2021 Annual Meeting

Presentation information

Oral presentation

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

[1K05-07] Corrosion in Water Coolant

Wed. Mar 17, 2021 11:10 AM - 12:00 PM Room K (Zoom room 11)

Chair: Hirokazu Ohta (CRIEPI)

11:10 AM - 11:25 AM

[1K05] Influences of dissolved hydrogen and temperature on oxide film thickness of TT690 alloy in simulated PWR primary water condition

*Takahiro Sasaoka1, Takumi Terachi2, Takuyou Yamada1, Koji Arioka1 (1. INSS, 2. KEPCO)

Keywords:Pressurized Water Reactor Primary Water, TT690 Alloy, Dissolved Hydrogen, Oxide Film Thickness

PWR一次系を模擬した水環境下においてTT690合金の皮膜厚さの溶存水素濃度依存性に対する温度の影響を調べた結果、340℃以下では内層皮膜厚さに及ぼす影響は小さいことがわかった。