In the context of the fourth-generation nuclear energy system, the lead-cooled fast reactor (LFR) is named for its use of either pure lead or lead-bismuth alloy as a coolant. Lead-bismuth eutectic (LBE), as a potential nuclear coolant material, is considered one of the candidate coolant materials for both lead-cooled fast reactors (LFR) and accelerator-driven subcritical systems (ADS) due to its characteristics such as high boiling point, high density, high thermal conductivity, and low viscosity. Stainless steel structural materials, including 316L, 410, CLAM, 15-15Ti steel, are widely used in structural components of LFR and ADS systems because of their high structural strength and excellent oxidation resistance. However, there are still some shortcomings in lead-based reactor structural materials, leading to serious dissolution corrosion and oxidation corrosion, resulting in performance deterioration of reactor materials.