Development of Cr-Coated Zircaloy for Accident Tolerant Fuels

Ying Chen

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)

10:00 AM - 10:15 AM

[3E02] Development of Cr-Coated Zircaloy for Accident Tolerant Fuels

(2) Alloy design based on first-principles

*Ying Chen¹, Davey Theresa¹, Jovellana John², Yang Huilong², Kano Sho², Abe Hiroaki² (1. Tohoku Univ., 2. UTokyo)

Keywords:Accident Tolerant Fuels , Alloy design, First-principles, Stability

This presentation is the 2nd report of the series of nuclear system research and development projects "Development of Cr-coated accident-resistant fuel". The basic consideration on selecting proper alloying elements to Cr based on the first-principles, as well as the priliminary results will be presented.