Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Observation And Modeling Of Inner Divertor Re-attachment In Discharges With Lithium Coatings in NSTX

Technical Report ·
DOI:https://doi.org/10.2172/1001676· OSTI ID:1001676
In the National Spherical Torus Experiment (NSTX), modifications to the inner divertor plasma regimes are observed in high triangularity, H-mode, NBI heated discharges due to lithium coatings evaporated on the plasma facing components. In particular, the drop in the recombination rate, the reduced neutral pressure and the reduced electron density (inferred from Stark broadening measurements of high-n deuterium Balmer lines) suggested that the inner divertor, which is usually detached in discharges without lithium, re-attached. Experimental results are compared to simulations obtained with a 1D partially ionized plasma transport model integrated in the non-local thermodynamic equilibrium radiation transport code CRETIN to understand how the reduced recycling affects the divertor parameters in NSTX discharges with lithium coatings.
Research Organization:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
Sponsoring Organization:
USDOE Office of Science (SC)
OSTI ID:
1001676
Report Number(s):
PPPL-4584
Country of Publication:
United States
Language:
English

Similar Records

Observation and modeling of inner divertor re-attachment in discharges with lithium coatings in NSTX
Journal Article · Sat Dec 18 19:00:00 EST 2010 · Journal of Nuclear Materials · OSTI ID:1529185

Snowflake Divertor Configuration in NSTX
Conference · Fri Dec 31 23:00:00 EST 2010 · OSTI ID:1037042

Effect of Lithium PFC Coatings on NSTX Density Control
Journal Article · Mon Aug 21 00:00:00 EDT 2006 · Journal of Nuclear Materials · OSTI ID:936701