2024 Annual Meeting

Presentation information

Oral presentation

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

[3C10-13] Corrosion

Thu. Mar 28, 2024 2:45 PM - 3:55 PM Room C (21Bildg.2F 21-205)

Chair:Kazunori Morishita(Kyoto Univ.)

3:15 PM - 3:30 PM

[3C12] SCC initiation behavior of Alloy 600 in simulated PWR primary water using blunt notch CT specimen

*Takuyo Yamada1, Takumi Terachi1, Yuuki Yamaoka1, Koji Arioka1 (1. INSS)

Keywords:Alloy 600, Simulated PWR primary water, SCC initiation behavior, Temperature dependence

Blunt notch CT test of 20%CW alloy 600 MA was performed in a simulated PWR primary water environment from 290 to 360°C. Temperature dependence of SCC initiation was evaluated from this method. And SCC initiation process was investigated using microscopic observations.