A. Pereira , S. Moreno , J. Rodríguez , M. Villalba
{"title":"Kernel ridge regression estimation of high-frequency signals for nuclear fusion diagnostics","authors":"A. Pereira , S. Moreno , J. Rodríguez , M. Villalba","doi":"10.1016/j.fusengdes.2025.115261","DOIUrl":null,"url":null,"abstract":"<div><div>Estimating missing signals in plasma measurements is a significant challenge, particularly in fusion plasma devices where high-frequency temporal evolution signals provide valuable insight into the behavior of plasma. Indeed, occasional signal absence can impact to misfunction of other active diagnostics, leading to misinterpretation of the plasma state and inaccurate management of related control systems that affect the overall performance of the device. Therefore, the replacement of synthetic and accurate signals is a crucial aspect for system performance and reliability in fusion diagnostics, particularly when original signals are missing or erroneous. Precise prediction of high-frequency signals refers to time-series synthetic data that are modelled at an extremely fine scale. Due to the large number of samples, high frequency observations generally contain a large amount of data and most forecasting techniques based on dimensionality reduction or feature selection are not applicable as valuable information is lost before training periods. Besides, many real-time signals such as those in ITER, are non-stationary, meaning that their spectral content changes with time. In the current work a novel algorithm is presented based on kernel ridge regression (KRR) confidence machine. It provides a balance between computational efficiency and high accuracy across the entire frequency spectrum.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115261"},"PeriodicalIF":2.0000,"publicationDate":"2025-06-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379625004570","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
Estimating missing signals in plasma measurements is a significant challenge, particularly in fusion plasma devices where high-frequency temporal evolution signals provide valuable insight into the behavior of plasma. Indeed, occasional signal absence can impact to misfunction of other active diagnostics, leading to misinterpretation of the plasma state and inaccurate management of related control systems that affect the overall performance of the device. Therefore, the replacement of synthetic and accurate signals is a crucial aspect for system performance and reliability in fusion diagnostics, particularly when original signals are missing or erroneous. Precise prediction of high-frequency signals refers to time-series synthetic data that are modelled at an extremely fine scale. Due to the large number of samples, high frequency observations generally contain a large amount of data and most forecasting techniques based on dimensionality reduction or feature selection are not applicable as valuable information is lost before training periods. Besides, many real-time signals such as those in ITER, are non-stationary, meaning that their spectral content changes with time. In the current work a novel algorithm is presented based on kernel ridge regression (KRR) confidence machine. It provides a balance between computational efficiency and high accuracy across the entire frequency spectrum.
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.