Analysis of the thermal-hydraulic effects of a plasma disruption on the DTT TF magnets

The Divertor Tokamak Test (DTT) facility, a fully superconducting nuclear fusion reactor being built in Italy, will contribute to address the power exhaust problem in EU DEMO perspective. A lot of flexibility of operation will be demanded to the machine, which should be capable to tackle also severe transients such as plasma disruptions. In this work, the 4C thermal-hydraulic code is used to com-pute the temperature margin during a plasma disruption, using as input the heat generated into the Toroidal Field coil casing and transferred to the winding pack, and the possibility that this leads to a quench of the magnet is studied. The results of the analysis will give important feedbacks for the design of the quench protection system, e.g. suggesting the opportunity of triggering a fast current discharge right after the disruption, as well as for the machine operation, e.g. assessing the required re-cooling time of the magnets after a disruption.