• DocumentCode
    2727417
  • Title

    ICRH system for the Ignitor machine

  • Author

    Carpignano, F. ; Coppi, B. ; Nassi, M.

  • Author_Institution
    MIT, Cambridge, MA, USA
  • Volume
    2
  • fYear
    1993
  • fDate
    11-15 Oct 1993
  • Firstpage
    1065
  • Abstract
    The ICRH system adopted for the Ignitor machine is characterized by a maximum power delivered to the plasma of 18 MW and a wide range of operating frequencies (100<ν<210 MHz). The main functions of the system are to control the time evolution of the plasma temperature and the toroidal current density profiles, to keep the region where g<1 small and to suppress the possible onset of sawtooth oscillations by fast particle stabilization in relatively low plasma density discharges. The ICRH system can also be used to accelerate the attainment of ignition, to extend the conditions under which ignition is possible, to explore the conditions under which the second stability region of finite β plasmas can be achieved, to produce significant levels of power from D-3He fusion reactions, to reduce the Volt-sec requirement and to perform current drive experiments in low density discharges (ne<2×1020 m-3 ). The wide range of frequencies has been adopted in order to operate in different regimes (ω=ωCD, ω(C 3)He, 2ωCT, ωCH at maximum toroidal magnetic field). This additional source of heating allows Ignitor to produce a significant level of α power in low plasma current and low toroidal magnetic field discharges, while operating at lower mechanical and thermal stresses and sustaining the discharges for a longer period of time. The ICRH system is composed of 6 antennae, completely inserted in first wall recesses, that are driven by amplifiers through the equatorial ports of the machine. Each antenna module composed of straps grouped in poloidal pairs, is able to couple up to 3 MW of heating power to the plasma
  • Keywords
    antennas in plasma; deuterium; fusion reactor design; fusion reactor fuel; fusion reactor ignition; fusion reactors; helium; plasma density; plasma oscillations; plasma radiofrequency heating; plasma temperature; plasma toroidal confinement; sawtooth instability; thermal stresses; 100 to 210 MHz; 18 MW; 3 MW; D-3He fusion reactions; D-He; ICRH system; Ignitor machine; antennae; current drive experiments; fast particle stabilization; finite β plasmas; fusion reactor ignition; low plasma density discharges; low toroidal magnetic field discharges; plasma temperature time evolution control; poloidal pairs; sawtooth oscillations; second stability region; thermal stresses; toroidal current density profiles control; Fault location; Frequency; Heating; Helium; Ignition; Plasma density; Plasma stability; Plasma temperature; Thermal stresses; Toroidal magnetic fields;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on
  • Conference_Location
    Hyannis, MA
  • Print_ISBN
    0-7803-1412-3
  • Type

    conf

  • DOI
    10.1109/FUSION.1993.518506
  • Filename
    518506