ITER demonstrates fast data transfer to Japan and the US

One of the challenges facing fusion is to identify the right materials for the next-generation fusion reactors like DEMO. A major initiative to find these solutions, the IFMIF-DONES project, achieved a major benchmark with the signing on 21 November of an international agreement to strengthen collaboration on testing to identify materials that best resist neutron irradiation.

The International Fusion Materials Irradiation Facility-Demo Oriented NEutron Source (IFMIF-DONES) is based in Granada, Spain. The agreement was signed between the IFMIF-DONES España Consortium, Fusion for Energy (F4E) representing the European Commission and Member States, and R&D centres in Croatia (RBI), Japan (QST) and Italy (INFN). The multinational agreement provides a framework for the financing and operation of the test facility.

Learn more at F4E or the IFMIF-DONES site.

The ITER Organization has begun recruitment for its 2026 internship program.

We invite students from across the ITER Members (the People's Republic of China, the European Union, India, Japan, the Republic of Korea, the Russian Federation, the United States) to apply for one of our exciting internship opportunities. All Bachelor’s, Master’s, or PhD students enrolled in a fully accredited degree program are eligible to apply. Internships are offered for up to six months and are extendable to up to one year under certain circumstances. 

The first wave of the campaign runs from 15 November 2025 through 6 January 2026, with the publication of 28 offers on the ITER website. A second-wave campaign will be advertised from 17 January 2026 through 28 February 2026.

See this page to apply. The deadline for first-wave opportunities is 6 January 2026.

The WEST tokamak in France, with its tungsten divertor, is exploring the plasma physics of operation in a tungsten environment.

Research on WEST is directly relevant to ITER, helping to answer questions such as "How will the actively cooled tungsten components of the ITER divertor behave after hours of plasma discharge?" or "Can performant plasmas be produced if plasma-facing components are damaged?" or "How can the monitoring system be optimized for these components?" 

In a six-week campaign that started on 7 November, the team is testing the performance of a tungsten coating on tiles in collaboration with ITER, running experiments to test the "I-mode" regime (an ELM-free improved confinement regime with low impurity content) in collaboration with American and Chinese collaborators, and studying the growth of deposits on the divertor under high particle fluence.

The WEST tokamak (for W Environment in Steady-state Tokamak) is located at the Institute for Magnetic Fusion Research (IRFM) near ITER, part of the French Alternative Energies and Atomic Energy Commission's (CEA's) Cadarache Centre.

See the article published on the CEA IRFM website.

At the ITER Neutral Beam Test Facility in Italy, progress was made in October on the MITICA testbed, where a full-size prototype of the ITER heating neutral beam injector will be tested before ITER operation.

During tests of MITICA's cryogenic infrastructure, the cryopump system successfully reached its nominal operating temperatures: 4.6 K for the cryopumps and 80 K for the thermal radiation shields. Controlled gas injection inside MITICA’s vacuum vessel came next, providing essential data on the cryopumps' behaviour and their capability to capture and retain gas under realistic operating conditions. The charcoal layer within the cryopump reached full saturation, allowing researchers to study gas release dynamics and system limitations. The campaign concluded with the successful warm-up of the MITICA cryogenic system back to room temperature.

Read a full report on the Consorzio RFX website in English or Italian.