Published January 1986 | Version v1
Journal article

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