日本金属学会2024年春期(第174回)講演大会

Presentation information

一般講演

10. Energy and Related Materials » Nuclear Materials

[G] Nuclear Materials

Thu. Mar 14, 2024 9:00 AM - 12:15 PM Rm.I (Rm.603, 6th Flr.,Lecture Hall Blg.)

座長:阿部 陽介(原子力機構)、福元 謙一(福井大学)

9:30 AM - 9:45 AM

[213] Effect of Defect Distribution Gradient on Nano-oxide Behavior in 12Cr-ODS Steels Irradiated with 2.8 MeV Fe2+ Ions

*Zideng WANG1, Jingjie Shen2, Huilong Yang3, Sho Kano1, Hiroaki Abe1 (1. The University of Tokyo, 2. National Institute for Fusion Science, 3. Shanghai Jiaotong University)

Keywords:nano oxide、sink strength、diffusion、ion irradiation

This study examines 12Cr-ODS steels irradiated with 2.8 MeV Fe2+ ions, finding that defect gradients lead to varied dislocation loop sizes and nano-oxide behavior.

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