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Results from the last DD and DT JET campaigns in the framework of the EUROfusion Tokamak Exploitation Work Package activity

*Corresponding author for this work
  • University of Padua
  • National Research Council (CNR)
  • Commissariat a l'Energie Atomique et aux Energies Alternatives (CEA)
  • National Agency for New Technologies, Energy and Sustainable Economic Development (ENEA)
  • Max-Planck-Institut für Plasmaphysik (IPP)
  • United Kingdom Atomic Energy Authority (UKAEA)
  • Ecole Polytechnique Fédérale de Lausanne (EPFL)
  • Czech Academy of Sciences

Research output: Contribution to journalArticleScientificpeer-review

Abstract

JET, the only tokamak capable of operating with deuterium–tritium (D–T) fuel (since TFTR was shutdown in 1999), has provided essential experimental data to support ITER and DEMO design and operation. Within the EUROfusion Tokamak Exploitation Work Package, JET completed its final campaigns (2022–2023), culminating in the third D–T campaign (DTE3). These experiments addressed key challenges in plasma scenarios, exhaust control, and tritium management under reactor-relevant conditions. Significant progress was achieved in demonstrating ITER-like integrated scenarios with impurity seeding, achieving partial divertor detachment and high confinement ( (Formula presented) (Formula presented) (Formula presented) (Formula presented) 0.85) at 3 MA in D–T plasmas. Advanced exhaust regimes such as quasi-continuous exhaust (QCE) and X-point radiator (XPR) were successfully achieved first in D–D and then extended to D–T operation, confirming their relevance for mixed isotope operation. Operational milestones included a new world record of 69 MJ fusion energy in tritium-rich hybrid plasmas and long-pulse H-mode operation up to 60 s, contributing with unique data to the CICLOP database. Physics studies focused on peeling-limited pedestals in support of ITER and improved understanding of edge stability and impurity screening in metallic environments. Extensive usage of the shattered pellet injector (SPI) on JET provided critical information for the design of the ITER disruption mitigation system (DMS). Real-time control systems for D/T ratio control and plasma exhaust were deployed and demonstrated in D–D and D–T, while energetic particle physics investigations unfolded the role of fast ions in turbulence suppression mechanisms. Comprehensive tritium retention studies using gas balance method, post-mortem analysis, and ITER-relevant laser induced desorption spectroscopy (LIDS) diagnostics provided essential input for tritium accountancy strategies. These results are validating the ITER operational concepts, inform DEMO design, and deliver critical experience in nuclear operation and scenario integration.

Original languageEnglish
Article number116010
JournalNuclear Fusion
Volume66
Issue number11
DOIs
Publication statusPublished - 2026
MoE publication typeA1 Journal article-refereed

Funding

This work has been carried out within the framework of the EUROfusion Consortium, funded by the European Union via the Euratom Research and Training Programme (Grant Agreement No. 101052200 - EUROfusion). The Swiss contribution to this work has been funded by the Swiss State Secretariat for Education, Research and Innovation (SERI).

Keywords

  • control
  • disruptions
  • D–T
  • magnetic fusion
  • plasma scenarios
  • plasma-wall interaction
  • runaway electrons

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