• DocumentCode
    301040
  • Title

    Advances in JT-60U facilities and its operation

  • Author

    Kimura, T.

  • Author_Institution
    Naka Fusion Res. Establ., JAERI, Ibaraki, Japan
  • Volume
    1
  • fYear
    1995
  • fDate
    30 Sep-5 Oct 1995
  • Firstpage
    724
  • Abstract
    Recent advances in the JT-60 upgrade (JT-60U) facilities are described which have been made for supporting various physics programs aiming at obtaining reactor-grade plasmas with higher performance in quasi-steady state. It has been proved that B4C-converted (0.3 mm thick) carbon fiber composite (CFC) graphite divertor tiles and decaborane-based boronization using a mixture of deuterium and helium as working gas of a glow discharge are effective for wall conditioning. For improving the confinement and edge plasma characteristics, the operation of divertor plasmas with a shape of high triangularity in excess of 0.4 has been started. Feedback control of neutron production by NBI injection has been demonstrated for establishment of advanced plasma control in steady state operation. With regard to the heating systems, the increase in the NBI beam power up to 36 MW has accelerated the progress in the JT-60U plasma performance and the increase in the ICRF power up to 6.4 MW has progressed the studies on fast ion behavior, especially the TAE mode since 1994. Although ten years passed since the first plasma of the JT-60, the integrity of its main facilities has been kept by good maintenance activities. Moreover, the JT-60U operational efficiency has been much improved by the above advances of the facilities, which has given rise to remarkable progress in the JT-60U plasma performance has been successfully obtained. Two important developments of a negative-ion-based NBI system with beam energy of 500 keV and injection power of 10 MW and an advanced closed pumped divertor are now in progress towards steady-state operation with high performance
  • Keywords
    Tokamak devices; fusion reactor design; fusion reactor materials; fusion reactor operation; nuclear reactor maintenance; plasma beam injection heating; plasma radiofrequency heating; 10 MW; 36 MW; 500 keV; 6.4 MW; B4C; C; ICRF power; JT-60 upgrade; JT-60U; NBI beam power; NBI injection; TAE mode; carbon fiber composite; closed pumped divertor; confinement; decaborane-based boronization; divertor plasmas; edge plasma; facilities; fast ion; graphite divertor tiles; maintenance; neutron production; plasma control; steady state operation; wall conditioning; Deuterium; Glow discharges; Helium; Physics; Plasma accelerators; Plasma confinement; Plasma properties; Shape; Steady-state; Tiles;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium
  • Conference_Location
    Champaign, IL
  • Print_ISBN
    0-7803-2969-4
  • Type

    conf

  • DOI
    10.1109/FUSION.1995.534326
  • Filename
    534326