Laser heated emissive probe (LHEP) for plasma potential measurement in the ADITYA-U tokamak

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Fusion Engineering and Design
Magnetic confinement fusion research
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Laser heated emissive probe (LHEP) for plasma potential measurement in the ADITYA-U tokamak

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article en

Abstract

This article reports the first direct measurement of plasma potential, ϕ p l in the Last Closed Flux Surface (LCFS) of Ohmically heated Hydrogen plasma of ADITYA-U tokamak using Laser heated emissive probe (LHEP). Experiments have been conducted using the especially developed reciprocating diagnostic system with probe-holder assembly containing two identical planar disk-probes, one is heated with an IR laser (carbon-dioxide laser) and serves as an emissive probe, and the other is used as a cold Langmuir probe to facilitate statistical comparison of the measured parameters. The engineering design has been optimized with careful considerations of technical challenges, space constraints for the laser placement near the tokamak port and the alignment of the laser beam onto the probe-tip. The system is portable, compact, and can measure plasma potential at different radial locations in the Scrape Off-Layer (SOL)/edge region and LCFS of the Aditya-U tokamak on a shot-to-shot basis. Design, installation and evolution of the LHEP diagnostic system on the Aditya-U tokamak is presented in this paper. This work represents significant progress in plasma diagnostics by demonstrating the reliable operation of LHEP and the direct measurement of plasma potential in a tokamak environment.

Fusion Engineering and DesignVol. 233
Openalex Percentile: Top 15%
Magnetic confinement fusion research
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