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.)

10:00 AM - 10:15 AM

[3A03] Development of Cr-coated Zircaloy for Accident Tolerant Fuels

(3) In-situ measurement for deformation of Cr/Zry double layered material

*Koichi Ogata1, Yasunari Shinohara1, Bo Li2, Sho Kano2, Hiroaki Abe2 (1. NDC, 2. UTokyo)

Keywords:Accident Tolerant Fuel, Cr-coated Zirconium Alloy, In-situ Observation, Acoustic Emission

This is 3rd presentation of a series of nuclear system research and development projects "Development of Cr-coated Zircaloy for Accident Tolerant Fuels."
To study the fracture behavior of Cr layer of Cr/Zry double layered material, we performed in-situ measurement during mechanical test using Cr/Zry double layered material. The experimental method and results of the test will be reported in this presentation.

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