Overview of the third JET deuterium-tritium campaign

Abstract JET returned to deuterium-tritium operations in 2023 (DTE3 campaign), approximately two years after DTE2. DTE3 was designed as an extension of JET’s 2022-2023 deuterium campaigns, which focused on developing scenarios for ITER and DEMO, integrating in-depth physics understanding and control schemes. These scenarios were evaluated with mixed D-T fuel, using the only remaining tritium-capable tokamak until its closure in 2023. A core-edge-SOL integrated H-mode scenario was developed and tested in D-T, showing good confinement and partial divertor detachment with Ne-seeding. Stationary pulses with good performance, no tungsten accumulation, and even without ELMs were achieved in D-T. Plasmas with pedestals limited by peeling modes were studied with D, T-rich, and D-T fuel, revealing a positive correlation between pedestal electron pressure and pedestal electron density. The Quasi-Continuous Exhaust regime was successfully achieved with D-T fuel, with access criteria similar to those in D plasmas. A scenario with full detachment, the X-point radiator regime, was established in D-T, aided by the real-time control of the radiator’s position. The crucial characterisation of tritium retention continued in DTE3, using gas balance measurements and the new LID-QMS diagnostic. Nuclear technology studies were advanced during the DTE3 campaign, addressing issues such as the activation of water in cooling loops and single event effects on electronics. Building on the previous D, T and DTE2 campaigns and the lessons learned from them, DTE3 extended our understanding of D-T plasmas, particularly in scenarios relevant to next-generation devices such as ITER and DEMO.

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Publication Details

Journal
Plasma Physics and Controlled Fusion
Published
2025-03-06
DOI
https://doi.org/10.1088/1361-6587/adbd75
Citations
18
Primary Topic
Fusion materials and technologies
Type
article
Field-Weighted Citation Impact
9.32

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article

Overview of the third JET deuterium-tritium campaign

T. Dittmar, D. Brida, A. Widdowson, M. Zlobinski et al.
18 citations
Plasma Physics and Controlled Fusion
Fusion materials and technologies
9.32
article

Overview of the third JET deuterium-tritium campaign

T. Dittmar, D. Brida, A. Widdowson, M. Zlobinski, S. Henderson, Philippe Jacquet, M. Dunne, E. Litherland-Smith, Y. Kazakov, B. Sieglin, P. A. Schneider, A. Kappatou, Peter Lomas, A. Meigs, I.S. Carvalho, Lennard Ceelen, S. Silburn, G. Pucella, D. King, L. Frassinetti, X. Litaudon, D. Matveev, E.R. Solano, N. Vianello, T.O.S.J. Bosman, E. Tsitrone, M. Maslov, D. Valcárcel, M. Lennholm, M. Faitsch, D. Van Eester, J. Hobirk, D. Keeling, R. Henriques, O. Sauter, B. Labit, Z. Ghani, C. Lowry, I. Balboa, J. Mailloux, H. Reimerdes, I. Coffey, H.J. Sun, E. Lerche, P. Carvalho, M. Mantsinen, M. Bernert, A. R. Field, S. Brezinsek, L. Garzotti, I. Jepu, C. Challis, D. Kos, F. Rimini, R. Villari, V.K. Zotta, M. Wischmeier, J. Bernardo, K. Krieger, L. Piron, A. Hakola, M. Baruzzo, S. Wiesen, C. Pérez von Thun, C. Olde, E. Joffrin, Carine Giroud, S. Menmuir, Кирил Киров
article en
18 citations

Abstract

Abstract JET returned to deuterium-tritium operations in 2023 (DTE3 campaign), approximately two years after DTE2. DTE3 was designed as an extension of JET’s 2022-2023 deuterium campaigns, which focused on developing scenarios for ITER and DEMO, integrating in-depth physics understanding and control schemes. These scenarios were evaluated with mixed D-T fuel, using the only remaining tritium-capable tokamak until its closure in 2023. A core-edge-SOL integrated H-mode scenario was developed and tested in D-T, showing good confinement and partial divertor detachment with Ne-seeding. Stationary pulses with good performance, no tungsten accumulation, and even without ELMs were achieved in D-T. Plasmas with pedestals limited by peeling modes were studied with D, T-rich, and D-T fuel, revealing a positive correlation between pedestal electron pressure and pedestal electron density. The Quasi-Continuous Exhaust regime was successfully achieved with D-T fuel, with access criteria similar to those in D plasmas. A scenario with full detachment, the X-point radiator regime, was established in D-T, aided by the real-time control of the radiator’s position. The crucial characterisation of tritium retention continued in DTE3, using gas balance measurements and the new LID-QMS diagnostic. Nuclear technology studies were advanced during the DTE3 campaign, addressing issues such as the activation of water in cooling loops and single event effects on electronics. Building on the previous D, T and DTE2 campaigns and the lessons learned from them, DTE3 extended our understanding of D-T plasmas, particularly in scenarios relevant to next-generation devices such as ITER and DEMO.

Plasma Physics and Controlled FusionVol. 67(4)
ITER (FR), National Agency for New Technologies, Energy and Sustainable Economic Development (IT), Institució Catalana de Recerca i Estudis Avançats (ES), Forschungszentrum Jülich (DE), Commissariat à l'Énergie Atomique et aux Énergies Alternatives (FR), Barcelona Supercomputing Center (ES), Consorzio Venezia Ricerche (IT), CEA Cadarache (FR), Max Planck Institute for Plasma Physics (DE), Institute of Plasma Physics and Laser Microfusion (PL), Dutch Institute for Fundamental Energy Research (NL), Laboratoire de Physique des Plasmas (FR), Consorzio CREO (Italy) (IT), United Kingdom Atomic Energy Authority (GB), École Polytechnique Fédérale de Lausanne (CH), Eindhoven University of Technology (NL), Sapienza University of Rome (IT), KTH Royal Institute of Technology (SE), VTT Technical Research Centre of Finland (FI), Universitat Politècnica de Catalunya (ES)
Ministerio de Ciencia, Innovación y Universidades, EUROfusion, European Commission, Euratom Research and Training Programme, Staatssekretariat für Bildung, Forschung und Innovation, European Regional Development Fund, Agencia Estatal de Investigación
Openalex Percentile: Top 1%
Fusion materials and technologies
9.32
DOIOpen Access PDFOpenAlex
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