2018 Annual Meeting

Presentation information

Print

Oral presentation

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

[1D01-04] Zirconium Alloys

Mon. Mar 26, 2018 10:00 AM - 11:00 AM Room D (R1-212 -R1 Building)

Chair: Kan Sakamoto (NFD)

10:00 AM - 10:15 AM

[1D01] A Comparative Study of Deformation Behavior of Zr-1.8Nb Cladding Tube Under Axial and Hoop Stress

*Zishou Zhao1, Zhengang Duan2, Jingjie Shen1, John Patrick McGgrady1, Huilong Yang1, Sho Kano1, Hiroaki Abe1 (1. The University of Tokyo, Graduate School of Engineering, 2. Tohoku University, Graduate School of Engineering)

Keywords:Anisotropy, Deformation, Texture, Microstructure, Twinning, EBSD

The uniaxial tension (UT) tests and advanced expansion due to compression (A-EDC) test have been applied to examine the deformation behavior of Zr-1.8Nb cladding tubes, respectively. The differences of mechanical properties and microstructure evolution between UT test and A-EDC test have been compared and discussed.