Development of Cr-coated Zircaloy for Accident Tolerant Fuels

Sho Kano

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.)

10:15 AM - 10:30 AM

[3A04] Development of Cr-coated Zircaloy for Accident Tolerant Fuels

(4) Microstructural evolutions of radiation damage in Cr and (Cr, Zr) Laves phase

*Sho Kano¹, Lijuan Cui¹, Kejian Wei¹, Hiroaki Abe¹ (1. UTokyo)

Keywords:Accident Tolerant Fuels, Cr-coated Zircaloy, Ion irradiation

This presentation is the 4th in a series of presentations on "Development of Cr-coated Zircaloy for Accident Tolerant Fuels". The ion irradiation effects on both the metallic Cr and the metal compound (Laves phase) which is formed at the interface between the Cr-layer and Zry-substrate will be reported in my talk.