Developing a reactor-compatible divertor has been identified as a particularly challenging technology problem for magnetic confinement fusions. Application of Lithium (Li) in NSTX resulted in improved H-mode confinement, H-mode power threshold reduction, and other plasma performance benefits. The liquid lithium coating of the divertor surfaces can also provide a "sacrificial" protective layer to protect the substrate solid material from transient high heat flux such as the ones caused by the edge localized modes. These promising Li results in NSTX and related modelling calculations motivated the liquid lithium divertor concept disclosed.
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