Development of Cr-Coated Zircaloy for Accident Tolerant Fuels

Bo LI

Presentation information

Oral presentation

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

[3E01-08] Accident Tolerant Fuel

Fri. Sep 9, 2022 9:45 AM - 11:55 AM Room E (E1 Bildg.2F No.24)

Chair:Kinya Nakamura(CRIEPI)

10:15 AM - 10:30 AM

[3E03] Development of Cr-Coated Zircaloy for Accident Tolerant Fuels

(3) Cr/Zry interface by diffusion bonding

*Bo LI¹, Huilong YANG¹, Reuben Holmes¹, Lijuan CUI¹, Sho KANO¹, Hiroaki ABE¹ (1. UTokyo)

Keywords:accident tolerant fuel , diffusion bonding, microstructure, interface

This report is the third project in the "Development of Cr-Coated Zircaloy for Accident Tolerant Fuels". The interface between Cr and zirconium alloy was prepared by the diffusion bonding method, and the microstructure of the interface was evaluated.