核电系统中，液态金属腐蚀问题是影响加速器驱动次临界系统(ADS)稳定服役的关键。概述了液态Pb-Bi合金和不锈钢在核电中的应用背景。在此基础上，重点综述了近年来常用不锈钢材料在液态Pb-Bi合金环境下的腐蚀行为，其中不锈钢在液态Pb-Bi合金中的腐蚀机制包括:(1)不锈钢中Ni元素在液态Pb-Bi合金中优先溶解而发生的溶解腐蚀;(2)不锈钢中Fe、Cr等元素与液态Pb-Bi合金中的溶解氧反应发生的氧化腐蚀;(3)晶界处优先溶解扩散导致的晶界脆化;(4)动态腐蚀条件下液态Pb-Bi合金流动对不锈钢造成的冲蚀与磨蚀等。针对不锈钢在液态Pb-Bi合金中的腐蚀情况，分别从腐蚀时间、腐蚀温度、不锈钢的合金成分、液态Pb-Bi合金中的溶解氧浓度及其流动速率等影响因素进行分析。同时归纳了其防护技术，包括对不锈钢的表面处理与改性，精确控制液态合金中的溶解氧浓度等。最后展望了未来液态金属腐蚀的研究重点及其防护涂层的制备关键。

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.