Corrosion issues in lead-cooled fast reactor (LFR) and accelerator driven systems (ADS)

Wetting Behavior of LBE on Corroded Candidate LFR Structural Materials of 316L, T91 and CLAM

“…In LBE with low oxygen concentration, dissolution corrosion is the main corrosion mechanism. This effect, on one hand, dissolves the material matrix, on the other hand, within a certain temperature range, it will cause lead-bismuth atoms to infiltrate the alloy along dislocations or grain boundaries and sub-grain boundaries, resulting in a sharp drop in the plasticity of the material [ 27 , 32 , 33 ]. In LBE with a high oxygen concentration, oxidation corrosion plays a dominant role.…”

Environmental degradation of structural materials in liquid lead- and lead-bismuth eutectic-cooled reactors

“…A major challenge in the deployment of these nuclear systems is that the principal candidate structural materials, including ferritic/martensitic (F/M) steels and austenitic stainless Table 1.1 Basic characteristics of select reactor coolants [28]. steels (AuSS), are not fully compatible with liquid Pb and/or LBE coolants [29][30][31][32][33][34][35][36], showing severe performance degradation due to LMC and/or LME (Fig. 1.2).…”

Evaluation of Power Fluidic Pumping Technology for Molten Salt Reactor Applications

“…Caustic soda was extensively evaluated as a reactor coolant, moderator, and fuel carrier as early as the late 1940s [42], with efforts extending into the 1960s [43]. Lead-cooled reactors are another Generation IV reactor concept, with high-temperature corrosion being a primary issue that has yet to be fully resolved [44].…”