Confinement studies of neutral beam heated discharges in TFTR
- 1 January 1986
- journal article
- Published by IOP Publishing in Plasma Physics and Controlled Fusion
- Vol. 28 (1A) , 17-27
- https://doi.org/10.1088/0741-3335/28/1a/003
Abstract
The TFTR tokamak has reached its original machine design specifications (Ip=2.5 MA and BT=5.2 T). Recently, the D degrees neutral beam heating power has been increased to 6.3 MW. By operating at low plasma current (Ip approximately=0.8 MA) and low density (ne approximately=1*1019 m-3), high ion temperatures (9+or-2 keV) and rotation speeds (7*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*1019 m-3 and the central density to 1.6*1020 m-3. This wide range of operating conditions has enabled the authors to conduct 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.Keywords
This publication has 7 references indexed in Scilit:
- Confinement Studies In TFTRFusion Technology, 1985
- Repeating pneumatic hydrogen pellet injector for plasma fuelingReview of Scientific Instruments, 1985
- Thermal energy confinement scaling in PDX limiter dischargesNuclear Fusion, 1984
- Marfe: an edge plasma phenomenonNuclear Fusion, 1984
- Initial Confinement Studies of Ohmically Heated Plasmas in the Tokamak Fusion Test ReactorPhysical Review Letters, 1984
- Energy confinement scaling in Tokamaks: some implications of recent experiments with Ohmic and strong auxiliary heatingPlasma Physics and Controlled Fusion, 1984
- New techniques for calculating heat and particle source rates due to neutral beam injection in axisymmetric tokamaksJournal of Computational Physics, 1981