Observation and modeling of inner divertor re-attachment in discharges with lithium coatings in NSTX

Journal Article · 19 December 2010 · Journal of Nuclear Materials

DOI: https://doi.org/10.1016/j.jnucmat.2010.12.041 · OSTI ID:1529185

Scotti, Filippo ^[1]; Soukhanovskii, V. A. ^[2]; Adams, M. L. ^[2]; Scott, H. A. ^[2]; Kugel, H. W. ^[1]; Kaita, R. ^[1]; Roquemore, A. L. ^[1]

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1. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
2. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

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. In conclusion, 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: Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA)
• Grant/Contract Number: AC52-07NA27344
• OSTI ID: 1529185
• Report Number(s): LLNL-JRNL--434143; 402083
• Journal Information: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: 1 Vol. 415; ISSN 0022-3115
• Publisher: ElsevierCopyright Statement
• Country of Publication: United States
• Language: English