2017 Annual Meeting

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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.)

3:00 PM - 3:15 PM

[3J11] Effects of thermo-mechanical history on the composition of bcc precipitates in Zr-2.5Nb alloys

*Ippei Ohkuma1, Yoshitaka Matsukawa1, Hiroaki Muta2, Huilong Yang3, Takeshi Toyama1, Shinsuke Yamanaka2, Yuhki Satoh1, Hiroaki Abe3 (1. Tohoku University, 2. Osaka University, 3. The University of Tokyo)

Keywords:fuel cladding, precipitates

Zr-Nb合金の析出物の組成は、熱加工履歴によって大きく変化する。モデル合金を使った系統的調査の結果について報告する。