Preliminary fault analysis of EFCC system in the Divertor Tokamak Test (DTT) facility
Tokamaks use Error Field Correction Coils to reduce the error fields due to misalignments and assembly tolerances in the main magnetic system, with the aim of avoiding plasma instabilities. These coils may fail for various reasons, e.g., problems in insulation or power supply. This paper presents a method to evaluate the capability of correcting error fields in case of failure of one or more coils. The effectiveness is assessed in terms of the Three Mode Error Index metric. The paper shows the results obtained for the Divertor Tokamak Test facility, but the method is quite general and can be applied to any device.
Authors
- R. Martone (ORCID: https://orcid.org/0000-0002-5675-5491)
- Pasquale Zumbolo (ORCID: https://orcid.org/0000-0002-1573-7713)
- Andrea Gaetano Chiariello (ORCID: https://orcid.org/0000-0003-0506-8955)
- R. Albanese (ORCID: https://orcid.org/0000-0003-4586-8068)
- Antonio Iaiunese (ORCID: https://orcid.org/0000-0003-2343-3960)
Institutions
- Parthenope University of Naples (IT)
- University of Campania "Luigi Vanvitelli" (IT)
- Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali di Frascati (IT)
- Consorzio CREO (Italy) (IT)
- Frascati Scienza (IT)
- University of Naples Federico II (IT)
Publication Details
- Journal
- Fusion Engineering and Design
- Published
- 2025-03-06
- DOI
- https://doi.org/10.1016/j.fusengdes.2025.114915
- Primary Topic
- Magnetic confinement fusion research
- Type
- article
- Field-Weighted Citation Impact
- 0.00