• DocumentCode
    2721878
  • Title

    Confinement capability of ITER-EDA design

  • Author

    Uckan, Nermin A.

  • Author_Institution
    Oak Ridge Nat. Lab., TN, USA
  • Volume
    1
  • fYear
    1993
  • fDate
    11-15 Oct 1993
  • Firstpage
    183
  • Abstract
    Confinement capability of the ITER-EDA (R=7.75 m, I=25 MA) operational scenarios is evaluated and compared with the ITER CDA (R=6 m, 22 MA). The ignition capability of ITER EDA is somewhat higher than that of CDA by a factor of 1.1-1.2 with empirical power law scalings and by a factor of 1.5-2 with offset linear scalings. Simulations with the RLW χ(∇Te)crit model show that both the EDA and CDA scenarios operates in L-mode, however CDA ignition margin is much smaller. With empirical scalings, the required L-mode confinement enhancement factor [H=τE/τE(scaling)] corresponding to, for example, ITER89-P L-mode scaling would be 1.5-1.6 in ITER EDA relative to 1.8 in CDA for 10% He (plus 1% Be) concentration. At a higher concentration of He of 20-25%, the confinement capability is deteriorated and the required confinement enhancement factor (over empirical L-mode scalings) is ⩾2. The Ohmic confinement time is a factor of two higher in the EDA design (as compared to the CDA), yielding a strong reduction in the auxiliary power required to reach ignition. In 1.5-D simulations with L-mode enhancement factors of H⩾1.2 allowed ohmic ignition with 25 MA, ignition was aided by initially peaked density profiles (and low He content) during the start-up
  • Keywords
    fusion reactor design; fusion reactor ignition; fusion reactor operation; fusion reactors; plasma density; plasma instability; plasma simulation; plasma toroidal confinement; Conceptual Design Activities; Engineering Design Activities; ITER CDA; ITER-EDA design; ITER89-P L-mode scaling; L-mode; Ohmic confinement time; Rebut-Lallia-Watkins model; auxiliary power; confinement capability; confinement enhancement factor; empirical power law scalings; fusion reactor; ignition capability; initially peaked density profiles; offset linear scalings; ohmic ignition; operational scenarios; simulations; Coils; Electronic design automation and methodology; Guidelines; Helium; Ignition; Physics; Plasma confinement; Plasma temperature; Safety; Steady-state;
  • 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.1993.518311
  • Filename
    518311