抄録
Supercritical water-cooled reactor (SCWR) is one of the advanced reactor concepts for generation IV nuclear reactors. Material of fuel cladding for SCWR is required long term integrity and durability at metal temperature of 700℃. Then, 15Cr-20Ni austenitic stainless steel (1520S) which has sufficient creep strength at 700℃ was proposed for the candidate materials for fuel cladding of SCWR. In this study, oxidation behavior of 1520S as candidate materials, SUS316L and SUSS 1 OS as comparison materials in supercritical water at 700℃ and 650℃ under 24MPa for 1500h were discussed in terms of: temperature, cold work (CW) and surface finish. The main objective of this work is to predict the oxide behavior of candidate materials after 50,000h which is the estimated maximum operating time of fuel cladding.
