新控制的50年历史的飞轮发电机EZ2 -一个必要的更新，以最新的工业状态为ASDEX升级的环形领域

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-09-24 DOI:10.1016/j.fusengdes.2025.115446

Oliver Seibold-Benjak , Michael Rott , Claus-Peter Käsemann , Stanislaw Classen , the ASDEX Upgrade Team

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引用次数: 0

摘要

自1973年以来，“Energiezentrale 2 - EZ2″”的传动系统一直是ASDEX环形磁场线圈的核心电源，利用其167 MVA发电机。上一次升级是在1998年进行的。由于近年来电力电子设备故障和更换部件的可用性不断恶化，ASDEX升级团队决定更新驱动、发电机和辅助系统的电力电子设备和控制系统，使其达到工业可用技术的最新状态。本文重点研究了ASDEX主励磁线圈的非平凡电流控制的实现，该控制仅通过控制发电机励磁电流来实现。详细描述了发电机控制系统从概念开发到验证的过程，为今后的工作奠定了基础。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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New control of the 50-years-old flywheel generator EZ2– a necessary update to the latest industrial state of the art for the toridal field of ASDEX upgrade

The drive train of the "Energiezentrale 2 – EZ2″ has served as the core of the power supply for the toroidal field coils of ASDEX since 1973, utilizing its 167 MVA generator. The last upgrade was carried out in 1998. Due to the combination of power electronics failures and the steadily worsening availability of replacement parts in recent years, the ASDEX Upgrade team decided to renew the power electronics and control systems for the drive, generator, and auxiliary systems, bringing them up to the latest state of industrially available technology.

This paper specifically focuses on the implementation of the non-trivial current control for the main field coils of ASDEX, which is achieved solely through the control of the generator’s excitation current. It provides a detailed description of the process from concept development to the validation of the generator control system, laying the foundation for future work.

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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.