IntroductionLead 17lithium (Pb–17Li), which contains 83 mol% lead (Pb)and 17 mol% lithium (Li), has been considered as one of the tri-tium breeding materials for the future fusion reactor besides liquidlithium since 1980s [1,2]. The obvious advantage is that Pb–17Liplays both of the roles of breeder and neutron multiplier in thereactor system. Moreover, it shows low chemical reactivity withwater and air in comparison with liquid lithium. However, one ofthe critical issues is the Pb–17Li shows bad compatibility with thestructural steels, e.g. reduced activation ferritic/martensitic steel(RAFM) [3]. The dissolution and penetration are the main mech-anisms of corrosion which happen at high temperature conditionwhen the structural materials contact with the molten Pb–17Li. The