The Divertor Tokamak Test (DTT) facility has been launched to investigate alternative power exhaust solutions for DEMO. DTT should offer sufficient flexibility to be able to incorporate the best candidate divertor concept (e.g. conventional, Snowflake, Super-X, Double Null, liquid metals). In this paper, the revised up-down symmetric DTT device is presented. The up-down symmetrisation of the device makes it possible to have the reference values of the plasma current up to 5.5 MA and, at the same time, it has an impact on the costs, for which a slight revision of the main parameters has been considered. The DTT alternative magnetic configurations, such as Double Null, SnowFlake, Super-X, Double Super-X and Single Null with reverse triangularity, guarantee suitable constraints on the plasma-wall distance and the plasma elongation. The feasibility of the configurations is evaluated in terms of maximum vertical forces and currents on the PF coils along the scenarios.

Magnetic configurations and electromagnetic analysis of the Italian DTT device

Ramogida G.;Crisanti F.;Pizzuto A.
2019-01-01

Abstract

The Divertor Tokamak Test (DTT) facility has been launched to investigate alternative power exhaust solutions for DEMO. DTT should offer sufficient flexibility to be able to incorporate the best candidate divertor concept (e.g. conventional, Snowflake, Super-X, Double Null, liquid metals). In this paper, the revised up-down symmetric DTT device is presented. The up-down symmetrisation of the device makes it possible to have the reference values of the plasma current up to 5.5 MA and, at the same time, it has an impact on the costs, for which a slight revision of the main parameters has been considered. The DTT alternative magnetic configurations, such as Double Null, SnowFlake, Super-X, Double Super-X and Single Null with reverse triangularity, guarantee suitable constraints on the plasma-wall distance and the plasma elongation. The feasibility of the configurations is evaluated in terms of maximum vertical forces and currents on the PF coils along the scenarios.
2019
Alternative divertor concepts; Plasma magnetic scenarios; Tokamak
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.12079/53767
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