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)

11:00 AM - 11:15 AM

[3E06] Development of Cr-Coated Zircaloy for Accident Tolerant Fuels

(6) Effects of hydrogen on hoop properties in Zircaloy cladding using Advanced Expansion Due to Compression method

*Neli Sashkova Nikolova1, Huilong Yang1, Sho Kano1, Hiroaki Abe1 (1. University of Tokyo)

Keywords:Hydrogen effect, Hoop mechanical properties, Advanced expansion due to compression, Zircaloy-4

This is the sixth presentation in the series "Development of Cr-Coated Zircaloy for Accident Tolerant Fuels" of the Innovative Nuclear Research and Development Program. In order to confirm the mechanical integrity of the developed Cr-coated zircaloy cladding, as a preliminary study, in this report the results for the effects of hydrogen on the hoop-direction mechanical properties of the Zircaloy cladding, using the advanced expansion due to compression method (A-EDC), will be discussed.