Abstract
Dual-band infrared (IR) measurements of the National Spherical Torus eXperiment (NSTX) Liquid Lithium Divertor (LLD) are reported that demonstrate liquid Li is more effective at removing plasma heat flux than Li-conditioned graphite. Extended dwell of the outer strike point (OSP) on the LLD caused an incrementally larger area to be heated above the Li melting point through the discharge leading to enhanced D retention and plasma confinement. Measurement of Tsurface near the OSP demonstrates a significant reduction of the LLD surface temperature compared to that of Li-coated graphite at the same major radius. Modeling of these data with a 2-D simulation of the LLD structure in the DFLUX code suggests that the structure of the LLD was successful at handling up to q⊥,peak = 5 MW/m2 inter-ELM and up to 10 MW/m2 during ELMs from its plasma-facing surface as intended, and provide an innovative method for inferring the Li layer thickness.
Original language | English |
---|---|
Pages (from-to) | S397-S400 |
Journal | Journal of Nuclear Materials |
Volume | 438 |
Issue number | SUPPL |
DOIs | |
State | Published - 2013 |
Funding
This work was supported by the US Department of Energy, Contract numbers DE-AC05-000R22725, DE-AC52-07NA27344, and DE-AC02-09CH11466.
Funders | Funder number |
---|---|
U.S. Department of Energy | DE-AC05-000R22725, DE-AC02-09CH11466, DE-AC52-07NA27344 |