Lower hybrid counter current drive for edge current density modification in DIII-D
- Lawrence Livermore National Lab., CA (US)
- Massachusetts Inst. of Technology, Cambridge, MA (US). Plasma Fusion Center
- General Atomics, San Diego, CA (US)
Each of the Advanced Tokamak operating modes in DIII-D is thought to have a distinctive current density profile. So far these modes have only been achieved transiently through experiments which ramp the plasma current and shape. Extension of these modes to steady state requires non-inductive current profile control, e.g. with lower hybrid current drive (LHCD). Calculations of LHCD have been done for DIII-D using the ACCOME and CQL3D codes, showing that counter driven current at the plasma edge can cancel some of the undesirable edge bootstrap current and potentially extend the VH-mode. Results are presented for scenarios using 2.45 GHz LH waves launched from both the midplane and off-axis ports. The sensitivity of the results to injected power, n{sub e} and T{sub e}, and launched wave spectrum is also shown.
- Research Organization:
- Lawrence Livermore National Lab., CA (United States); General Atomics, San Diego, CA (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-7405-ENG-48; AC03-89ER53277
- OSTI ID:
- 10181172
- Report Number(s):
- UCRL-JC-113264; CONF-9304112-23; ON: DE93019157; TRN: 93:019995
- Resource Relation:
- Conference: 10. topical conference on radio frequency power in plasmas,Boston, MA (United States),1-3 Apr 1993; Other Information: PBD: Jul 1993
- Country of Publication:
- United States
- Language:
- English
Similar Records
Predicted performance of a tangential viewing hard x-ray camera for the DIII-D high field side lower hybrid current drive experiment
Lower hybrid current drive for edge current density modification in DIII-D: Final status report