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.

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.; Palma, M. D.; 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.. - In: IEEE TRANSACTIONS ON PLASMA SCIENCE. - ISSN 0093-3813. - (2022), pp. 1-6. [10.1109/TPS.2022.3162902]

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

Bonifetto R.;Bonesso M.;D'Ambrosio D.;Marsilio R.;Recchia M.;Ventura G.;Veronese F.;Zanino R.;Zavarise G.
2022

Abstract

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.
File in questo prodotto:
File Dimensione Formato  
Paper_DTT_NBI_Agostinetti_submitted_Jan27.docx.pdf

accesso aperto

Tipologia: 2. Post-print / Author's Accepted Manuscript
Licenza: PUBBLICO - Tutti i diritti riservati
Dimensione 1.08 MB
Formato Adobe PDF
1.08 MB Adobe PDF Visualizza/Apri
Improved_Conceptual_Design_of_the_Beamline_for_the_DTT_Neutral_Beam_Injector.pdf

non disponibili

Tipologia: 2a Post-print versione editoriale / Version of Record
Licenza: Non Pubblico - Accesso privato/ristretto
Dimensione 7.45 MB
Formato Adobe PDF
7.45 MB Adobe PDF   Visualizza/Apri   Richiedi una copia
Pubblicazioni consigliate

I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.

Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11583/2970405