29th Symposium on Fusion Technology (SOFT 2016)

P2.008 The DTT device: plasma wall interaction issues

Sep 6, 2016, 2:20 PM

1h 40m

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

Board: 8

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

Speaker

Giorgio Maddaluno (FSN)

Description

on behalf of the EUROfusion WPDTT2 team & the DTT report contributors Within the frame of the DTT program, included in the EuroFusion roadmap, the design of a new Tokamak dedicated to tackle the Power Exhaust problem as an integrated bulk and edge plasma problem has been developed. The main guidelines used to work out the machine parameters will be shortly illustrated.To allow the machine flexibility in withstanding power exhaust as large as possible, a set of small internal coils will be installed in order to study many of the advanced magnetic configuration presently evaluated. Divertor magnetic configurations with different geometries and materials (including liquid metals) will be reported by several examples. The machine is foreseen to start the operations with a standard divertor configuration of actively cooled W. The first wall will consist of removable panels with a coating of W; its temperaure will be actively controlled aiming to operate up to a temperature of around 300º ÷400º C. The main expected machine performances have been explored by using different numerical codes. In particular the integrated plasma bulk and edge features have been studied by using the code COREDIV, also performing runs with different impurities at different concentrations.