This paper firstly illustrates the objectives, the figure of merits and the specifications considered in the design of the equilibrium configurations in the Divertor Tokamak Test (DTT) facility. The reference single null scenario is detailed. The range of alternative plasma shapes and current capabilities are then discussed. A number of in-vessel coils can be used to locally modify the magnetic configuration in the divertor region. Finally, a comparison of costs and benefits of the various configurations is given, with particular reference to the power exhaust issues.

The DTT device: Poloidal Field Coil Assessment for Alternative Plasma Configurations

Albanese, Raffaele;CASTALDO, ANTONIO;
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Abstract

This paper firstly illustrates the objectives, the figure of merits and the specifications considered in the design of the equilibrium configurations in the Divertor Tokamak Test (DTT) facility. The reference single null scenario is detailed. The range of alternative plasma shapes and current capabilities are then discussed. A number of in-vessel coils can be used to locally modify the magnetic configuration in the divertor region. Finally, a comparison of costs and benefits of the various configurations is given, with particular reference to the power exhaust issues.
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/11577/3220328
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