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  4. Varistor development for in-vessel magnetic field coils in nuclear fusion devices
 
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2023
Journal Article
Title

Varistor development for in-vessel magnetic field coils in nuclear fusion devices

Abstract
So called “varistors”, based on doped ceramic materials (Clarke, 1999; Gupta, 1990; Garcia, 2022; Modine, 1988) could provide interesting functionality for future nuclear fusion scientific experiments and power plants. They are of special interest for passive in-vessel coils but also for protection of active in-vessel coil feedthroughs. Due to the special high vacuum, high radiation environment, commercially available components are not sufficient for the required parameters. The IPP1 decided to start a technology development project in cooperation with the IKTS2 to improve parameter space and to demonstrate feasibility of the concepts described in this paper. Also very first results of already developed low-voltage, high current-density varistors are given.
Author(s)
Teschke, Markus
Max-Planck-Institut für Plasmaphysik
Firmbach, Fabian
Fraunhofer-Institut für Keramische Technologien und Systeme IKTS  
Hutzler, Thomas  
Fraunhofer-Institut für Keramische Technologien und Systeme IKTS  
Martin, Hans-Peter
Fraunhofer-Institut für Keramische Technologien und Systeme IKTS  
Schönfeld, Katrin  
Fraunhofer-Institut für Keramische Technologien und Systeme IKTS  
Zammuto, Irene
Max-Planck-Institut für Plasmaphysik
Journal
Fusion engineering and design  
DOI
10.1016/j.fusengdes.2023.113586
Language
English
Fraunhofer-Institut für Keramische Technologien und Systeme IKTS  
Keyword(s)
  • Varistors

  • In-vessel coils

  • Passive stabilization loops

  • Overvoltage protection

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