{"title":"An interpretable isoflux-based observer for plasma shape control errors in tokamaks","authors":"Alessandro Tenaglia, Federico Pesamosca, Federico Felici, Daniele Carnevale, Stefano Coda, Adriano Mele, Antoine Merle","doi":"10.1016/j.fusengdes.2024.114618","DOIUrl":null,"url":null,"abstract":"In tokamaks, plasma shape control is often achieved through a so-called approach that regulates the poloidal flux differences between a reference point and a set of control points and magnetic field values at suitable locations to obtain the desired shape. Despite its simplicity, this approach presents two primary drawbacks: first, a method is needed to translate desired shape modifications, , radial or vertical shifts, into variations of the poloidal flux and magnetic field references; second, interpreting controller performance metrics may not be straightforward, since control errors are expressed in terms of physical quantities, , flux differences, magnetic fields, that cannot be directly related to positional errors. In this work, we propose a comprehensive methodology to establish relationships that link variations of poloidal flux and magnetic field values concerning a nominal plasma equilibrium in a predefined set of shape control points to local deformations of the Last Closed Flux Surface (LCFS). The effectiveness of this approach is demonstrated on the Tokamak à Configuration Variable (TCV) model through extensive simulations that consider various plasma configurations and shape modifications.","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9000,"publicationDate":"2024-08-12","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://doi.org/10.1016/j.fusengdes.2024.114618","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
In tokamaks, plasma shape control is often achieved through a so-called approach that regulates the poloidal flux differences between a reference point and a set of control points and magnetic field values at suitable locations to obtain the desired shape. Despite its simplicity, this approach presents two primary drawbacks: first, a method is needed to translate desired shape modifications, , radial or vertical shifts, into variations of the poloidal flux and magnetic field references; second, interpreting controller performance metrics may not be straightforward, since control errors are expressed in terms of physical quantities, , flux differences, magnetic fields, that cannot be directly related to positional errors. In this work, we propose a comprehensive methodology to establish relationships that link variations of poloidal flux and magnetic field values concerning a nominal plasma equilibrium in a predefined set of shape control points to local deformations of the Last Closed Flux Surface (LCFS). The effectiveness of this approach is demonstrated on the Tokamak à Configuration Variable (TCV) model through extensive simulations that consider various plasma configurations and shape modifications.
在托卡马克中,等离子体形状控制通常是通过所谓的方法来实现的,即调节参考点和一组控制点之间的极磁通量差值以及适当位置的磁场值,以获得所需的形状。这种方法虽然简单,但有两个主要缺点:首先,需要一种方法将所需的形状修改(如径向或纵向移动)转化为极磁通量和磁场参考值的变化;其次,解释控制器的性能指标可能并不简单,因为控制误差是以物理量(如通量差、磁场)来表示的,无法直接与位置误差相关。在这项工作中,我们提出了一种综合方法,用于建立一种关系,将预定义的一组形状控制点中标称等离子体平衡的极性通量和磁场值的变化与最后封闭通量面(LCFS)的局部变形联系起来。通过考虑各种等离子体配置和形状修改的大量模拟,在托卡马克 à 配置变量(TCV)模型上演示了这种方法的有效性。
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.