2023 Fall Meeting

Presentation information

Oral presentation

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

[3A01-05] Fuel Cladding Materials 1

Fri. Sep 8, 2023 9:30 AM - 10:55 AM Room A (IB Bildg.1F IB013)

Chair:Yoshitaka Matsukawa(Kumamoto Univ.)

9:45 AM - 10:00 AM

[3A02] Development of Cr-coated Zircaloy for Accident Tolerant Fuels

(2) Mechanical property evaluations of Cr/Zircaloy bonding materials

*ZIQI WEI1, Neli Nikolova1, Bo Li1, Lijuan Cui1, Kejian Wei1, Sho Kano1, Hiroaki Abe1 (1. the University of Tokyo)

Keywords:Accident Tolerant Fuels, Cr/Zircaloy joint, Mechanicl behavior, Finite element method

This presentation is the second in a series of presentations on “Development of Cr-coated Zircaloy for Accident Tolerant Fuels.” The purpose is to investigate the mechanical behavior of Cr-Zircaloy bonded materials under tensile stress, primarily targeting the properties of the Cr/Zry interface. Our findings indicate that the Cr/Zircaloy bonded at 1073 K demonstrates superior interfacial strength compared to those bonded at 1273 K, which is attributed to the fewer formation of intermetallic compounds and interfacial defects during the low-temperature bonding process.

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