[3A01-05] Fuel Cladding Materials 1

[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.