AbstractThis paper describes a new experimental liquid-lithium facility for investigation of the corrosion-mass transfer and stability of electrical insulator self-healing coatings in the self-cooled vanadium-lithium blanket. This monometallic test facility was constructed of V-4 wt.% Ti-4 wt.% Cr alloy and simulates the conditions projected for a fusion reactor blanket. The vanadium alloy-liquid-lithium test facility will provide test velocities up to 4 m s−1, temperatures up to about 700°C and a system temperature difference up to 250°C. The facility provides the control and monitoring of impurities in liquid lithium.
Particle control in steady state magnetic fusion reactors by solid and liquid lithium plasma-facing components