Development of the electron cyclotron resonance heating system for Divertor Tokamak Test

Author:

Garavaglia Saul1ORCID,Balbinot Luca2ORCID,Bruschi Alessandro1ORCID,Busi Daniele3ORCID,Bussolan Andrea1,Fanale Francesco45,Granucci Gustavo1ORCID,Moro Alessandro1ORCID,Platania Paola1ORCID,Rispoli Natale1ORCID,Romano Afra45ORCID,Sartori Emanuele2ORCID,Schmuck Stefan1ORCID,Simonetto Alessandro1ORCID,Vassallo Espedito1ORCID

Affiliation:

1. Institute for Plasma Science and Technology—CNR 1 , via Cozzi 53, 20125 Milano, Italy

2. Consorzio RFX 2 , Corso Stati Uniti 4, 35127 Padova, Italy

3. Department of Mechanical Engineering, Politecnico di Milano 3 , via La Masa 1, 20156 Milan, Italy

4. ENEA, Fusion and Nuclear Safety Department 4 , C. R. Frascati, via E. Fermi 45 00044, Frascati, Italy

5. DTT S.c. a r. l., C. R. Frascati 5 , via E. Fermi 45 00044, Frascati, Italy

Abstract

The Divertor Tokamak Test (DTT) facility, whose construction has started in Frascati (Italy), will be equipped with an ECRH (electron cyclotron resonance heating) system including 32 gyrotrons as microwave power sources. The procurement of the first batch of sources with 16 MW total power, based on 170 GHz/≥ 1 MW/100 s vacuum tubes, is in progress and will be available for the first DTT plasma. The system is organized into four clusters of 8 gyrotrons each. The power is transmitted from the Gyrotron Hall to the Torus Hall Building (THB) by a quasioptical transmission line (TL), mainly composed of large mirrors shared by eight beams coming from eight different gyrotrons and designed for up to 1.5 MW power per single beam, similar to the TL installed at the stellarator W7-X. One of novelties introduced in the DTT system is that the mirrors of the TLs are embodied in a vacuum enclosure, using large metal seals, mainly to avoid air absorption and risk of arcs. The main reason is to reduce the risk of air breakdown, maintaining a pressure of 10−5 mbar far away from the Paschen minimum. The TL estimated volume is between ∼70 and ∼85 m3. The direct connection of the TL to the tokamak vacuum vessel has been evaluated, and different solutions have been proposed in order to prevent a possible impact on DTT operations. The microwave power is injected into the tokamak using independent single-beam front-steering launchers, real-time controlled and located in the equatorial and upper ports of four DTT sectors. In-vessel piezoelectric walking drives are the most promising candidates for the launcher mirror movement considering their compactness and capability to operate in an environment with strong magnetic field under ultra-high vacuum. The DTT ECRH system design, presented here, is based mainly on existing and assessed solutions, although the challenging adaptations to the DTT case are considered.

Publisher

American Vacuum Society

Subject

Materials Chemistry,Electrical and Electronic Engineering,Surfaces, Coatings and Films,Process Chemistry and Technology,Instrumentation,Electronic, Optical and Magnetic Materials

Reference21 articles.

1. R. Martone , R.Albanese, F.Crisanti, and P.Martinwith the support of DTT community, “DTT Divertor Tokamak Test facility Interim Desing Report” (DTT Interim Design Report,2019), https://www.dtt-project.it/DTT_IDR_2019_WEB.pdf.

2. The European roadmap towards fusion electricity

3. DTT - Divertor Tokamak Test facility: A testbed for DEMO

4. The DTT device: System for heating

5. Electron cyclotron resonance heating and current drive in toroidal fusion plasmas

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