The liquid lithium-lead breeding blanket in the international thermonuclear experimental reactor is one of the major international concerns and one of the potential conceptual designs for the fusion reactor.
Reduced activation ferritic-martensitic steels are being considered for application in future fusion technology as the relevant structural material, which will be in contact with the lithium-lead breeding material.
According to the test results, comprehensive evaluations of these findings have been performed to determine the wastage rates and mechanisms for the conceptual design of the fusion reactor.
From micro to macro, systematic cross-scale models are needed for the understanding of corrosion/wastage mechanisms in fusion reactor engineering applications.
