• DocumentCode
    1950529
  • Title

    Activity of national institute for Fusion Science toward realization of helical fusion reactor

  • Author

    Komori, A. ; Kaneko, Osamu ; Sakakibara, Sho ; Horiuchi, R. ; Sagara, Akihiko ; Yamada, Hiroyoshi ; Takeiri, Y.

  • Author_Institution
    Nat. Inst. for Fusion Sci., Toki, Japan
  • fYear
    2011
  • fDate
    26-30 June 2011
  • Firstpage
    1
  • Lastpage
    8
  • Abstract
    Since 1989, National Institute for Fusion Science (NIFS) promotes academic approaches toward exploration of fusion science for steady-state helical reactor and realizes establishment of comprehensive understanding of toroidal plasmas as an inter-university research organization and a key center of worldwide fusion research. Three key projects, Large Helical Device (LHD) project, simulation science project, and fusion engineering project are organized for early realization of net current free fusion reactor. The LHD has been producing high-performance plasmas comparable to those of large tokamaks, and several new findings with regard to plasma physics have been obtained. The simulation science project contributes understanding and systemizing the physical mechanism of plasma confinement in fusion plasmas and exploring complexity science of a plasma for realization of the numerical test reactor. In the fusion engineering project, the design of the helical fusion reactor has been progressed based on the development of superconducting coils, the blanket, fusion materials and tritium handling.
  • Keywords
    plasma toroidal confinement; stellarators; superconducting coils; tritium handling; fusion engineering project; fusion materials; helical fusion reactor; large helical device project; net current free fusion reactor; numerical test reactor; plasma confinement; plasma physics; simulation science project; steady-state helical reactor; superconducting coils; toroidal plasmas; tritium handling; Carbon; Inductors; Magnetic confinement; Physics; Plasma temperature; Visualization; Waste heat; Helical Reactor; Large Helical Device; fusion engineering; numerical simulation; steady-state operation;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering (SOFE), 2011 IEEE/NPSS 24th Symposium on
  • Conference_Location
    Chicago, IL
  • ISSN
    1078-8891
  • Print_ISBN
    978-1-4577-0669-1
  • Electronic_ISBN
    1078-8891
  • Type

    conf

  • DOI
    10.1109/SOFE.2011.6052351
  • Filename
    6052351