In nuclear power system, the stable operation of accelerator driven subcritical system (ADS) is restricted by liquid metal corrosion. The background of the stainless steel’s application in liquid Pb-Bi alloy is summarized in nuclear power. Thereafter, the corrosion behavior of stainless steel in liquid Pb-Bi alloy in recent years is mainly reviewed. The corrosion mechanism of stainless steel in liquid Pb-Bi alloy includes:(1) dissolution corrosion of stainless steel by preferential dissolution of Ni in liquid Pb-Bi alloy; (2) oxidation corrosion by the reaction of Fe, Cr in stainless steel with dissolved oxygen in liquid Pb-Bi alloy; (3) grain boundary embrittlement by preferential dissolution and diffusion through grain boundary; (4) erosion and abrasion by the flowing liquid Pb-Bi alloy in dynamic corrosion condition. The corrosion of stainless steel in liquid Pb-Bi alloy is affected by following factors:e.g. time, temperature, alloy composition in stainless steel, dissolved oxygen concentration and flowing rate of liquid Pb-Bi alloy. Meanwhile, the protection technique is summarized, including surface treatment and modification of stainless steel, precise controlling dissolved oxygen concentration in liquid alloy and so on. Finally, the future research focus of liquid metal corrosion and the preparation of protective coating are prospected.