基于顺序折扣算法的JT-60SA在线无监督撕裂模式检测

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Tatsuya Yokoyama, Shizuo Inoue, Shinichiro Kojima, Takuma Wakatsuki, Maiko Yoshida
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引用次数: 0

摘要

建立了一种基于统计异常检测和顺序折现算法的非经验撕裂模式检测器模型,并通过JT-60SA初始运行阶段的实验数据验证了该模型的预测性能。检测和预测中断的发生是保护托卡马克装置免受中断造成的损坏的一个重要问题,使用机器学习技术的经验模型正在开发中。基于异常检测的非经验模型是解决这种经验模型是否可以外推到未来托卡马克的固有不确定性问题的一种可能解决方案。所建立的检测器模型具有良好的预测性能,其处理时间小于未使用gpu等先进器件的JT-60SA的控制周期时间。结果表明,采用顺序折现算法的统计异常检测方法不仅适用于JT-60SA等离子体控制器,而且适用于未来的ITER和DEMO等设备。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Online un-supervised tearing mode detection with sequentially discounting algorithms for JT-60SA
A non-empirical tearing mode detector model based on statistical anomaly detection with sequentially discounting algorithms has been developed, and its prediction performance has been demonstrated with experiment data in the JT-60SA initial operation phase. Detection and prediction of the occurrence of disruptions is an important issue to protect the tokamak device from the damage caused by disruptions, and empirical models using machine learning techniques are being developed. A non-empirical model based on anomaly detection is one possible solution to an inherent problem of uncertainty as to whether such empirical models can be extrapolated to future tokamaks. The developed detector model has shown a good prediction performance, and its processing time was smaller than the control cycle time of the JT-60SA without any advanced devices such as GPUs. The result suggests that the statistical anomaly detection with sequentially discounting algorithms is a good choice to be implemented in the plasma controller not only in the JT-60SA but also in the future devices such as ITER and DEMO.
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来源期刊
Fusion Engineering and Design
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.
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