• DocumentCode
    2758568
  • Title

    Recent Results in Large Helical Device

  • Author

    Nagayama, Y. ; Ikeda, K. ; Komori, A. ; Kumazawa, R. ; Morita, S. ; Ohyabua, N. ; Peterson, B.J. ; Sakakibara, S. ; Shimozuma, T. ; Yamada, H. ; Ashikawa, N. ; Chikaraishi, H. ; Emoto, M. ; Funaba, H. ; Goncharov, P. ; Goto, M. ; Hamada, Y. ; Ida, K. ; Id

  • Author_Institution
    Nat. Inst. for Fusion Sci., Toki
  • fYear
    2005
  • fDate
    Sept. 2005
  • Firstpage
    1
  • Lastpage
    6
  • Abstract
    This paper presents recent experimental results in the Large Helical Device (LHD), which is the world largest helical system (Rax~3.6 m, aav~0.6 m, Bax~2.75 T) and has capability of steady state operation because of the superconducting magnets. LHD confines the plasma with Tio~2 keV and ne ~0.8times1019 m-3 for 1905 sec using the ICRF heating. In this case, the total plasma heating energy was ~1.3 GJ. This indicates that high energy ions generated by ICRF is well confined. Large magnetic island in the vacuum field due to the error field is vanished in plasma with higher temperature or with higher beta, so the error field is not an issue in helical systems. The obtained averaged beta is more than 4.3 % in LHD. Since the beta is not limited by the MHD events or magnetic island but the beta is limited by the lack of heating power, further improvement of beta can be expected. Internal and external transport barrier have been also observed, and the electron temperature and the ion temperature exceed 10 keV in the improved confinement mode in LHD. Besides the potential of the disruption free steady stated operation, LHD experiment accumulates evidences so that fusion reactor becomes more realistic
  • Keywords
    fusion reactor ignition; plasma confinement; plasma magnetohydrodynamics; plasma radiofrequency heating; plasma temperature; plasma transport processes; stellarators; superconducting magnets; ICRF heating; LHD; Large Helical Device; MHD events; disruption free steady stated operation; electron temperature; error field; external transport barrier; fusion reactor; heating power; helical systems; high energy ions; internal transport barrier; ion temperature; magnetic island; plasma confinement; plasma heating energy; superconducting magnets; vacuum field; Electrons; Heating; Magnetic confinement; Magnetohydrodynamics; Plasma confinement; Plasma devices; Plasma temperature; Steady-state; Superconducting magnets; Vacuum systems;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering 2005, Twenty-First IEEE/NPS Symposium on
  • Conference_Location
    Knoxville, TN
  • Print_ISBN
    0-4244-0150-X
  • Electronic_ISBN
    0-4244-0150-X
  • Type

    conf

  • DOI
    10.1109/FUSION.2005.252854
  • Filename
    4018888