Transient electrical behavior of DEMO toroidal field coils system in normal operation and fault conditions

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

Fusion Engineering and Design Pub Date : 2025-03-09 DOI:10.1016/j.fusengdes.2025.114941

G. Messina , P. Zito , M. Manganelli , S. Valenti , L. Morici , V. Corato , A. Ferro

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引用次数: 0

Abstract

This study examines the transient electrical behavior of the DEMO Toroidal Field Coils (TFC) system under normal operation and fault conditions. The DEMO superconducting magnet system comprises a Central Solenoid, Poloidal Field coils, and d-shaped Toroidal Field Coils, the latter all connected in series. Fast Discharge Units (FDUs) are integrated to protect the system by quickly dissipating stored magnetic energy during a quench. Simulations were conducted using MATLAB/Simulink and ANSYS/Simplorer, incorporating the TFC inductance matrix, power cable connection impedances, and stray parameters of discharge resistors. The results highlight the significant voltage peaks that occur during fast discharges, which can stress the insulation of TFCs and associated components. Various fault scenarios, including ground faults and short circuits, were analyzed to determine their impact on peak transient voltages. The findings highlight the importance of a consistent quench protection system and the accurate design of the insulation level coordination to ensure the safety and reliability of superconducting magnets. The simulations showed consistent results across both platforms, validating the models used. Future work will aim to refine the models and explore additional fault scenarios to further enhance system performance and reliability. This comprehensive fault analysis provides critical insights for the design and safety of the DEMO TFC system, ensuring its reliable operation under diverse conditions.

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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.