Development of Cr-Coated Zircaloy for Accident Tolerant Fuels

Lijuan Cui

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)

10:45 AM - 11:00 AM

[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)

Keywords: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.