• An Italian 6 T, 5.5 MA superconducting tokamak
• Final design almost completed
• More than 100 ML contracts assigned and additional 100 ML contracts awarded
• Construction starting at ENEA Frascati Research Centre
• Within the European roadmap to the realization of fusion energy
• Designed to study the power exhaust problem in:
  • An integrated environment within a hi performance tokamak
  • DEMO (DEMOnstration Power Plant) relevant conditions

• Explore and qualify alternative power exhaust solutions for DEMO.
• Test the physics and technology of various alternative divertor concepts under plasma conditions that can be extrapolated to DEMO.
• Ultimately show whether alternative configuration or liquid metal plasma facing components are technologically viable, technically maintainable and economically attractive.
• Train new generations of engineers and scientists for science and technological transfer.

The main DTT features are advanced system design, new technological and engineering solutions in a variety of fields including superconductivity, huge heat flux, real time control, power electronics, innovative materials, remote handling.

ITER is under construction at Cadarache (France). Its mission is to improve Q to about 10, by increasing magnetic field, plasma current and machine dimensions (P_fus=500 MW from P_in=50 MW).

The DEMOnstration power plant, DEMOThe DEMOnstration power plant, DEMO, is the will be ITER's successor, presently under prelimary design by EUROfusion Consortium. It is planned to be operative  around 2050.

The power exhaust problem could be solved by improving a number of present-day limitations:

• Plasma facing components technology -> max heat flux presently limited to 10-20 MW/m²
• Geometry + Plasma shape
• Impurity seeding to increase radiation
• Liquid metals

DTT aims at providing a key integrated environment, relevant to DEMO, where all the previous approaches can be tested.

DTT will offer sufficient flexibility to incorporate the best candidate divertor concept even at a later stage of its realization, on the basis of the EUROfusion studies carried out in present tokamaks involved in the PEX (Plasma Exhaust Assessment Panel) activities (around 2022-2023).