CORROSION OF FERRITIC-MARTENSITIC STEELS IN STEAM COMPARED TO SUPERCRITICAL WATER

摘要

The Supercritical Water Reactor is one of the six Generation IV nuclear power plant designs and was envisioned for its high thermal efficiency and simplified core[1]. This reactor is designed to function at high outlet temperature (between 500℃ and 600℃), which requires cladding and structural materials with good corrosion resistance. Because of their radiation and stress corrosion cracking resistance, ferritic-martensitic steels, such as HCM12A and NF616, are candidates for this reactor[2]. These alloys were corroded in both supercritical water and steam at 500℃. Steam corrosion was undertaken to obtain a more detailed kinetic behavior of the alloys since in previous studies on zirconium, the corrosion rates found using steam and supercritical water were similar[3].