TJ-II, (CIEMAT), Madrid, Spain

Located in Spain, this stellarator offers unique data on magnetic confinement and plasma stability. Since is a local Spanish ICTS (Unique Scientific and Technical Infrastructure) operated by the LNF, experiments derived to the STRANAI network activities can be proposed for the inclusion in its operational campaign.
Thanks to its flexible magnetic configuration and advanced diagnostics, the device enables studies of plasma behavior under different confinement regimes, supporting both theoretical developments and validation of numerical models.
Experiments aligned with the objectives of the STRANAI network can be proposed for inclusion in its operational campaign, offering participating institutions the opportunity to conduct targeted investigations that contribute to the development of artificial intelligence tools and advanced data analysis methods applied to fusion research.

The world’s largest stellarator, providing extensive data on steady-state plasma confinement and stability. Wendelstein 7-X is a key facility for validating advanced magnetic confinement concepts and testing innovative plasma control strategies essential for the development of future fusion reactors. Its unique modular coil system allows unprecedented flexibility in shaping the magnetic fields, enabling researchers to explore optimized configurations that minimize turbulence and energy losses.

Next experimental campaigns will offer research opportunities focused on high-performance plasma scenarios, impurity transport studies, and long-pulse operation under reactor-relevant conditions.

Wendelstein 7-X, (IPP), Greifswald, Germany

Large Helical Device, (NIFS), Toki, Japan

Located in Toki, Japan, this device employs a heliotron magnetic field configuration and is the world’s second-largest superconducting stellarator. The Large Helical Device (LHD) has significantly advanced the understanding of long-pulse plasma discharges, impurity transport, and magnetic field optimization. Its experimental campaigns have provided valuable insights into plasma confinement, advanced divertor concepts, and energetic particle behavior.

LHD will complete its final operational campaign in 2025, closing a key chapter in stellarator research. Its extensive data repository remains a crucial resource for exploring scaling laws among stellarators and supporting the development of predictive models for future fusion devices.