NEUTRAL BEAM HEATING OF TEXTORFunded under: FP2-FUSION 10C
The TEXTOR tokamak has been designed for technology orientated research and is extensively used for systematic studies of the plasma adjacent to the limiters and wall, and for the application and development of novel limiters and coatings of surfaces facing the plasma. Carbonisation and boronisation of liner and limiters, and the pump limiters ALT I and ALT II, are some of the improvements of the last years. It is intended for the TEXTOR programme to have the plasma boundary layer and the loads to the limiters close to the conditions in large devices such as JET, DIII-D, JT60 and TFTR. ICR-heating of TEXTOR increased the loads to the liner and the limiters significantly. The addition of neutral beams of similar power will enlarge the range of parameters further. This paper presents first results of plasma heating in TEXTOR by two neutral beams, each of 1.2 MW power at 47 kV, with co, counter, or balanced injection of hydrogen into a deuterium plasma tangentially.
Bibliographic Reference: EXTRACT: PROCEEDINGS OF THE 16TH EUROPEAN CONFERENCE ON CONTROLLED FUSION AND PLASMA PHYSICS, VOLUME 13B (1989) PART III, PP. 1221-1224, EUROPEAN PHYSICAL SOCIETY
Record Number: 1989128088800 / Last updated on: 1992-11-04
Original language: EN
Available languages: en