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Improved Conceptual Design of the Beamline for the DTT Neutral Beam Injector

Agostinetti P.; Benedetti E.; Bonifetto R.; Bonesso M.; Cavenago M.; Bello S.D.; Dalla Palma M.; D’Ambrosio D.; Dima R.; Favero G.; Ferro A.; Fincato M.; Giorgetti F.; Granucci G.; Lombroni R.; Marconato N.; Marsilio R.; Murari A.; Patton T.; Pavei M.; Pepato A.; Pilan N.; Raffaelli F.; Rebesan P.; Recchia M.; Ripani M.; Romano A.; Sartori E.; Tinti P.; Valente M.; Variale V.; Ventura G.; Veronese F.; Zanino R.; Zavarise G.

The Divertor Tokamak Test facility (DTT) will be a new experimental facility located at Frascati, Rome, Italy, whose main goal will be to have a better understanding on hot plasma interactions with plasma-facing components (PFCs) and aid in the development of ITER and successively DEMO. The improved conceptual design of the beamline for the DTT neutral beam heating (NBH) system is here overviewed, with a particular focus on the technical solutions adopted to fulfill the requirements and maximize beamline performances. The proposed system features a beamline providing deuterium neutrals (D⁰) with an energy of 510 keV and an injected power of 10 MW. Various design options have been considered, and a comprehensive set of simulations has been carried out using several physics and engineering codes to drive the choice of the most suitable design options and optimize them, aiming at finding a good compromise among different design requirements.

ID 466560
DOI 10.1109/TPS.2022.3162902
PRODUCT TYPE Journal Article
LAST UPDATE 2022-12-09T14:47:29Z