Development of Cr-coated Zircaloy for Accident Tolerant Fuels

Hiroaki ABE

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.)

9:30 AM - 9:45 AM

[3A01] Development of Cr-coated Zircaloy for Accident Tolerant Fuels

(1) Synthesis of Cr/zircaloy interface and its microstructural analysis

*Hiroaki ABE¹, Bo LI¹, John Andrew Kane Jovellana¹, Lijuan Cui¹, Kejian Wei¹, Sho Kano¹ (1. The University of Tokyo)

Keywords:Accident Tolerant Fuels, Cr/zircaloy joint

This presentation is the first in a series of presentations on "Development of Cr-coated Zircaloy for Accident Tolerant Fuels". In addition to describing the overall picture of this project, we report on the synthesis of Cr/Zircaloy joint materials and the results of microstructural evaluation research.