Abstract
The final goal of this study is to clarify the enhancement of wall surface wettability of metal-material due to the Radiation Induced Surface Activation (RISA) in the basic design guidelines of the supercritical pressure water-cooled reactor (SCWR). Two specimens of the PNC1520 which is considered as a potential material of fuel-cladding tube of SCWR and SUS304 under high-temperature and high-pressure condition were used to measure the effect of surface wettability by γ-ray irradiation. Consequently, the RISA effect decreased when the specimen temperature over 250oC. Due to RISA enhancement, the surface wettability on the oxidized specimen was significantly improved rather than on the non-oxidized specimen.