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The Divertor Tokamak Test facility (DTT) [1, 2] is a new D-shaped superconducting tokamak under construction in Italy, with the first plasma planned for 2026. It will be equipped with 3 auxiliary heating systems: a 170 GHz ECRH system, a 60-90 MHz ICRH system, and a negative ion NBI system. The primary task of DTT (R0 = 2.19m, a =0.70m, pulse length <= 100s, BT <= 6T, Ipl <= 5.5MA, Psep/R '15) is to study the controlled power and particle exhaust from a fusion reactor, which is a main research topic in the European Fusion Roadmap [3], and test alternative exhaust strategies. An intensive integrated modelling work of DTT operational scenarios with the Single Null (SN) divertor configuration (Fig.1) is underway, in order to support the machine design, and particularly the definition of the heating mix, the design of the neutron shields, the assessment of fast particle losses and the design of diagnostic systems, as well as to help the elaboration of a DTT scientific work-programme.
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