ALT-I pump limiter experiments with ICRF heating on TEXTOR
The ALT-I (Advanced Limiter Test-I) was installed on TEXTOR to benchmark the ability of a pump limiter as an efficient particle collector and to determine the physics of pump limiter operation. Experiments continue to show its capability of removing particles from the plasma edge under different operating conditions. In this paper we report first experimental results using ALT-I in conjunction with high power ICRF heating. The particle removal rate increases as the edge flux and density increase during the ICRF pulse. For a head geometry that collects flux from both electron and ion drift sides, the plasma temperature rise is asymmetric with electron temperature on the electron side increasing more than on the ion side during the ICRF pulse. When ALT-I is the major limiter, the particle fluxes on both sides increase by about the same factor and the particle flux on the ion side is always larger, by a factor of 1.5 to 2 than on the electron side during both ohmic and ICRF periods. The degradation of particle confinement inferred from Langmuir probe measurement is more than a factor of two at a maximum achieved power of 2 MW.
- Research Organization:
- California Univ., Los Angeles (USA). Center for Plasma Physics and Fusion Engineering; Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.); Sandia National Labs., Livermore, CA (USA)
- DOE Contract Number:
- FG03-85ER51069
- OSTI ID:
- 5725212
- Report Number(s):
- UCLA/PPG-968; CONF-860522-4; ON: DE86010914
- Resource Relation:
- Conference: 7. international conference on plasma surface interactions in controlled fusion devices, Princeton, NJ, USA, 5 May 1986
- Country of Publication:
- United States
- Language:
- English
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ALT-I pump limiter experiments
Related Subjects
LIMITERS
TEST FACILITIES
TEXTOR TOKAMAK
ELECTRON TEMPERATURE
ICR HEATING
JOULE HEATING
LANGMUIR PROBE
VACUUM SYSTEMS
CLOSED PLASMA DEVICES
ELECTRIC HEATING
ELECTRIC PROBES
HEATING
HIGH-FREQUENCY HEATING
PLASMA HEATING
PROBES
RESISTANCE HEATING
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
700209* - Fusion Power Plant Technology- Component Development & Materials Testing