Preliminary fault analysis of EFCC system in the Divertor Tokamak Test (DTT) facility

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-03-06 DOI:10.1016/j.fusengdes.2025.114915

Antonio Iaiunese , Raffaele Albanese , Andrea Gaetano Chiariello , Pasquale Zumbolo , Raffaele Martone

引用次数: 0

Abstract

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.

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来源期刊

Fusion Engineering and Design 工程技术-核科学技术

CiteScore

3.50

自引率

23.50%

发文量

275

审稿时长

3.8 months

期刊介绍： The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.