ALT-II progress report and proposal, December 1989--December 1990
The Advanced Limiter Test (ALT-11) is a joint international program among the United States, the Federal Republic of Germany, and Japan to investigate the performance of a toroidal belt pump limiter in a tokamak, to investigate the behavior of the plasma edge, and to relate edge behavior to overall core energy and particle confinement. The experiments are carried out in the TEXTOR tokamak at KFA Juelich, Federal Republic of Germany. The ALT-II experiment was installed in TEXTOR in 1987 with the objectives of optimizing plasma performance in a limiter tokamak, and of studying the physics of particle removal, density and impurity control, and confinement enhancement by a toroidal belt pump limiter. The ALT-II program addresses large area limiter tokamak operation issues by providing a program specifically directed toward plasma optimization and particle and impurity control by a toroidal belt limiter in a machine dedicated to the investigation of plasma-wall interactions. TEXTOR features the most advanced set of edge plasma diagnostics of any tokamak for the task of diagnosing and understanding the impact of the limiter on the plasma confinement and performance. With the addition of 3.4 MW of neutral beam injection heating (NBI) to the existing 4 MW of ion cyclotron resonance heating (ICRH), TEXTOR also provides power densities equivalent to larger tokamaks.
- Research Organization:
- Univ. of California, Los Angeles, CA (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- FG03-85ER51069
- OSTI ID:
- 6911759
- Report Number(s):
- DOE/ER/51069-T5; ON: DE93004142; TRN: 92-038207
- Country of Publication:
- United States
- Language:
- English
Similar Records
ALT-II armor tile design for upgraded TEXTOR operation
Langmuir probe measurements in the TEXTOR tokamak during ALT-I pump limiter experiments
Related Subjects
PUMPED LIMITERS
TESTING
BEAM INJECTION HEATING
PLASMA DIAGNOSTICS
PLASMA IMPURITIES
PROGRESS REPORT
TEXTOR TOKAMAK
CLOSED PLASMA DEVICES
DOCUMENT TYPES
HEATING
IMPURITIES
LIMITERS
PLASMA HEATING
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
700420* - Fusion Technology- Plasma-Facing Components- (1992-)