Steam oxidation behavior of ZrO2/Cr-coated pure zirconium prepared by plasma electrolytic oxidation followed by filtered cathodic vacuum arc deposition

X Wang, Y Liao, C Xu, H Guan, M Zhu, C Gao… - Journal of Alloys and …, 2021 - Elsevier
Plasma electrolytic oxidation (PEO) and filtered cathodic vacuum arc deposition (FCVAD)
techniques were employed to fabricate a ZrO 2/Cr composite coating on pure zirconium. The …

High temperature oxidation of CrAl-coated Zr–1 Nb alloy in 1000–1300° C steam

X Wang, Q Zhou, J Zhao, Y Liao, C Xu, X **… - Journal of Alloys and …, 2023 - Elsevier
The CrAl coating of 13 µm thick on Zr–1 Nb alloy prepared by filtered cathodic vacuum arc
deposition with Cr70Al30 target exhibited excellent steam oxidation resistance below 1200° …

Role of microchannels in breakaway oxidation of Zr alloy under high-temperature steam oxidation at 1000℃

Z Cui, J Liu, P Hu, J Qiu, S **e, R Meng, W Liu, J Lu… - Corrosion …, 2022 - Elsevier
In the present study, to determine the mechanism of the breakaway phenomenon, high-
temperature steam oxidation of zirconium alloys was carried out at 1000℃. Additionally, the …

High temperature oxidation of Zr1Nb alloy with plasma electrolytic oxidation coating in 900–1200° C steam environment

X Wang, K Wei, H Guan, C Xu, W Xue, Y Zhang… - Surface and Coatings …, 2021 - Elsevier
A continuous ceramic coating of 8 μm thick on Zr single bond 1Nb alloy was fabricated by
plasma electrolytic oxidation (PEO) in alkaline phosphate electrolyte. The high-temperature …

Understanding the oxidation resistance of zirconium alloy at 1000° C based on the formation of a Zr-Sn intermetallic phase and co-precipitation of Sn and Nb

Z Cui, J Liu, G Liu, G Tang, X Liu, R Meng… - Acta Materialia, 2024 - Elsevier
The oxidation behavior of zirconium alloy in high-temperature steam plays a dominant role
in the operation of nuclear reactors under accident conditions. The present work …

Understanding the high-temperature corrosion behavior of zirconium alloy as cladding tubes: a review

Y Tang, J Liao, D Yun - Frontiers in Materials, 2024 - frontiersin.org
Operated under extreme conditions, corrosion occurs between zirconium alloy cladding
tubes and the coolant in the primary loop of pressurized water reactors (PWRs), contributing …

Enhanced high-temperature oxidation resistance of a zirconium alloy cladding by high-temperature preformed oxide on the cladding

CM Lee, DS Sohn - Corrosion Science, 2018 - Elsevier
Using a zirconium alloy, pre-oxidation was conducted at 1200° C in a steam environment,
and the pre-oxidised specimens were oxidised at 1012, 1100, and 1200° C. The preformed …

Self-toughening mechanism of the ZrO2 scale and the precipitation of Sn during the steam oxidation of ZIRLO™ at 1200° C

J Liu, Y **e, Z Hao, Z Cui, R Meng, F Zhao, J Yang… - Acta Materialia, 2023 - Elsevier
The steam oxidation behavior of ZIRLO™ at 1200° C was investigated using a
thermogravimetric analyzer. The microstructure of the oxide was analyzed using SEM …

Development of oxidation model for zirconium alloy cladding and application in the analysis of cladding behavior under loss of coolant accident

D Wang, Y Zhang, S Wu, GH Su, S Qiu, W Tian… - Journal of Nuclear …, 2022 - Elsevier
Abstract During Loss of Coolant Accident (LOCA) in Pressurized Water Reactor (PWR), the
oxidation of zirconium alloy cladding has a significant impact on the core degradation …

Oxidation behavior and microstructural evolution of Zr-1.0 Nb-0.01 Cu during high-temperature transients

L Chen, B Luan, S Ma, P Wan, X Yang, H Zhou, G Bai… - Corrosion …, 2023 - Elsevier
To study the oxidation behavior and microstructural evolution of Zr-1.0 Nb-0.01 Cu claddings
during high-temperature transients simulating LOCA scenarios, samples were oxidized to …