在 JET 进行经验误差场控制，为 ITER 启动做准备

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

Fusion Engineering and Design Pub Date : 2024-10-21 DOI:10.1016/j.fusengdes.2024.114694

L. Piron , Carlos Paz-Soldan , Morten Lennholm , Krassimir Kirov , Daniel Valcarcel , Matteo Baruzzo , Tommaso Bolzonella , Rachele Cicioni , Peter De Vries , Nicolò Ferron , Matteo Gambrioli , Y. Gribov , R. Henriques , Emmanuel Joffrin , Piero Martin , Massimiliano Mattei , Gabriele Manduchi , Luigi Pangione , Leonardo Pigatto , Alfredo Pironti , Luca Zabeo

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引用次数: 0

摘要

这项工作报告了在 JET 开展的误差场识别和控制研究，以及开发用于热核实验堆的经验 EF 控制器的进展情况。在执行非中断罗盘扫描方法（Paz-Soldan C. 等人，Nuclear Fusion 62 (2022) 126007）之后，JET 实时中央控制器中包含了经验性外频控制器，该方法允许识别外频源和用于误差场补偿的电流。在测试经验 EF 控制器时，观察到天生锁定的 n = 1 模式自旋上升，并在 1.8 MA 等离子体电流、2.1 T 环形磁场情况下探索了比其他方法更低的密度机制。这些实验结果证明了 EF 校正的好处。为准备在热核实验堆中进行 EF 校正研究，开发了用于热核实验堆的经验 EF 控制器，并将其集成到等离子体控制系统数据库中。

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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Empirical error field control at JET in preparation of ITER start-up

This work reports on error field identification and control studies carried out at JET and insights on the development of the empirical EF controller for ITER. The empirical EF controller has been included in the JET real-time central controller following the execution of the non-disruptive compass scan method (Paz-Soldan C. et al., Nuclear Fusion 62 (2022) 126007), which allowed the identification of the EF source and the currents for error field compensation. When testing the empirical EF controller, born locked n = 1 modes have been observed to spin-up and a lower density regime has been explored in the 1.8 MA plasma current, 2.1 T toroidal magnetic field scenario than otherwise achievable. These experimental results demonstrate the benefits of EF correction. In preparation of EF correction studies in ITER, the empirical EF controller for ITER has been developed and integrated in the plasma control system database.

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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.