Confinement studies of neutral beam heated discharges in TFTR
- 1. Oak Ridge National Lab., TN (USA)
- 2. Princeton Univ., NJ (USA). Plasma Physics Lab.
Description
The TFTR tokamak has reached its original machine design specifications (Isub(p)=2.5 MA and Bsub(T)=5.2T). Recently, the D0 neutral beam heating power has been increased to 6.3 MW. By operating at low plasma current (Isub(p) approx. 0.8 MA) and low density (n-barsub(e) approx. 1 x 1019m-3), high ion temperatures (9 +- 2 keV) and rotation speeds (7 x 105 m/s) have been achieved during injection. At the opposite extreme, pellet injection into high current plasmas has been used to increase the line-average density to 8 x 1019 m-3 and the central density to 1.6 x 1020 m-3. This wide range of operating conditions has made possible scaling studies of the global energy confinement time in both ohmically and beam heated discharges as well as more detailed transport studies of the profile dependence. (author)
Additional details
Publishing Information
- Journal Title
- Plasma Phys. Control. Fusion
- Journal Volume
- 28
- Journal Issue
- 1A
- Series
- Plasma Phys. Control. Fusion.
- Journal Page Range
- 17-27
- CODEN
- PPCFE
Conference
- Title
- 12. European Conference on Controlled fusion and plasma physics.
- Dates
- 2-6 Sep 1985.
- Place
- Budapest (Hungary).
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 17066488
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BEAM INJECTION HEATING; CONFINEMENT TIME; ENERGY LOSSES; ENERGY TRANSFER; JOULE HEATING; NEUTRAL ATOM BEAM INJECTION; PELLET INJECTION; PERFORMANCE TESTING; PLASMA CONFINEMENT; SCALING LAWS; TFTR TOKAMAK
- Descriptors DEC
- BEAM INJECTION; CLOSED PLASMA DEVICES; CONFINEMENT; HEATING; PLASMA HEATING; TESTING; THERMONUCLEAR DEVICES; TOKAMAK DEVICES