Assessment of the structural integrity of in-vessel ELM control coils located on the high field side of the TCABR tokamak

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-09-17 DOI:10.1016/j.fusengdes.2025.115434

A.S. Bouzan , R. Ramos Jr , F.M. Salvador , J.I. Elizondo , G.P. Canal

{"title":"Assessment of the structural integrity of in-vessel ELM control coils located on the high field side of the TCABR tokamak","authors":"A.S. Bouzan , R. Ramos Jr , F.M. Salvador , J.I. Elizondo , G.P. Canal","doi":"10.1016/j.fusengdes.2025.115434","DOIUrl":null,"url":null,"abstract":"<div><div>The use of Resonant Magnetic Perturbations (RMP) is a well-established technique to control Edge Localized Modes (ELM) in tokamak plasmas. Uncontrolled ELM instabilities can dissipate high energy fluxes that are not withstood by the most advanced materials. In-vessel RMP coils on the low field side (LFS) are usually employed to suppress/mitigate ELMs, but research indicates that applying RMP fields on the high field side (HFS) may improve ELM control. To investigate the effects of RMP fields on both sides, the Tokamak à Chauffage Alfvén Brésilien (TCABR) is being upgraded. Among the improvements, a set of 108 RMP coils will be installed inside the vacuum vessel: 54 coils on the LFS and 54 coils on the HFS. These coils will have to operate with both direct (up to 2kA) or alternating (up to 1kA) currents, high voltages (up to 4kV), and frequencies up to 10kHz. Consequently, high stress levels due to temperature gradients and electromagnetic loads act in the coils casing. This work presents structural analyses of the in-vessel coils that will be installed on the HFS, for operations in direct current. In these analyses, finite element simulations using the software ANSYS were carried out to evaluate the feasibility of installing this set of coils. The maximum stresses in the CP coil components were obtained and compared with the allowable stresses for each component, showing that the proposed set of CP coils can be safely installed and operated in TCABR.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115434"},"PeriodicalIF":2.0000,"publicationDate":"2025-09-17","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/S0920379625006301","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

The use of Resonant Magnetic Perturbations (RMP) is a well-established technique to control Edge Localized Modes (ELM) in tokamak plasmas. Uncontrolled ELM instabilities can dissipate high energy fluxes that are not withstood by the most advanced materials. In-vessel RMP coils on the low field side (LFS) are usually employed to suppress/mitigate ELMs, but research indicates that applying RMP fields on the high field side (HFS) may improve ELM control. To investigate the effects of RMP fields on both sides, the Tokamak à Chauffage Alfvén Brésilien (TCABR) is being upgraded. Among the improvements, a set of 108 RMP coils will be installed inside the vacuum vessel: 54 coils on the LFS and 54 coils on the HFS. These coils will have to operate with both direct (up to 2 kA) or alternating (up to 1 kA) currents, high voltages (up to 4 kV), and frequencies up to 10 kHz. Consequently, high stress levels due to temperature gradients and electromagnetic loads act in the coils casing. This work presents structural analyses of the in-vessel coils that will be installed on the HFS, for operations in direct current. In these analyses, finite element simulations using the software ANSYS were carried out to evaluate the feasibility of installing this set of coils. The maximum stresses in the CP coil components were obtained and compared with the allowable stresses for each component, showing that the proposed set of CP coils can be safely installed and operated in TCABR.

查看原文本刊更多论文

TCABR托卡马克高场侧船载ELM控制线圈结构完整性评价

利用共振磁扰动（RMP）控制托卡马克等离子体的边缘局域模式（ELM）是一种成熟的技术。不受控制的ELM不稳定性会耗散最先进材料无法承受的高能量通量。通常采用低场侧（LFS）的容器内RMP线圈来抑制/减轻ELM，但研究表明，在高场侧（HFS）应用RMP线圈可以改善ELM的控制。为了研究RMP电场对双方的影响，正在对托卡马克 Chauffage alvvac - bracimsiilien （TCABR）进行升级。在这些改进中，将在真空容器内安装一组108个RMP线圈：LFS上安装54个线圈，HFS上安装54个线圈。这些线圈必须在直流（高达2ka）或交流（高达1ka）电流，高压（高达4kv）和频率高达10khz的情况下工作。因此，由于温度梯度和电磁载荷的高应力水平在线圈外壳中起作用。这项工作介绍了将安装在HFS上的容器内线圈的结构分析，用于直流操作。在这些分析中，利用ANSYS软件进行了有限元模拟，以评估安装这套线圈的可行性。得到了CP线圈各部件的最大应力，并与各部件的许用应力进行了比较，表明所设计的CP线圈可以在TCABR中安全安装和运行。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

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.