Published November 1, 2005 | Version v1
Journal article

Integrated modelling of the current profile in steady-state and hybrid ITER scenarios

  • 1. Oak Ridge National Laboratory, Oak Ridge, TN (United States)
  • 2. Associazione Euratom-ENEA sulla Fusione, CR. Frascati (Italy)
  • 3. Association EURATOM-CEA sur la Fusion, CEA Cadarache (France)
  • 4. Massachusetts Institute of Technology, Plasma Science and Fusion Center, Cambridge, MA (United States)
  • 5. Princeton Plasma Physics Laboratory, Princeton, NJ (United States)
  • 6. Associazione Euratom-ENEA-CNR sulla Fusione, IFP-CNR, Milano (Italy)
  • 7. ITER International Team ITER Naka Joint Work Site, Naka-machi, Naka-gun, Ibaraki-ken (Japan)
  • 8. CompX, Del Mar, CA (United States)
  • 9. Max Planck Institut fuer Plasmaphysik, EURATOM Association, Garching (Germany)
  • 10. Nuclear Fusion Institute, RRC 'Kurchatov Institute', 123128 Moscow (Russian Federation)
  • 11. General Atomics, San Diego, CA (United States)
  • 12. EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon (United Kingdom)
  • 13. FOM-Institute for Plasma Physics Rijnhuizen, Association EURATOM-FOM, Trilateral Euregio Cluster (Netherlands)

Description

We present integrated modelling of steady-state and hybrid scenarios for ITER parameters using several predictive transport codes. These employ models for non-inductive current drive sources in conjunction with various theory-based and semi-empirical transport models. In conjunction with the simulation effort, the current drive models are being evaluated in a series of cross-code and code-experiment comparisons under ITER-relevant conditions. New benchmark evaluations of current drive from injection of neutral beams (NBCD), electron cyclotron waves (ECCD) and lower hybrid waves (LHCD) are reported. Simulations using several transport modelling codes self-consistently calculate the heating and current drive sources using ITER design parameters. Operating constraints are also taken into account, although the calculations reported here still require further refinement. The modelling addresses both the final stationary state and dynamic access to it. The simulations indicate that generation and control of internal and edge barriers to access and maintain high confinement will be a major undertaking for future simulations, as well as a challenge for the ITER steady-state and hybrid experimental programme

Availability note (English)

Available online at http://stacks.iop.org/0029-5515/45/1309/nf5_11_012.pdf or at the Web site for the journal Nuclear Fusion (ISSN 1741-4326 ) http://www.iop.org/

Additional details

Publishing Information

Journal Title
Nuclear Fusion
Journal Volume
45
Journal Issue
11
Journal Page Range
p. 1309-1320
ISSN
0029-5515
CODEN
NUFUAU