@article{9153,
  author = {A. Kappatou and M. Baruzzo and A. Hakola and E. Joffrin and D. Keeling and B. Labit and E. Tsitrone and T.O.S.J. Bosman and L. Ceelen and S. Wiesen and N. Vianello and M. Wischmeier and I. Balboa and J. Bernardo and M. Bernert and S. Brezinsek and D. Brida and I.S. Carvalho and et al. and JET Contributors and EUROfusion Tokamak Exploitation Team},
  title = {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.},
  year = {2025},
  journal = {Plasma Physics and Controlled Fusion},
  volume = {67},
  pages = {045039},
  doi = {10.1088/1361-6587/adbd75},
}