Initial-temperature profiles on the PDX inner toroidal limiter

Technical Report · Thu Sep 01 00:00:00 EDT 1983

DOI:https://doi.org/10.2172/5639340· OSTI ID:5639340

Ulrickson, M; Kugel, H W

The temperature profiles resulting from plasma operation on the PDX vertical, large area, inner toroidal limiter have been measured during both ohmic and neutral-beam-heated discharges using a scanning infrared camera. An asymmetric double-peaked temperature profile is seen after neutral-beam-heated discharges. Disruptions in ohmically heated discharges are found to be preceded by a single-peaked deposition and succeeded by an initially symmetric double-peaked deposition. The results were compared with the Schmidt model for scrape-off at a toroidal limiter and it was found that the measured double-peaked temperature profiles yielded scrape-off lengths consistent with previous measurements.

• Research Organization: Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
• DOE Contract Number: AC02-76CH03073
• OSTI ID: 5639340
• Report Number(s): PPPL-2041; ON: DE83017812
• Country of Publication: United States
• Language: English

Related Subjects

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