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.)

3:30 PM - 3:45 PM

[3C13] Corrosion Behavior of Ion-irradiated Zirconium Alloy

*KATSUHITO TAKAHASHI1, Yasuhisa Aono1, Takashi Mutaguchi2, Shyun Simabukuro2, Hideo Watanabe2 (1. Hitachi, 2. Kyushu Univ.)

Keywords:Zirconium alloy, Corrosion, Hydrogen pick-up, Irradiation damage

沸騰水型軽水炉(BWR)に用いられるジルコニウム合金の,通常運転時の腐食・水素吸収に及ぼす照射損傷の影響を検討するため,ジルコニウム合金としてジルカロイ2に重イオンを照射してはじき出し損傷を付与した後,BWR水質を模擬した高温高圧水に浸漬し,腐食挙動に及ぼす照射損傷の影響を評価した。

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