Predictive modeling of a lithium vapor box divertor in NSTX-U using SOLPS-ITER

The unmitigated heat flux in attached operation of a fusion power plant is predicted to be destructive to any solid divertor surface. Detachment, whereby the plasma pressure drops significantly before reaching the divertor target thus greatly reducing the heat flux and sputtering, will be necessary...

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Bibliographic Details
Main Authors: E.D. Emdee, R.J. Goldston, J.D Lore, X. Zhang
Format: Article
Language:English
Published: Elsevier 2021-06-01
Series:Nuclear Materials and Energy
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S235217912100082X