CNR ExploRA

Articolo in rivista, 2023, ENG, 10.1016/j.fusengdes.2023.113797

Progress on the conceptual design of the antennas for the DTT ECRH system

Fanale F.; Baiocchi B.; Bruschi A.; Busi D.; Bussolan A.; Figini L.; Garavaglia S.; Granucci G.; Romano A.

ENEA, Fusion and Nuclear Safety Department, C.R. Frascati (RM), Italy; DTT S.C. a r.l., Frascati (RM), Italy; CNR ISTP - Institute for Plasma Science and Technology, Milano, Italy; Department of Mechanical Engineering, Politecnico di Milano, Italy.

One of the main goals of the Divertor Tokamak Test (DTT) facility is to reach a ratio of power crossing the separatrix over the major radius of about 15 MW m - 1, as the one expected in DEMO. For this purpose, up to 45 MW of external additional heating power shall be coupled to the plasma, provided by Electron Cyclotron Resonance Heating (ECRH), Ion Cyclotron Resonance Heating and Neutral Beam Injection. The foreseen total ECRH power installed at full power shall be 32 MW, generated using 1 MW/170 GHz gyrotrons, for 100 s. The present ECRH system foresees two launching antennas per DTT sector, based on the front-steering concept. The equatorial antenna is dedicated to plasma heating and current drive and the upper antenna to the stabilization of MHD instabilities. This paper focuses on the latest design concept for these two antennas and on the definition of the ex-vessel matching optics unit of the last section of the evacuated Transmission Line (TL). The design has been updated to be compatible with the insertion of CVD diamond windows, to separate the vacuum environment of DTT from the one of the TL. This choice requires adding corrugated waveguide sections between the last mirror of the TL and the first mirror inside the port, requiring some adaptation of the in-vessel optics and of the supporting structure. The possibility to modify the steering range for the launching mirror has been also investigated to be compatible with the new design of the first wall and for the upper antenna, to reach the q = 2 surface in the new plasma scenario.

Fusion engineering and design (Print) 192 , pp. 113797-1–113797-8