Corrosion behavior of Cr-coated zirconium alloy cladding in LiOH/H3BO3-containing water at 360 ℃
Source abstract
Abstract
The corrosion behaviors of Cr-coated zirconium alloy (Zr-0.9 Nb) tube were investigated in 70 ppm Li and 3.5 ppm Li+ 1000 ppm B aqueous solutions at 360 °C/18.6 MPa by static autoclave tests, respectively. Results show that Cr coating improves the corrosion resistance of Zr-0.9 Nb under LiOH and Li+B conditions. The corrosion products of Cr coating were Cr 2O 3 and Cr(OH) 3, while the Cr 2O 3 was more easily transformed into Cr(OH) 3 under LiOH conditions. Some of the Cr(OH) 3 dissolved in the late stage of corrosion, resulting in the thinning of the oxide film.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
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