2017 Annual Meeting

Presentation information

Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 402-1 Nuclear Materials and the Irradiation Behavior

[3J10-15] Zirconium Alloys

Wed. Mar 29, 2017 2:45 PM - 4:15 PM Room J (16-305 Building No.16)

Chair: Naoko Oono (Hokkaido Univ.)

2:45 PM - 3:00 PM

[3J10] Oxidation process of Nb precipitates in the surface oxide layer of J-AlloyTM subjected to corrosion in PWR-simulated water

*Yoshitaka Matsukawa1, Shuhei Kitayama1, Kenta Murakami2, Yasunari Shinohara3, Kenta Yoshida1, Huilong Yang2, Takeshi Toyama1, Hiroaki Muta4, Shinsuke Yamanaka4, Hiroaki Abe2 (1. Tohoku University, Institute for Materials Research, 2. The University of Tokyo, 3. NDS, 4. Osaka University)

Keywords:corrosion, fuel cladding, precipitates

PWR模擬水中で腐食させたJ合金の酸化被膜におけるNb析出物をSTEM-EDS/EELSで解析した結果について報告する。