The new super-conducting Divertor Tokamak Test facility (“DTT”, R = 2.19 m, a = 0.7 m, BT <= 6 T, Ip <= 5.5 MA) [1], [2] is currently under construction in Frascati (Italy). DTT is designed to investigate innovative solutions to the power exhaust problem in support of ITER operations and DEMO design. This goal will be achieved through the flexibility of DTT in terms of divertor configurations.
Exploring Divertor Tokamak Test (DTT) operation space and plasma scenarios through time-dependent 0.5D integrated modelling
Vincenzi P.; Bolzonella T.; Ambrosino R.; Castaldo A.; Casiraghi I.; Mantica P.
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