2023 Fall Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 503-1 Reactor Chemistry, Radiation Chemistry, Corrosion, Water Chemistry,Water Quality Control

[1A01-04] Radiolysis, Corrosion 1

Wed. Sep 6, 2023 2:45 PM - 3:50 PM Room A (IB Bildg.1F IB013)

Chair:Hiroshi Abe(Tohoku Univ.)

2:45 PM - 3:00 PM

[1A01] Direct experimental evidence of the reduction of Cr2O3 by Zr at high temperature

*Kejian Wei1, Lijuan Cui1, Bo Li1, Zongda Yang1, Sho Kano1, Hiroaki Abe1 (1. UTokyo)

Keywords:Accident tolerant fuel, Cr coating, Oxidation mechanism

Cr-coated Zr alloys are widely considered as one of the most promising candidates for the accident tolerant fuel (ATF). The key degradation process of the Cr coating is the reduction of Cr2O3 by Zr. However, there is still a lack of direct experimental evidence for this redox reaction. To analyze the reaction between the Cr2O3 and Zry4 alloy, they were first bonded under high temperature. After bonding, a new Cr-enriching layer adjacent to the Zry4 substrate was observed, which was thought to be the direct experimental evidence of the reduction of Cr2O3 by Zr. In accompany with this redox reaction, there are also another two important processes, ZrO2 transformed into α-Zr (O) and the inter diffusion of Cr/Zr happened. Therefore, the present results indicated that a Cr2O3 layer is not a sufficient barrier against the inter diffusion of Cr/Zr.

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