Poster, 2023, ENG

Conceptual design of the DTT ECRH High voltage Power Supply system

De Nardi M.; Recchia M.; Gaio E.; Granucci G.; Garavaglia S.; Rispoli N.; Romano A.

Consorzio RFX (CNR, ENEA, INFN, Università di Padova, Acciaierie Venete SpA), Padova, Italy; CNR ISTP - Institute for Plasma Science and Technology, Section of Padova and Milano, Italy; DTT S.c.a r.l., C.R. Frascati, Italy; ENEA, Fusion and Nuclear Safety Department C.R. Frascati, Italy.

The Divertor Tokamak Test facility (DTT) is a Controlled Thermonuclear Fusion experiments which is in the scope of the Eurofusion programme to investigate the effects of thermal loads on the divertor. DTT will be realized at the Enea Research Center in Frascati, Italy and in the first experimental phase it will exploit an Electron Cyclotron Resonant Heating system (ECRH) exploiting 16 radio frequency (RF) sources (Gyrotrons) rated for 1MW power. These are fed in couple by a total of 8 high voltage power supply set (HVPS) based on the ITER design which procurement will be launched in 2023. Each HVPS is composed of one Main High Voltage Power Supply (MPS), rated for 55kV 110A, and two Body power Supplies (BPSs), rated for 35kV 20mA and this work will describe the power supply requirements, the conceptual design of the DTT HVPSs system, the layout and interfaces with the main systems.

SOFE 2023 - IEEE Symposium on Fusion Engineering, Oxford, UK, 9-13 July 2023

Keywords

DTT, ECRH, High voltage, Power Supply system

CNR authors

Granucci Gustavo, Rispoli Natale, Garavaglia Saul Francesco, Recchia Mauro, Gaio Elena

CNR institutes

ISTP – Istituto per la Scienza e Tecnologia dei Plasmi

ID: 483468

Year: 2023

Type: Poster

Creation: 2023-06-29 16:55:22.000

Last update: 2023-07-03 11:48:30.000

External links

OAI-PMH: Dublin Core

OAI-PMH: Mods

OAI-PMH: RDF

URL: https://sofe2023.co.uk/posters/

External IDs

CNR OAI-PMH: oai:it.cnr:prodotti:483468