A multi-classifier disruption predictor based on optimized support vector machine on EAST

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Dongmei Liu , Xinli Zhu , Shuangbao Shu , Shun Wang , Biao Shen , Bihao Guo
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引用次数: 0

Abstract

Plasma disruption presents a significant risk to the operation of tokamaks. In this study, we propose a multi-classifier disruption predictor based on the support vector machine optimized using an improved particle swarm optimization algorithm. This approach is specifically designed for the EAST experiments conducted since 2020. A dataset comprising 194 disruption and 401 non-disruption shots was selected to evaluate the predictor's performance. Twelve representative diagnostic signals were selected by analyzing the statistical characteristics of the data in the plasma current flattop phase, with each signal corresponding to a sub-classifier. The performance of each signal's sub-classifier predictor was considered, leading to the development of a weighting scheme for the prediction results. The final prediction result was obtained from a linear combination of these results by their respective weights. With optimized weight schemes, the predictor effectively identified plasma diagnostic signal features, achieving a true positive rate of 93.9 % and a false positive rate of <4.99 %, indicating its ability to trigger alarms promptly. Overall, the results demonstrate the feasibility of the proposed approach for disruption prediction on EAST.
基于优化支持向量机的多分类器干扰预测
等离子体破坏对托卡马克的运行构成了重大风险。在本研究中,我们提出了一种基于改进粒子群优化算法优化的支持向量机的多分类器干扰预测器。这种方法是专门为2020年以来进行的EAST实验设计的。一个包含194个干扰和401个非干扰镜头的数据集被选择来评估预测器的性能。通过分析等离子体电流平顶相位数据的统计特征,选择12个具有代表性的诊断信号,每个信号对应一个子分类器。考虑了每个信号的子分类器预测器的性能,从而开发了预测结果的加权方案。最终的预测结果由这些结果各自的权重进行线性组合得到。通过优化的权重方案,该预测器有效地识别了血浆诊断信号特征,真阳性率为93.9%,假阳性率为4.99%,表明其能够及时触发警报。总体而言,结果证明了该方法用于东线中断预测的可行性。
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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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