Community Research and Development Information Service - CORDIS


One of the primary goals of fusion research is to find ways of increasing the energy confinement time. A major method of increasing the energy confinement time within a given machine is to operate a higher plasma current. Although Z(eff) in DIII-D is generally less than 2, high radiated power and metal accumulation have been observed during high current beam heated H-mode discharges. Reduction of metallic impurity flux has been obtained on numerous tokamaks with the introduction of a thin carbon film. This paper reports the successful carbonisation of the DIII-D vacuum vessel which allowed for routine high current operation, and it examines the confinement properties of carbonised discharges. It is concluded that deuterium H-mode energy confinement with carbonisation increases with increasing plasma current and decreases with increasing neutral beam power.

Additional information

Authors: SCHISSEL D P ET AL., General Atomics, San Diego (US);WINTER J, Institut für Plasmaphysik, Kernforschungsanlage Jülich GmbH, Jülich (DE)
Bibliographic Reference: Report: GA-A20085 EN (1990) 4 pp.
Availability: Available from General Atomics, Department of Energy, San Diego, CA 92138 (US)
Record Number: 199011835 / Last updated on: 1994-12-02
Original language: en
Available languages: en