I. Zammuto , A. Herrmann , M. Weißgerber , W. Zeidner , N. Arden , N. Berger , V. Brack , T. Lunt , B. Petzold , V. Rohde , G. Schall , M. Teschke , T. Vierle , S. Vorbrugg , Paolo Badino , Marco Dani
{"title":"Final implementation of the new upper divertor with coils in ASDEX Upgrade","authors":"I. Zammuto , A. Herrmann , M. Weißgerber , W. Zeidner , N. Arden , N. Berger , V. Brack , T. Lunt , B. Petzold , V. Rohde , G. Schall , M. Teschke , T. Vierle , S. Vorbrugg , Paolo Badino , Marco Dani","doi":"10.1016/j.fusengdes.2025.115028","DOIUrl":null,"url":null,"abstract":"<div><div>Theoretical investigations into detachment mechanisms have emphasized the potential of addressing the power exhaust challenge through alternative divertor configurations, such as the Snowflake and X-Divertor concepts. These configurations are realized by integrating two coils positioned along the outer strike line of the upper divertor. This concept is set to be tested soon at ASDEX Upgrade (AUG), a mid-sized tokamak located in Garching. Since August 2022, AUG has been undergoing a maintenance phase to facilitate various tasks, including the installation of novel components such as the upper divertor equipped with cryopump, inner and outer divertor modules, and notably, two concentric coils, each capable of carrying a current of 52 kAt.</div><div>The coil conductor design has been specifically tailored to meet these requirements. It features a hollow copper conductor with an internal water-cooling channel, surrounded by electrical insulation made of Tefzel—a fluorine-based polymer—and encased in a stainless-steel jacket. This design ensures compatibility with the stringent ultra-high vacuum (UHV) conditions of the vacuum vessel while also providing protection against electrical faults. Extensive electrical and thermal testing of the conductor has been carried out in recent years to validate its performance.</div><div>A distinctive feature of these coils is their construction from a single, continuous length of conductor, eliminating internal electrical joints to reduce the risk of failures. However, this design approach required a significant effort to wind the coils within the highly constrained space of the AUG vacuum vessel. A sophisticated bending procedure, supported by in-house-developed tools, was devised to address the spatial limitations and meet the required precision.</div><div>Following an extensive testing phase using a custom-built mock-up, the two coils were successfully bent and installed within the AUG vacuum vessel, integrating seamlessly into the new upper divertor structure. This paper provides a detailed overview of the project's main components, its current status, and the critical assembly phases involved.</div><div>Index Terms— ASDEX Upgrade, Divertor, In-vessel coils Snowflake divertor; advanced divertor configuration.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 115028"},"PeriodicalIF":2.0000,"publicationDate":"2025-06-01","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/S0920379625002285","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"2025/4/9 0:00:00","PubModel":"Epub","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
Theoretical investigations into detachment mechanisms have emphasized the potential of addressing the power exhaust challenge through alternative divertor configurations, such as the Snowflake and X-Divertor concepts. These configurations are realized by integrating two coils positioned along the outer strike line of the upper divertor. This concept is set to be tested soon at ASDEX Upgrade (AUG), a mid-sized tokamak located in Garching. Since August 2022, AUG has been undergoing a maintenance phase to facilitate various tasks, including the installation of novel components such as the upper divertor equipped with cryopump, inner and outer divertor modules, and notably, two concentric coils, each capable of carrying a current of 52 kAt.
The coil conductor design has been specifically tailored to meet these requirements. It features a hollow copper conductor with an internal water-cooling channel, surrounded by electrical insulation made of Tefzel—a fluorine-based polymer—and encased in a stainless-steel jacket. This design ensures compatibility with the stringent ultra-high vacuum (UHV) conditions of the vacuum vessel while also providing protection against electrical faults. Extensive electrical and thermal testing of the conductor has been carried out in recent years to validate its performance.
A distinctive feature of these coils is their construction from a single, continuous length of conductor, eliminating internal electrical joints to reduce the risk of failures. However, this design approach required a significant effort to wind the coils within the highly constrained space of the AUG vacuum vessel. A sophisticated bending procedure, supported by in-house-developed tools, was devised to address the spatial limitations and meet the required precision.
Following an extensive testing phase using a custom-built mock-up, the two coils were successfully bent and installed within the AUG vacuum vessel, integrating seamlessly into the new upper divertor structure. This paper provides a detailed overview of the project's main components, its current status, and the critical assembly phases involved.
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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