2019 Annual Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 502-1 Nuclear Materials, Degradation, Radiation Effects, and Related Technology

[1M04-05] SCC

Wed. Mar 20, 2019 10:50 AM - 11:25 AM Room M (Common Education Bildg. 2 3F No.37)

Chair:Yoshiyuki Kaji(JAEA)

11:05 AM - 11:20 AM

[1M05] The effect of long term thermal aging on SCC growth behavior of SUS630 in high temperature water

Study of hardness and microstructural changes with aging

*Takuyo Yamada1, Takumi Terachi1, Makie Okamoto1, Koji Arioka1 (1. Institute of nuclear safety system, inc.)

Keywords:SUS630, 17-4PH stainless steel, Stress corrosion cracking in high temperature water, Thermal aging, Precipitation hadening heat treatment

The effect of thermal aging on SCC growth behavior of SUS630 in high temperature water were investigated. After thermal aging at 350 and 400°C for up to 10,000h of H1100 and H1150, the SCC growth rate and the hardness increased with aging. Spinodal decomposition, G phase and Cu-rich phase were observed in the aged materials.