• DocumentCode
    1604466
  • Title

    DEMO: Heating and current drive system integration with blanket system

  • Author

    Grossetti, G. ; Harman, J. ; Mittwollen, M. ; Poli, E. ; Scherer, Theo ; Spah, P. ; Straus, D. ; Vaccaro, Alfredo

  • Author_Institution
    Karlsruhe Inst. of Technol. (Inst. of Appl. Mater.), Assoc. KIT-EURATOM, Karlsruhe, Germany
  • fYear
    2013
  • Firstpage
    1
  • Lastpage
    6
  • Abstract
    A preliminary design integration study of the Electron Cyclotron Heating and Current Drive, and Neutral Beam heating systems with the outboard Multi-Module blanket Segments in DEMO, is being presented. Scope of the work is to provide a first assessment on requirement analysis, concept generation and evaluation of the remote maintenance for a DEMO fusion power plant, in order to maximize its availability. The work has been divided into three phases: firstly, assessments to define the required openings for Electron Cyclotron and Neutral Beam launchers have been made. For the former, a Remote Steering concept has been considered, while for the latter a properly rescaled-ITER-like system has been taken into account. Secondly, CAD model of a DEMO sector has been modified to contain the port openings and a coarse port plug. Thirdly, a preliminary structural and electro-magnetic analysis has been carried out, considering two blanket concepts: Helium Cooled Lithium Lead and Helium Cooled Pebble Bed.
  • Keywords
    Tokamak devices; fusion reactor blankets; fusion reactor design; plasma toroidal confinement; CAD model; DEMO fusion power plant; DEMO sector; Helium Cooled Lithium Lead; Helium Cooled Pebble Bed; blanket system; coarse port plug; electro-magnetic analysis; electron cyclotron heating-current drive; heating-current drive system integration; neutral beam heating systems; outboard multimodule blanket segments; port openings; remote steering concept; rescaled-ITER-like system; Heating; Helium; Maintenance engineering; Manifolds; Niobium; Plasmas; Stress; DEMO; heating and current drive; nuclear fusion; remote handling;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering (SOFE), 2013 IEEE 25th Symposium on
  • Conference_Location
    San Francisco, CA
  • Print_ISBN
    978-1-4799-0169-2
  • Type

    conf

  • DOI
    10.1109/SOFE.2013.6635329
  • Filename
    6635329