High-harmonic fast wave heating experiments in CDX-U
- Princeton Univ., NJ (United States). Princeton Plasma Physics Lab.
- National Inst. of Fusion Science (Japan)
One of the primary objectives of the proposed National Spherical Tokamak Experiment (NSTX) is the investigation of very high {beta} regimes. Consequently, finding efficient methods of non-inductive heating and current drive required to heat and sustain such plasmas is of considerable importance. High-frequency fast waves are a promising candidate in this regard. However, in NSTX, the field-line pitch at the outer midplane will range from 0 up to 60 degrees from plasma start-up to current flattop. Thus, antenna strap orientation with respect to the edge magnetic field may have a serious impact on power coupling and absorption. To address this issue, the vacuum vessel of the Current Drive Experiment -- Upgrade (CDX-U) spherical tokamak has been upgraded to accommodate a rotatable two-strap antenna capable of handling several hundred kilowatts in short pulses. Details of the antenna design and results from loading measurements made as a function of power, strap angle, and strap phasing will be presented. Results from microwave scattering experiments will also be discussed.
- Research Organization:
- Princeton Univ., Princeton Plasma Physics Lab., NJ (United States)
- Sponsoring Organization:
- USDOE Office of Energy Research, Washington, DC (United States)
- DOE Contract Number:
- AC02-76CH03073
- OSTI ID:
- 304208
- Report Number(s):
- Cfp-3711; CONF-9704102-; ON: DE98051431; TRN: 99:002938
- Resource Relation:
- Conference: 12. topical conference on radio frequency power in plasmas, Savannah, GA (United States), 1-3 Apr 1997; Other Information: PBD: [1997]
- Country of Publication:
- United States
- Language:
- English
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