The Divertor Tokamak Test facility (DTT) is a new fusion device under construction in Frascati, Italy. It is a compact, superconducting tokamak (R=2.19 m, a=0.70 m, average triangularity 0.3) with 6 T on-axis maximum toroidal magnetic field and plasma current up to 5.5 MA. Its main goals are to support the science and technology of plasma exhaust in view of ITER and DEMO and to provide a facility for high performance tokamak physics and to address core confinement and stability issues also in negative triangularity configurations, and the management of transient events like disruptions and ELMs.

Divertor Tokamak Test Facility: Science Basis and Status of the Project

Granucci G;Innocente P;Mantica P;Valisa M;
2021

Abstract

The Divertor Tokamak Test facility (DTT) is a new fusion device under construction in Frascati, Italy. It is a compact, superconducting tokamak (R=2.19 m, a=0.70 m, average triangularity 0.3) with 6 T on-axis maximum toroidal magnetic field and plasma current up to 5.5 MA. Its main goals are to support the science and technology of plasma exhaust in view of ITER and DEMO and to provide a facility for high performance tokamak physics and to address core confinement and stability issues also in negative triangularity configurations, and the management of transient events like disruptions and ELMs.
2021
Istituto per la Scienza e Tecnologia dei Plasmi - ISTP
DTT
Divertor Tokamak Test Facility
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Descrizione: Poster Divertor Tokamak Test Facility Science Basis and Status of the Project
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/395560
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