日本金属学会2023年春期(第172回)講演大会

Presentation information

一般講演

10. Energy and Related Materials » Nuclear Materials

[G] Nuclear Materials

Thu. Mar 9, 2023 9:00 AM - 11:45 AM Rm. K (Rm.1311,1st Flr.,Buld.No.13)

座長:外山 健(東北大学)、藪内 聖皓(京都大学)

10:45 AM - 11:00 AM

[265] On the tensile behaviors of the Cr-Zircaloy bilayer fabricated by diffusion bonding

*Ziqi Wei1, Huilong Yang2, Bo Li1, Lijuan Cui1, Sho Kano1, Hiroaki Abe1 (1. Graduate School of Engineering, The University of Tokyo、2. School of Nuclear Science and Engineering, Shanghai Jiao Tong University)

Keywords:Cr-Zircaloy、tensile test、diffusion bonding、interfacial failure、FEM

RT and 573K-tensile tests are conducted on the diffusion-bonded Cr-Zry4 bilayer. The deformation and interfacial failure are analyzed from the perspective of microstructure and numerical simulation.

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