Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
10645131 | Journal of Nuclear Materials | 2011 | 4 Pages |
Abstract
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.
Related Topics
Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
Filippo Scotti, V.A. Soukhanovskii, M.L. Adams, H.A. Scott, H.W. Kugel, R. Kaita, A.L. Roquemore,