日本金属学会2024年春期(第174回)講演大会

Presentation information

一般講演

10. Energy and Related Materials » Nuclear Materials

[G] Nuclear Materials

Thu. Mar 14, 2024 9:00 AM - 12:15 PM Rm.I (Rm.603, 6th Flr.,Lecture Hall Blg.)

座長:阿部 陽介(原子力機構)、福元 謙一(福井大学)

11:30 AM - 11:45 AM

[220] Investigation of Hoop Tensile Behavior in Chromium-Coated Zircaloy for Accident Tolerant Fuel Cladding Materials

*Ziqi WEI1, Bo LI1, Lijuan CUI2, Zongda YANG1, Kejian WEI1, Sho KANO1, Hiroaki Abe1 (1. The University of Tokyo, 2. Sichuan University (China))

Keywords:Accident Tolerant Fuel (ATF)、Cr coating、Hoop mechanical behaviors、Pulsed laser deposition

This study focused on a preliminary evaluation of the mechanical behaviors of Cr-coated Zircaloy-4 cladding tubes under hoop tensile stress using the Advanced Expansion-Due-to- Compression test.

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