2021 Fall Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 502-1 Nuclear Materials, Degradation, Radiation Effects, and Related Technology

[3D13-16] Zircalloy

Fri. Sep 10, 2021 4:00 PM - 5:15 PM Room D

chair: Ken-Ichi Fukumoto (Univ. of Fukui)

4:15 PM - 4:30 PM

[3D14] High Temperature Hoop Deformation of Zircaloy- 4 Nuclear Fuel Cladding using Advanced Expansion due to Compression Test

*Neli Sashkova Nikolova1, Huilong Yang1, Sho Kano1, Hiroaki Abe1 (1. UTokyo)

Keywords:High temperature, Hoop mechanical properties, Advanced Expansion due to Compression, Zircaloy 4

The acquisition of hoop direction tensile properties is necassery for textured materials such as Zircaloy-4 nuclear fuel cladding tube. The purpose of this study is to evaluate the deformation in the hoop direction at high temperature of Zircaloy-4 using a newly developed Advanced Expansion due to Compression (A-EDC) test.
In this work Zirclaoy 4 cladding tubes were tested at temperature ranging from room temperature up to 773K. The stress-strain curves in hoop direction were derived and the effect of temperature on the tensile hoop properties was further investigated.