• DocumentCode
    3594194
  • Title

    Thermal cycling of water-cooled divertor mock-ups

  • Author

    Linke, J. ; Duwe, R. ; R?¶dig, M. ; Schuster, A.

  • Author_Institution
    Forschungszentrum Julich GmbH, Germany
  • Volume
    1
  • fYear
    1997
  • Firstpage
    373
  • Abstract
    During normal operation, the high heat flux components of ITER will suffer cyclic heat loads in the order of more than 5 MW/m2 . Candidate armor materials are carbon materials, tungsten alloys and beryllium. Most likely copper alloys will be used for the heat sink. In order to study the performance of several joining techniques between these materials, simulation experiments were performed in an electron beam facility. This paper describes the performance of beryllium-copper joints
  • Keywords
    Tokamak devices; fusion reactor design; Be; Be-C joints; C; ITER; armor materials; beryllium; carbon materials; cyclic heat loads; electron beam facility; heat sink; high heat flux components; joining techniques; normal operation; thermal cycling; tungsten alloys; water-cooled divertor mock-ups; Cooling; Copper alloys; Electron beams; Frequency; Heat sinks; Heating; Organic materials; Temperature; Testing; Tungsten;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
  • Print_ISBN
    0-7803-4226-7
  • Type

    conf

  • DOI
    10.1109/FUSION.1997.687058
  • Filename
    687058