Published January 2005 | Version v1
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Nonthermal particle and full-wave diffraction effects on heating and current drive in the ICRF and LHRF regimes

  • 1. MIT Plasma Science and Fusion Center, Cambridge, MA (United States)
  • 2. Oak Ridge National Laboratory, Oak Ridge, TN (United States)
  • 3. Princeton Plasma Physics Laboratory, Princeton, NJ (United States)
  • 4. CompX Corporation, Del Mar, CA (United States)
  • 5. Mission Research Corp., Newington, VA (United States)
  • 6. Lodestar, Boulder, CO (United States)
  • 7. Max-Planck-Institut fuer Plasmaphysik, Garching (Germany)
  • 8. Association EURATOM-CEA sur la Fusion, Cadarache (France)

Description

Fast waves (FW) are a primary technique for heating and current drive (CD) on the proposed burning plasma device, ITER, and lower hybrid (LH) waves are a candidate for edge current profile control. The models used to simulate these two waves rely on assumptions of Maxwellian populations that allow efficient analytic implementations of the plasma response, and in the case of the LH wave, the ray tracing models used are able to follow the very small wavelengths in a continuum manner without requiring a fine computational grid. Recent advances in algorithms and parallel computational methods have allowed these assumptions to be tested, permitting more accurate estimates of heating deposition and CD efficiencies in a burning plasma. Absorption by energetic particles for both waves can be significant, reducing electron heating and associated CD. Wave propagation and absorption is dependent on the velocity space distribution of particles in the plasma and on the geometric effects of focusing and diffraction. Fusion born alpha particles and neutral beam ions may interact with these waves in a manner that cannot be accurately modeled by Maxwellian distributions. The AORSA2D code has been modified to use a generalized non-Maxwellian conductivity, and has been applied to ITER reference scenarios. Preliminary analysis for ITER suggests that alpha absorption may be limited to a few tens of percent, and thus, allow reasonable CD efficiencies, assuming that the RF does not significantly alter the alpha slowing-down distribution. We also discuss the interaction of an energetic Tritium tail with FW in ITER. In addition, the effects of diffraction on LH waves in toroidal geometry are not well understood because computational limits have prohibited full-wave simulations at those small wavelengths. Simulations of LH waves have been restricted to WKB ray tracing techniques and 1D full-wave in the past, but the availability of massively parallel architectures have made full-wave calculations using an electromagnetic field solver tractable. The TORIC code has been adapted to run on parallel architectures making it possible to resolve the slow electrostatic LH wave. We present full-wave simulations of LH slow and fast waves in toroidal geometry for Alcator C-Mod at values of (ωpe/ωce)2 comparable to those expected in the ITER device. (author)

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Part of:
20th IAEA fusion energy conference 2004. Conference proceedings

Additional details

Publishing Information

ISBN
92-0-100405-2
Imprint Title
20th IAEA fusion energy conference 2004. Conference proceedings
Imprint Pagination
3451 p.
Journal Issue
no. 25/CD
Series
C and S papers series
Journal Page Range
[10 p.]
ISSN
1562-4153
Report number
IAEA-CSP--25/CD

Conference

Title
20. IAEA fusion energy conference 2004
Dates
1-6 Nov 2004
Place
Villamoura (Portugal)

Optional Information

Notes
16 refs, 6 figs
Secondary number(s)
TH/P4--35