Overview of the Divertor Tokamak Test (DTT) coil power supplies
The Divertor Tokamak Test (DTT) facility was mainly conceived to study the problem of the plasma power exhaust. Nevertheless, being a state-of-the-art tokamak including several power supply systems to generate high currents in the in-vessel and ex-vessel coils, it could be also exploited as a test b...
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Veröffentlicht in: | Fusion engineering and design 2023-03, Vol.188, p.113442, Article 113442 |
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Hauptverfasser: | , , , , , , , , , , , , , , , , , , , |
Format: | Artikel |
Sprache: | eng |
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Online-Zugang: | Volltext |
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Zusammenfassung: | The Divertor Tokamak Test (DTT) facility was mainly conceived to study the problem of the plasma power exhaust. Nevertheless, being a state-of-the-art tokamak including several power supply systems to generate high currents in the in-vessel and ex-vessel coils, it could be also exploited as a test bench to progress in tokamak power supply technology, for example by introducing and verifying novel solutions for ITER and DEMO. This paper presents the DTT coil power supply systems, focusing on the criticalities of the requirements and on the novelties of the adopted solutions. |
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ISSN: | 0920-3796 1873-7196 |
DOI: | 10.1016/j.fusengdes.2023.113442 |