Corrigendum to “Preliminary Proof-of-concept of Real-time Divertor Heat Flux Control from Infrared Cameras with Nitrogen Injection in the DIII-D Tokamak” [Fusion Engineering and Design 224 (March 2026) 115598]

Recent results from the DIII-D tokamak and implications for future devices

Thermofluid analysis of free surface liquid divertor in tokamak fusion reactor

Experimental observations of lithium as a plasma-facing surface in the DIII-D tokamak divertor

In-situ measurement of surface modifications of tungsten exposed to pulsed high heat flux for divertor design in tokamak-type fusion nuclear reactors