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Plasma Physics (Physics/ECE/NE 922) Seminar
Science Basis and Present Status of the new Divertor Tokamak Test facility
Date: Monday, November 23rd
Time: 12:00 pm
Place: Zoom Meeting
Speaker: Piero Martin, University of Padova and Consorzio RFX, Padova, Italy; DTT Consortium, Frascati, Italy
Abstract: One of the high priority challenges for the exploitation of fusion as an energy source is the disposal of the non-neutronic energy and particle exhaust in a reactor. The new Divertor Tokamak Test (DTT) facility (its construction is starting in Italy) [1], is an experiment to address that challenge in high-field, high performance tokamak with full integration between core and edge plasma scenarios.

DTT is superconducting tokamak with 6 T on-axis maximum toroidal magnetic field carrying plasma current up to 5.5 MA in pulses with length up to 100s. The D-shaped device is up-down symmetric, with major radius R=2.19 m and minor radius a=0.70 m. The auxiliary heating power coupled to the plasma at maximum performance is 45 MW, shared between 170 GHz ECRH, 60-90 MHz ICRH and 500 kV negative ion beam injectors. This allows matching the PSEP/R values, where Psep is the power flowing through the last closed magnetic surface, with those of ITER and DEMO. DTT is in fact designed to reach PSEP/R =15 MW/m.

This talk will discuss the science basis for the experiment and the state of the art of the project. The presentation will start from the scientific background of the experiment, then will move to its main physics driver and finally will discuss the expected plasma scenarios - in particular as far as plasma exhaust is concerned. Emphasis will be given to highlight the effort of designing an experimental tool, which will be a device not only for plasma exhaust studies, but also for the advancement of fusion science in the grand sense.

[1] “DTT-Divertor Tokamak Test facility. Interim Design Report”, R. Martone, R. Albanese, F. Crisanti, P. Martin, A Pizzuto Eds. April 2019,

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Host: Paul Terry
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