2017 Annual Meeting

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Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 403-1 Reactor Chemistry, Radiation Chemistry, Corrosion, Water Chemistry,Water Quality Control

[2I01-04] Mitigation of corrosive environment/Dose rate reduction

Tue. Mar 28, 2017 9:30 AM - 10:35 AM Room I (16-304 Building No.16)

Chair: Yusa Muroya (Osaka Univ.)

9:45 AM - 10:00 AM

[2I02] Mechanistic study for PWSCC in Alloy 690

Deformation of Alloy 690 in High Temperature Hydrogen Gas

*Takumi Terachi1, Nobuo Totsuka1, Takuyo Yamada1, Koji Arioka1 (1. Institute of Nuclear Safety System, Incorporated)

Keywords:Alloy 690, PWSCC, Hydrogen gas, HELP

690合金のPWSCC機構研究として、PWR1次系相当の水素ガスが材料の変形に及ぼす影響を検討した。320℃の高温アルゴンガス条件からPWR相当の水素分圧条件に環境を変えた時、0.5TCT試験片のき裂先端周辺で大きな変形が生じた。