Publications (4)
Deuterium retention in pre-lithiated samples and Li-D co-deposits in the DIII-D tokamak
M. Morbey, F. Effenberg, S. Abe +10
Divertor designs involving liquid lithium have been proposed as an alternative to solid designs and wall conditioning techniques. However, Li affinity with tritium poses a risk for…
Advances in neutral tungsten ultraviolet spectroscopy for the potential benefit to gross erosion diagnosis
C. A. Johnson, D. A. Ennis, S. D. Loch +8
A spectral survey of tungsten emission in the ultraviolet region has been completed in the DIII-D tokamak and the CTH torsatron to assess the potential benefit of UV emission for t…
Evaluation of silicon carbide as a divertor armor material in DIII-D H-mode discharges
T. Abrams, S. Bringuier, D. M. Thomas +7
Silicon carbide (SiC) represents a promising but largely untested plasma-facing material (PFM) for next-step fusion devices. In this work, an analytic mixed-material erosion model…
Impact of ELM control techniques on tungsten sputtering in the DIII-D divertor and extrapolations to ITER
T. Abrams, E. A. Unterberg, D. L. Rudakov +7
The free-streaming plus recycling model (FSRM) has recently been developed to understand and predict tungsten gross erosion rates from the divertor during edge localized modes (ELM…