[3E01-08] 事故耐性燃料

[3E05] Development of Cr-Coated Zircaloy for Accident Tolerant Fuels

(5) Irradiation damage in pure chromium

*Lijuan Cui¹, Yang Huilong¹, Kano Sho¹, Abe Hiroaki¹ (1. UTokyo)

キーワード：Accident tolerant fuel cladding, Dislocation loops, Irradiation damage, Chromium, Swelling

The current presentation is the fifth topic of subject "Development of Cr-Coated Zircaloy for Accident Tolerant Fuels". The talk will present the ion irradiation damage in pure chromium. The Burgers vector and nature of dislocation loops are quantified.