2022 Fall Meeting

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)

11:15 AM - 11:30 AM

[3E07] Development of Cr-Coated Zircaloy for Accident Tolerant Fuels

(7) Experiment of in-situ observation for mechanical test of Cr/Zry double layered material

*Koichi Ogata1, Yasunari Shinohara1, Huilong Yang2, Sho Kano2, Hiroaki Abe2 (1. NDC, 2. UTokyo)

Keywords:ATF, Cr-coated Zry, In-situ Observation, Acoustic Emission

This is 7th presentation of a series of nuclear system research and development projects "Development of Cr-coated Zircaloy for Accident Tolerant Fuels."
To study Cr-coated zircaloy cladding mechanical properties that relates to its soundness, we prepared Cr/Zry double layered material samples, and performed three-point bending test applying in-situ observation and acoustic emission technics using these samples. the results of the test will be reported.