29th Symposium on Fusion Technology (SOFT 2016)

P2.006 DTT Device: Conceptual design of the superconducting magnet system

6 Sep 2016, 14:20

1h 40m

Foyer 2A (2nd floor), 3A (3rd floor) (Prague Congress Centre)

Board: 6

Poster A. Experimental Fusion Devices and Supporting Facilities P2 Poster session

Speaker

Alessandro Anemona (ICAS)

Description

In the European Fusion Roadmap, one of the main challenges to be faced is the mitigation of the risk due to the impossibility of directly extrapolate to DEMO the divertor solution adopted in ITER, due to the expected very large loads. Thus a satellite experimental facility oriented toward the exploration of robust divertor solutions for power and particles exhaust and to the study of plasma-material interaction scaled to long pulse operation, is currently being designed. Clearly, this kind of experiment presents challenging design requirements, due to the extreme operation conditions which shall be as representative as possible of the DEMO ones, but with much smaller dimensions and lower costs. Our team has performed a feasibility study for a fully superconducting magnet system of a compact tokamak reactor, in the framework of the activities carried out in Europe for the Divertor Tokamak Test (DTT) facility project. In the conceptual design presented in this paper, the magnet system is based on Cable-In-Conduit Conductors, adopting, whenever possible, the most recent developments in the field. It consists of 20 Toroidal Field, 6 Poloidal Field and 6 Central Solenoid module coils. The proposal is based on preliminary reference parameters such as plasma major and minor radii, magnetic field on plasma axis, plasma current, inductive flux etc., which should assure plasma scenarios suitable to investigate reliable power exhaust handling solutions. The main aspects driving the magnets design, from mechanical to thermo-hydraulic analyses, are here presented and discussed.