Power transport to the PDX scoop limiter

Technical Report · Tue Jul 01 04:00:00 EDT 1986

DOI:https://doi.org/10.2172/5381259· OSTI ID:5381259

Kugel, H W; Bol, K; Budny, R; Fonck, R; Goldston, R; Grek, B; Kaita, R; Kaye, S; Knize, R J; Manos, D

Power transport to the PDX graphite scoop limiter was measured during both ohmic- and neutral-beam-heated discharges by observing its front face temperatures using an infrared camera. Measurements were made as a function of plasma density, current, position, fueling mode, and heating power for both co- and counter-neutral beam injection. The measured thermal load on the scoop limiter was 25 to 50% of the total plasma heating power. The measured peak front face midplane temperature was 1500/sup 0/C corresponding to a peak surface power density of 3 kW/cm/sup 2/. This power density implies an effective parallel power flow of 54 kW/cm/sup 2/ in agreement with the radial power distribution extrapolated from TVTS and calorimetry measurements. Symmetric and asymmetric thermal loads were observed. The asymmetric heat loads were predominantly skewed toward the respective ion drift directions for both co- and counter-injected beams. The results of transport calculations are consistent with the direction and magnitude of the observed asymmetries.

• Research Organization: Princeton Univ., NJ (USA). Plasma Physics Lab.
• DOE Contract Number: AC02-76CH03073
• OSTI ID: 5381259
• Report Number(s): PPPL-2363; ON: DE86015513
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
BEAM INJECTION
CLOSED PLASMA DEVICES
ELECTRIC HEATING
ELECTROMAGNETIC RADIATION
ENERGY TRANSFER
HEATING
INFRARED RADIATION
JOULE HEATING
LIMITERS
NEUTRAL ATOM BEAM INJECTION
PDX DEVICES
PLASMA HEATING
RADIATIONS
RESISTANCE HEATING
THERMONUCLEAR DEVICES
TOKAMAK DEVICES