Transformation of amorphous passive oxide film on Zr65Cu17.5Ni10Al7.5 metallic glass ribbons
Research output: Contribution to journal › Article › Research › peer-review
Standard
In: Journal of alloys and compounds, Vol. 929.2022, No. 25 December, 167265, 25.12.2022.
Research output: Contribution to journal › Article › Research › peer-review
Harvard
APA
Vancouver
Author
Bibtex - Download
}
RIS (suitable for import to EndNote) - Download
TY - JOUR
T1 - Transformation of amorphous passive oxide film on Zr65Cu17.5Ni10Al7.5 metallic glass ribbons
AU - Sarac, Baran
AU - Kvaratskheliya, Askar
AU - Zadorozhnyy, Vladislav
AU - Ivanov, Yurii P.
AU - Klyamkin, Semen
AU - Xi, Lixia
AU - Berdonosova, Elena
AU - Kaloshkin, Sergey
AU - Zadorozhnyy, Mikhail
AU - Eckert, Jürgen
N1 - Publisher Copyright: © 2022 Elsevier B.V.
PY - 2022/12/25
Y1 - 2022/12/25
N2 - Zr-based metallic glass with favorable properties and a stable surface oxide layer is foreseen as an alternative material for water/nuclear reactor pressure systems. The high stability of Zr65Cu17.5Ni10Al7.5 metallic glass (MG) in anodic and cathodic regions within 0.5 M H2SO4 solution is evidenced by the negligible shift in the corrosion potential upon linear sweep voltammetry cycles. The recorded passivation current density of 15 mA cm–2 is very similar to 430 stainless steel. The formation of an amorphous Zr-rich oxide phase and slight dissolution of the native ZrO2 layer are confirmed by scanning transmission electron microscopy – energy dispersive X-ray analysis, which result from the interaction of hydronium ions (H3O+) with the oxide layer during linear polarization. Furthermore, promising hydrogen absorption of the produced Zr-based MG ribbons (1.33 %wt, non-reversible) by Sieverts-type apparatus were recorded at 400 °C and under 6 MPa, which evidences that this alloy can minimize the hydrogen evolution within the chamber due to the coverage with an oxide film and thereby prevent accidents.
AB - Zr-based metallic glass with favorable properties and a stable surface oxide layer is foreseen as an alternative material for water/nuclear reactor pressure systems. The high stability of Zr65Cu17.5Ni10Al7.5 metallic glass (MG) in anodic and cathodic regions within 0.5 M H2SO4 solution is evidenced by the negligible shift in the corrosion potential upon linear sweep voltammetry cycles. The recorded passivation current density of 15 mA cm–2 is very similar to 430 stainless steel. The formation of an amorphous Zr-rich oxide phase and slight dissolution of the native ZrO2 layer are confirmed by scanning transmission electron microscopy – energy dispersive X-ray analysis, which result from the interaction of hydronium ions (H3O+) with the oxide layer during linear polarization. Furthermore, promising hydrogen absorption of the produced Zr-based MG ribbons (1.33 %wt, non-reversible) by Sieverts-type apparatus were recorded at 400 °C and under 6 MPa, which evidences that this alloy can minimize the hydrogen evolution within the chamber due to the coverage with an oxide film and thereby prevent accidents.
KW - Electron microscopy
KW - Fuel cladding
KW - Gas-solid reactions
KW - Metallic glass
KW - Passivation
KW - Zirconium oxide
UR - http://www.scopus.com/inward/record.url?scp=85139028622&partnerID=8YFLogxK
U2 - 10.1016/j.jallcom.2022.167265
DO - 10.1016/j.jallcom.2022.167265
M3 - Article
AN - SCOPUS:85139028622
VL - 929.2022
JO - Journal of alloys and compounds
JF - Journal of alloys and compounds
SN - 0925-8388
IS - 25 December
M1 - 167265
ER -