The Divertor Tokamak Test (DTT) facility is currently under construction at ENEA Frascati. DTT is a compact, superconducting tokamak that will study different solutions to address the issue of power exhaust in EU DEMO perspective. A significant amount of auxiliary heating power will be needed, to reach relevant values of the heat flux on the divertor target: Electron Cyclotron Resonant Heating (ECRH), Ion Cyclotron Resonant Heating (ICRH) and a Neutral Beam Injector (NBI) are foreseen for this purpose.

Thermal-hydraulic and mechanical analysis of the Beam Line Components for the DTT Neutral Beam Injector / 67) Bonifetto, R; Agostinetti, P; D’Ambrosio, D; Marsilio, R; Murari, A; Ventura, G; Veronese, F; Zanino, R; Zappatore, A; Zavarise, G.. - ELETTRONICO. - (2023). (Intervento presentato al convegno International symposium on fusion nuclear technology tenutosi a Las Palmas (Spain) nel 10 - 15 Settembre 2023).

Thermal-hydraulic and mechanical analysis of the Beam Line Components for the DTT Neutral Beam Injector.

D’Ambrosio D;Marsilio R;Ventura G;Veronese F;Zanino R;Zavarise G.
2023

Abstract

The Divertor Tokamak Test (DTT) facility is currently under construction at ENEA Frascati. DTT is a compact, superconducting tokamak that will study different solutions to address the issue of power exhaust in EU DEMO perspective. A significant amount of auxiliary heating power will be needed, to reach relevant values of the heat flux on the divertor target: Electron Cyclotron Resonant Heating (ECRH), Ion Cyclotron Resonant Heating (ICRH) and a Neutral Beam Injector (NBI) are foreseen for this purpose.
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11583/2999474