2017 Annual Meeting

Presentation information

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.)

3:15 PM - 3:30 PM

[3J12] Effects of 140 MeV C4+ irradiation on microstructure and mechanical properties in Zr-1.8Nb alloys

*Huilong Yang1, Sho Kano1, Zhengang Duan3, Yoshitaka Matsukawa2, Kenta Murakami1, Hiroaki Abe1 (1. Graduate School of Engineering, The University of Tokyo, 2. Institute for Materials Research, Tohoku University, 3. Graduate School of Engineering, Tohoku University)

Keywords:Nuclear fuel cladding saterials, Zr-based alloy, Irradiation strengthening, Microstructure, Mechanical property

It is well known that irradiation hardening and resultant embrittlement is considered as one of the main performance degradation in Zr-based fuel cladding tubes. Therefore, the tensile specimens (Zr-1.8Nb, wt.%) with spatially-uniform irradiation damage were prepared by the irradiation of 140 MeV C4+ in the present study, and the irradiation effects on the microstructural and mechanical changes in Zr-Nb alloys were investigated.