Di Marzo, Vittorio (2025) Electromagnetic and mechanical design of the central solenoid in tokamak devices: from LTS to HTS configurations. [Tesi di dottorato]
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| Tipologia del documento: | Tesi di dottorato |
|---|---|
| Lingua: | English |
| Titolo: | Electromagnetic and mechanical design of the central solenoid in tokamak devices: from LTS to HTS configurations |
| Autori: | Autore Email Di Marzo, Vittorio vittorio.dimarzo@unina.it |
| Data: | 5 Dicembre 2025 |
| Numero di pagine: | 228 |
| Istituzione: | Università degli Studi di Napoli Federico II |
| Dottorato: | Information technology and electrical engineering |
| Ciclo di dottorato: | 38 |
| Coordinatore del Corso di dottorato: | nome email Russo, Stefano stefano.russo@unina.it |
| Tutor: | nome email Ambrosino, Roberto [non definito] |
| Data: | 5 Dicembre 2025 |
| Numero di pagine: | 228 |
| Parole chiave: | Nuclear Fusion, Tokamak, Central Solenoid, Superconducting Magnets, HTS, AC losses |
| Settori scientifico-disciplinari del MIUR: | Area 09 - Ingegneria industriale e dell'informazione > ING-INF/04 - Automatica |
| Informazioni aggiuntive: | Appartenenza al ciclo 38 (XXXVIII) |
| Depositato il: | 10 Dic 2025 22:50 |
| Ultima modifica: | 12 Ago 2026 05:38 |
| URI: | https://www.fedoa.unina.it/id/eprint/17029 |
Abstract
The global pursuit of carbon-neutral energy sources has revitalized interest in nuclear fusion as a long-term, safe, and sustainable solution for baseload electricity generation. Tokamak devices, based on magnetic confinement, represent the most advanced concept toward controlled thermonuclear fusion. Within these machines, the superconductive Central Solenoid (CS) component provides the flux for plasma initiation, current ramp-up and ultimately sets the discharge pulse length. However, its design involves extremely demanding electromagnetic and mechanical constraints, especially in view of fatigue life and the large magnetic field required. This Ph.D. thesis focuses on the electromagnetic and mechanical design of the CS in tokamak devices, moving from LowTemperature Superconducting (LTS) toward High-Temperature Superconducting (HTS) technologies. A comprehensive workflow has been developed, integrating optimization and both electromagnetic and mechanical verifications. The proposed methodology identifies CS configurations in a pre-design phase capable of maximizing the magnetic flux swing while ensuring structural integrity and fatigue compliance over reactor operating cycles. A finite-element validation strategy enables consistent assessment of metallic and non-metallic components, including a preliminary AC losses evaluation. This methodology is applied to the Divertor Tokamak Test (DTT), currently under construction in Frascati, Italy, through two case studies: (i) a full-HTS CS configuration, and (ii) the current reference DTT configuration featuring an LTS CS with an HTS insert. Results confirm promising electromagnetic and mechanical performances, providing guidelines for the next generation of superconducting magnets for fusion applications.
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