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DTT (Divertor Tokamak Test)

Italy’s purpose-built superconducting tokamak for testing the advanced divertor solutions that DEMO will need to handle reactor-level exhaust power—the single hardest unsolved engineering problem in magnetic fusion.

Reviewed Last reviewed: 9 Aug 2026 · Category: Machines & Facilities

The Exhaust Problem

In a fusion power plant, roughly 20 percent of the total thermal power must be channelled through the divertor—the narrow exhaust region where the magnetic field lines intersect material surfaces. In DEMO-class devices, this translates to heat fluxes that can exceed 20 MW/m², beyond the steady-state tolerance of any known material. The Divertor Tokamak Test facility, under construction at the ENEA Frascati Research Centre near Rome, is designed specifically to develop and validate the plasma-exhaust solutions that will make power-plant divertors survivable.1

Machine Parameters

DTT is a superconducting tokamak with a major radius of 2.19 m, a toroidal field of 6 T, and a plasma current of up to 5.5 MA. Auxiliary heating of 45 MW—provided by ion-cyclotron, electron-cyclotron, and neutral-beam systems—will drive power across the separatrix at levels sufficient to reproduce the scrape-off-layer conditions expected in DEMO.2 The device is designed for high flexibility: its poloidal-field coil set can produce conventional single-null, double-null, snowflake, Super-X, and X-point-target divertor configurations, allowing head-to-head comparison of competing exhaust geometries on a single machine.

DTT will be the world’s first superconducting tokamak built from the ground up to solve the divertor problem—capable of testing every leading exhaust concept under reactor-relevant power loads in a single device.

Plasma-Facing Components

The initial divertor will use ITER-grade tungsten monoblock targets on copper-chromium-zirconium cooling tubes, but the facility is designed for rapid divertor cassette exchange so that alternative concepts—including liquid-tin and liquid-lithium divertors—can be tested in later campaigns.3 This modularity is central to DTT’s mission: no single divertor solution has yet proven adequate for a power plant, and the field needs a dedicated testbed that can cycle through candidates at a pace faster than ITER’s operational schedule allows.

Programme Status and Significance

DTT received Italian government funding of approximately 500 million euros, supplemented by EUROfusion in-kind contributions. Civil construction at the Frascati site advanced through the mid-2020s, with magnet fabrication and vacuum-vessel assembly proceeding in parallel. First plasma is targeted for the late 2020s, with full-power divertor experiments to follow in the early 2030s.4

Together with COMPASS-U, WEST, and the upgraded ASDEX-Upgrade programme, DTT forms the European exhaust-solution network. Its unique combination of reactor-relevant power density, divertor flexibility, and superconducting steady-state capability makes it the closest analogue to DEMO exhaust conditions that will exist before DEMO itself is built.5

Sources

  1. R. Ambrosino et al., 'DTT – Divertor Tokamak Test facility: a testbed for DEMO exhaust solutions,' Fusion Engineering and Design, vol. 167, 112330, 2021.
  2. P. Martin et al., 'The DTT device: design overview and physics basis,' Nuclear Fusion, vol. 60, 095003, 2020.
  3. G. Mazzitelli et al., 'Liquid metal divertor concepts for DTT,' Nuclear Materials and Energy, vol. 29, 101072, 2021.
  4. ENEA, 'Divertor Tokamak Test facility: project status,' enea.it technical documentation, 2024.
  5. EUROfusion, 'European roadmap to fusion energy: the role of DTT,' EUROfusion programme documentation, 2023.

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