Neutral beam operations for JET TT and DT campaigns

Abstract Neutral beam injection (NBI) is a flexible auxiliary heating method for tokamak plasmas, capable of being efficiently coupled to the various plasma configurations required in the Tritium and mixed Deuterium–Tritium Experimental campaign 2 on the Joint European Torus (JET) device. High NBI power was required for high fusion yield and alpha particle studies and to provide mixed Deuterium–Tritium (D–T) fuelling in the plasma core, it was necessary to operate the JET NBI systems in both deuterium and tritium. Further, the pure tritium experiments performed required T NBI for high isotopic purity and reduced 14 MeV neutron yield. The use of NBI in tritium presents further challenges compared to standard NBI operation. The experience of preparing, commissioning and operating NBI across the 2021 and 2023 JET D–T experiments are explored in detail in this paper.

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Publication Details

Journal
Plasma Physics and Controlled Fusion
Published
2025-08-29
DOI
https://doi.org/10.1088/1361-6587/ae00f1
Citations
1
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
1.87

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article

Neutral beam operations for JET TT and DT campaigns

J. Fan, M. Walsh, D. King, C. Balshaw et al.
1 citations
Plasma Physics and Controlled Fusion
Magnetic confinement fusion research
1.87
article

Neutral beam operations for JET TT and DT campaigns

J. Fan, M. Walsh, D. King, C. Balshaw, A. Shepherd, R. Sharma, S. P. Marsden, Anurag Saigiridhari, R. McAdams, S. Merriman, D. Ćirić, Tim Robinson, Alan Barth, K. Flinders, A. Ash, Keith Sabin, I. Turner, T. Wilson, Maria Nicassio, T. Jones, gavin withenshaw, B. Woods
article en
1 citations

Abstract

Abstract Neutral beam injection (NBI) is a flexible auxiliary heating method for tokamak plasmas, capable of being efficiently coupled to the various plasma configurations required in the Tritium and mixed Deuterium–Tritium Experimental campaign 2 on the Joint European Torus (JET) device. High NBI power was required for high fusion yield and alpha particle studies and to provide mixed Deuterium–Tritium (D–T) fuelling in the plasma core, it was necessary to operate the JET NBI systems in both deuterium and tritium. Further, the pure tritium experiments performed required T NBI for high isotopic purity and reduced 14 MeV neutron yield. The use of NBI in tritium presents further challenges compared to standard NBI operation. The experience of preparing, commissioning and operating NBI across the 2021 and 2023 JET D–T experiments are explored in detail in this paper.

Plasma Physics and Controlled FusionVol. 67(9)
Oak Ridge National Laboratory (US), Culham Centre for Fusion Energy (GB), Culham Science Centre (GB), United Kingdom Atomic Energy Authority (GB)
EUROfusion, European Commission, Euratom Research and Training Programme
Openalex Percentile: Top 12%
Magnetic confinement fusion research
1.87
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