铅铋共晶(LBE)作为一种潜在核冷却剂材料，是铅冷快堆(LFR)和加速器次临界驱动(ADS)系统的候选冷却剂材料之一。LBE对不锈钢结构材料具有严重的侵蚀性，会导致不锈钢结构材料的性能恶化，在不锈钢结构材料表面制备耐腐蚀涂层是提高反应堆结构材料耐腐蚀能力的有效方式之一。首先，系统总结了FeCrAl基涂层、高熵合金涂层、陶瓷涂层和ODS型合金涂层等多种耐LBE腐蚀涂层的制备策略，包括磁控溅射技术、热喷涂技术、脉冲激光沉积技术等，对多种耐LBE腐蚀涂层沉积策略的优缺点进行了比较。其次，总结对比了多种耐LBE腐蚀涂层在不同腐蚀环境下的性能，依靠FeCrAl基制备的合金涂层具有良好的耐LBE腐蚀性能，如添加一定量的Ti、Si元素;高熵合金涂层具有与大块高熵合金相似的优异性能，但是各种元素之间可能存在复杂的交叉影响;陶瓷涂层具有优异的力学性能和耐腐蚀性，包括单涂层和复合陶瓷涂层;ODS型合金涂层是一种添加弥散氧化物颗粒的强化相涂层，少量Y2O3的加入能够显著提高结构材料的综合性能。相对于裸露基材，涂层材料在一定程度上为基材提供了良好的抗腐蚀和磨损保护，同时具有优异的耐辐照能力。最后对耐LBE腐蚀涂层的发展前景进行了展望，以推动铅基快堆用不锈钢结构材料的进一步发展。

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.