Science Basis and Present Status of the new Divertor Tokamak Test facility
 
CNR Padova & DTT Consortium, Frascati
Mardi 07/07/2020, 14h00-15h15
Salle René GRAVIER 506 rdc, CEA Cadarache

Le Mardi 7 Juillet 2020 à 14h00 (via Skype, lien ci-dessous)

On Tuesday July 7, 2020, at 02:00 p.m. (Skype meeting, see link below)

Aura lieu le Séminaire / The following Seminar will be held:

 

"Science Basis and Present Status of the new Divertor Tokamak Test facility"

 

Présenté par / Presented by (en anglais /in english):

Piero MARTIN

de/from :

Università degli Studi di Padova,  Consorzio RFX, Padova, Italy

DTT Consortium, Frascati, Italy

 

Nous comptons sur votre présence !

We are looking forward your attending !

 

Résumé/Abstract  :

Science Basis and Present Status of the new Divertor Tokamak Test facility 

Piero Martin3 for the DTT team

 

One of the highest priority challenges for the exploitation of fusion as an energy source is the disposal of the non-neutronic energy and particle exhaust in a reactor. The new Divertor Tokamak Test (DTT) facility [1], is an experiment to address that challenge in high-field, high performance tokamak with full integration between core and edge plasma scenarios. Its construction is starting in Frascati, Italy.

DTT is superconducting tokamak with 6 T on-axis maximum toroidal magnetic field carrying plasma current up to 5.5 MA in pulses with length up to 100s. The D-shaped device is up-down symmetric, with major radius R=2.19 m and minor radius a=0.64 m. The auxiliary heating power coupled to the plasma at maximum performance is 45 MW, shared between 170 GHz ECRH, 60-90 MHz ICRH and negative ion beam injectors. This allows matching the PSEP/R values, where Psep is the power flowing through the last closed magnetic surface, with those of ITER and DEMO. DTT is in fact designed to reach PSEP/R =15 MW/m.

This talk will discuss the science basis for the experiment and the state of the art of the project. The presentation will start from the scientific background of the experiment,  then will move to its main physics driver and finally will discuss the expected plasma scenarios - in particular as far as plasma exhaust is concerned. Emphasis will be given to highlight the effort of designing an experimental tool, which will be a device not only for plasma exhaust studies, but also for the advancement of fusion science in the grand sense.

 

[1] “DTT-Divertor Tokamak Test facility. Interim Design Report”, R. Martone, R. Albanese, F. Crisanti, P. Martin, A Pizzuto Eds. April 2019, https://www.dtt-project.enea.it/downloads/DTT_IDR_2019_WEB.pdf

 

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