2018 Annual Meeting

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Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 402-1 Nuclear Materials and the Irradiation Behavior

[1D05-08] Corrosion

Mon. Mar 26, 2018 11:00 AM - 12:00 PM Room D (R1-212 -R1 Building)

Chair: Yoshiyuki Kaji (JAEA)

11:00 AM - 11:15 AM

[1D05] SCC growth behavior of SUS630 in high temperature water

(1)Effect of precipitation hardening heat treatment, thermal aging and test temperature

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

Keywords:SUS630, 17-4 PH stainless steel, SCC growth behavior in high temperature water, Thermal aging, Precipitation hardening heat treatment

SCC growth behavior of SUS630 (17-4 PH stainless steel) in high temperature (250℃-320℃) water was investigated. SCC growth rate was increased with test temperature increasing. SUS630 was hardend with precipitaion hardening heat treatment and thermal aging. SCC growth rate was increased with with hardness increasing.