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Measurements of energy and flux of neutrals at the wall in the Tokamak Fusion Test Reactor

Journal Article · · J. Vac. Sci. Technol., A; (United States)
DOI:https://doi.org/10.1116/1.576234· OSTI ID:6317066
The energy and flux of charge-exchange neutral deuterium incident on the wall in the Tokamak Fusion Test Reactor (TFTR) were measured using a carbon resistance probe. This device utilizes the increase in electrical resistance of a thin carbon film produced by the impinging particles. Particle energies and fluxes were determined from the stopping effect of thin layers of silicon over the carbon. Film thicknesses were chosen to give a useful energy range from about 50 to 5000 eV. Time-resolved data were obtained for the first time by using a transient digitizer to record the signals every millisecond during the discharge. The deduced flux and Maxwellian temperature were 0.7 x 10/sup 14//cm/sup 2/s and kT = 350 eV, respectively, during Ohmic heating. Neutral beam heating (10 MW) increased the temperature by a factor of 4 and increased the flux by a factor of 2. The observed flux of neutrals to the wall is large enough for changes in the recycling of these particles to affect plasma fueling significantly.
Research Organization:
Sandia National Laboratories, Albuquerque, New Mexico 87185-5800
OSTI ID:
6317066
Journal Information:
J. Vac. Sci. Technol., A; (United States), Journal Name: J. Vac. Sci. Technol., A; (United States) Vol. 7:3; ISSN JVTAD
Country of Publication:
United States
Language:
English