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.

Abstract password authentication.
Password is required to view the abstract. Please enter a password to authenticate.

Password