Archivio Istituzionale della RicercaOne of the most critical challenges in magnetic confinement fusion is the management of large heat and particle fluxes. To address this issue, the Divertor Tokamak Test (DTT) facility is currently under construction at ENEA Frascati premises. It will test different power exhaust solutions for the EU DEMO reactor. Different plasma configurations will be required, asking for a significant flexibility and reliability of the different subsystems.
Engineering design of the thermal shield for the Divertor Tokamak Test (DTT) facility / Bonifetto, R; Barone, G; Belardi, V; Bonomi, D; Dallapalma, M; Del Nero, S; Fanelli, P; Fulici, M; Micheletti, M; Ventura, G; Zavarise, G.. - ELETTRONICO. - (2025). (Intervento presentato al convegno Symposium on Fusion Energy 2025 tenutosi a Cambridge, MA (USA) nel 23 - 26 giugno 2025).
Engineering design of the thermal shield for the Divertor Tokamak Test (DTT) facility
Bonifetto R;Barone G;Ventura G;Zavarise G.
2025
Abstract
One of the most critical challenges in magnetic confinement fusion is the management of large heat and particle fluxes. To address this issue, the Divertor Tokamak Test (DTT) facility is currently under construction at ENEA Frascati premises. It will test different power exhaust solutions for the EU DEMO reactor. Different plasma configurations will be required, asking for a significant flexibility and reliability of the different subsystems.
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https://hdl.handle.net/11583/2999479