2023 Fall Meeting

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.

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