• DocumentCode
    2436896
  • Title

    Progress of high power gyrotron development in JAEA

  • Author

    Sakamoto, Keishi ; Kasugai, Atsushi ; Kajiwara, Ken ; Takahashi, Koji ; Kobayashi, Noriyuki ; Oda, Yasuhisa

  • Author_Institution
    Japan Atomic Energy Agency, Naka
  • fYear
    2008
  • fDate
    15-19 June 2008
  • Firstpage
    1
  • Lastpage
    1
  • Abstract
    A 1 MW 170 GHz long pulse gyrotron is required for a power source of the electron cyclotron heating and current drive (EC H&CD) system on ITER (International Thermonuclear Experimental Reactor). In the ITER gyrotron development of JAEA (Japan Atomic Energy Agency), a stable 1 MW 170 GHz oscillation has been achieved at CW-relevant pulse duration (800 s), which is a twice of burning time of ITER plasma. The efficiency was 55% with the depressed collector with the precise optimization of the oscillation parameters in the hard self-excitation region during the oscillation. The power balance is measured calorimetrically, i.e., output power from the window is 1020 kW, power deposition to the collector is 742 kW, and a stray radiation output from the relief windows is 24 kW. Total ohmic-loss power into the inner components of the gyrotron is 63 kW. The power dissipation at the cavity agreed with the design value. The attained maximum efficiency in the long pulse mode is ~60%. The gyrotron has been working since March 2006 without major trouble, and records ~150 GJ of the output energy. The results satisfy the ITER requirement. As the frequency of 170 GHz is expected for the maximum toroidal field of 5.3 T at the plasma center of ITER, it is useful to estimate a frequency tunability of the gyrotron for the operation at lower toroidal filed. A simulation indicates that a similar performance is obtained at ~137 GHz oscillation at TE27,6 mode with the 170 GHz/TE31,8 mode oscillation. Both modes penetrate the diamond window of 1.853 mm in thickness. The triode magnetron injection gun (MIG) generates the rotational electron beam of low velocity divergence for both operation parameters. As for a fast frequency control, which will be useful for profile control in the fusion plasma, a He-free magnet with an additional super conducting sweeping coil was developed. A diameter of a room temperature bore is 240 mm, and the 7 T at the center. Using a commerci- - ally available standard DC power supplies, the magnetic field sweeping was demonstrated with a speed of 0.4 T/10 sec at 7 T.
  • Keywords
    Tokamak devices; fusion reactor instrumentation; gyrotrons; plasma instability; plasma radiofrequency heating; plasma toroidal confinement; DC power supplies; He-free magnet; ITER gyrotron; efficiency 55 percent; electron cyclotron heating and current drive system; frequency 170 GHz; fusion plasma profile control; high power gyrotron development; power 1 MW; rotational electron beam; superconducting sweeping coil; triode magnetron injection gun; Cyclotrons; Electrons; Frequency estimation; Gyrotrons; Heating; Inductors; Plasma measurements; Plasma temperature; Tellurium; Toroidal magnetic fields;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Plasma Science, 2008. ICOPS 2008. IEEE 35th International Conference on
  • Conference_Location
    Karlsruhe
  • ISSN
    0730-9244
  • Print_ISBN
    978-1-4244-1929-6
  • Electronic_ISBN
    0730-9244
  • Type

    conf

  • DOI
    10.1109/PLASMA.2008.4590753
  • Filename
    4590753