4.7 Article

The correlation between tetragonal phase and the undulated metal/oxide interface in the oxide films of zirconium alloys

Journal

JOURNAL OF NUCLEAR MATERIALS
Volume 524, Issue -, Pages 101-110

Publisher

ELSEVIER
DOI: 10.1016/j.jnucmat.2019.06.039

Keywords

Zirconium alloy; Transition mechanism; Undulated metal/oxide interface; Tetragonal zirconia; Raman

Funding

  1. Major Project of China National Nuclear Corporation [[2016] 298]

Ask authors/readers for more resources

The transition mechanism is of significance to the corrosion behavior of zirconium alloys. Two important phenomena may be the causes of transition, which are the undulated wavy interface and the existence of tetragonal zirconia at the metal/oxide interface. There is little detailed study on the correlation between these two features. Micro-scale Raman imaging of intensity and Raman shifts was conducted in this study to further evaluate the connection. It was studied based on the oxide films formed on Zr-0.5Sn-0.15Nb-0.5Fe-0.2 V and N36 claddings corroded in 500 degrees C/10.3 MPa steam. The stress in interfacial tetragonal zirconia has relationship with the amplitude to wavelength ratio of the undulated part and it is always found to be larger at the convex parts of interface. These parts are prone to crack formation. At one convex position that the oxide cracked, t-ZrO2 is found to be preserved beneath and above the crack. Stress is also preserved, but partially released. When interfacial t-ZrO2 exists, the stress in the surrounding monoclinic phase is observed to be small. This provides us a more detailed figure of the stress distribution in oxide film. Tetragonal phase is mainly distributed near the metal/oxide interface. More intense tetragonal signals are frequently found at the convex positions of interface. This might result from large tetragonal grains or aggregation of small t-ZrO2 grains. These grains are stabilized at convex parts because of the large compressive stress and might be unstable once the grain size exceeds a critical value or once cracks are formed at such positions. An illustration of the connection between t-ZrO2 and undulated interface is then proposed. Possible reasons that facilitate the formation of lateral cracks and possible reasons for the existence of t-ZrO2 at the convex positions are discussed. (C) 2019 Elsevier B.V. All rights reserved.

Authors

I am an author on this paper
Click your name to claim this paper and add it to your profile.

Reviews

Primary Rating

4.7
Not enough ratings

Secondary Ratings

Novelty
-
Significance
-
Scientific rigor
-
Rate this paper

Recommended

Article Metallurgy & Metallurgical Engineering

Corrosion of New Zirconium Claddings in 500°C/10.3MPa Steam: Effects of Alloying and Metallography

Jing-Jing Liao, Zhong-Bo Yang, Shao-Yu Qiu, Qian Peng, Zheng-Cao Li, Ming-Sheng Zhou, Hong Liu

ACTA METALLURGICA SINICA-ENGLISH LETTERS (2019)

Article Materials Science, Multidisciplinary

Research on the existence and stability of interfacial tetragonal zirconia formed on zirconium alloys

Jingjing Liao, Fei Xu, Qian Peng, Zhongbo Yang, Zhengcao Li, Shaoyu Qiu

JOURNAL OF NUCLEAR MATERIALS (2020)

Article Materials Science, Multidisciplinary

Critical behavior of interfacial t-ZrO2 and other oxide features of zirconium alloy reaching critical transition condition

Jingjing Liao, Junsong Zhang, Wei Zhang, Fei Xu, Zhongbo Yang, Guang Ran, Qian Peng, Shaoyu Qiu

Summary: The transition of zirconium alloys during corrosion is inevitable as it accelerates degradation of corrosion property. Research suggests that during transition, t-ZrO2 transforms into m-ZrO2, accompanied by lateral cracks and interconnected pores.

JOURNAL OF NUCLEAR MATERIALS (2021)

Article Materials Science, Multidisciplinary

Improved corrosion resistance of reactive gas pulse sputtered (TiTaNbZrNi)N high entropy alloy coatings with a hybrid architecture of multilayered and compositionally graded structures

W. Zhang, J. J. Liao, Z. B. Yang, S. Y. Qiu, J. J. Yang, J. L. Liao, Y. Y. Yang, N. Liu

Summary: The (TiTaNbZrNi)N hybrid structure coatings prepared by reactive gas pulse sputtering technique exhibit excellent performance in high temperature water corrosion and oxidation resistance, with the oxygen diffusion depth being influenced by the thickness of the (TiTaNbZrNi)Nx sublayer and multilayer interface.

JOURNAL OF NUCLEAR MATERIALS (2021)

Article Materials Science, Multidisciplinary

Mechanisms investigation of cathodic-anodic coupling reaction of Zr-H2O at 360 °C by long-term in-situ electrochemical polarization analyses

Jingjing Liao, Wei Zhang, Junsong Zhang, Zhongbo Yang, Fei Xu, Qian Peng, Zhengcao Li, Shaoyu Qiu

Summary: Long-term online monitoring was conducted on two zirconium claddings during corrosion in 360°C water, revealing that the cathodic reaction is activation-controlled while the anodic reaction is diffusion-controlled. Recombination of hydrogen atoms becomes increasingly difficult with time, especially in one of the alloys, suggesting increased diffusion probability of hydrogen atoms into the zirconium matrix. The proposal is supported by experimental data.

CORROSION SCIENCE (2021)

Article Chemistry, Physical

High-temperature oxidation behavior of Zr-4 and Zr-Sn-Nb alloy in different oxidation ambient

Wanqian Zhao, Tianguo Wei, JingJing Liao, Pengcheng Song, Xiaoming Peng, Zhihai Liao

Summary: The study investigated the oxidation characteristics of Zr-4 and Zr-Sn-Nb alloys in different environments, revealing kinetic oxidation transitions at different temperatures and faster oxidation kinetics in air compared to steam and oxygen. The composition and structure of the oxide layers also vary depending on the environment.

JOURNAL OF ALLOYS AND COMPOUNDS (2021)

Article Materials Science, Multidisciplinary

Interface evolution and corrosion performance of (TiTaNbZrNi)N HEA coatings with a hybrid architecture under 6 MeV Au-ion irradiation

W. Zhang, R. R. Liu, J. J. Liao, Z. H. Liao, R. C. Liu, K. Shi, Z. B. Yang, S. Y. Qiu, J. J. Yang

Summary: The interface evolution and corrosion resistance of the (TiTaNbZrNi)N hybrid structure coating under irradiation were investigated. The (TiTaNbZrNi)Nx sublayer disappeared after irradiation, transforming the three-phase interface into a two-phase interface. The irradiated coating showed lower oxygen penetration depth and better corrosion resistance.

JOURNAL OF NUCLEAR MATERIALS (2022)

Article Materials Science, Multidisciplinary

Addition of niobium in Fe-13Cr-4.5Al-2Mo alloy used as ATF cladding: Effect on high temperature water corrosion and in-situ electrochemistry

Jingjing Liao, Hui Wang, Jun Wu, Wei Zhang, Fei Xu, Hongying Sun, Xuguang An, Shaoyu Qiu

Summary: The addition of Niobium in candidate accident tolerant fuel cladding FeCrAl alloy has been investigated in this study. The results showed that FeCrAl alloys have good corrosion resistance in high temperature water environments. The addition of a moderate amount of Nb improved the corrosion resistance, while a high Nb content may lead to porosity and iron depletion in the oxide film.

MATERIALS & DESIGN (2022)

Article Materials Science, Multidisciplinary

H dissolution and desorption near He-V complexes in W surfaces with different orientations

Liuming Wei, Jingwen Li, Yonggang Li, Qirong Zheng, Fan Cheng, Chuanguo Zhang, Jingyu Li, Gaofeng Zhao, Zhi Zeng

Summary: This study investigates the influence of He-V complexes on H behaviors on different W surfaces using DFT calculations. The results show that H dissolution is most difficult but H trapping is easiest on the W (110) surface, while the opposite is true on the W (111) surface. Moreover, the presence of He-V complexes increases the difficulty of H diffusion from bulk to surface and desorption.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Effect of deposition parameters on characteristics and oxidation behavior of magnetron sputtered Cr coatings

Yan Meng, Song Zeng, Chen Chen, Chaowen Zhu, Huahai Shen, Xiaosong Zhou, Xiaochun Han

Summary: The characteristics of magnetron sputtered Cr coatings vary with different temperature, bias voltage, and pressure. Coatings with random orientation, good crystallinity, and small grain size exhibit favorable oxidation behavior, while coatings with strong (200) texture, poor crystallinity, and large grains have many intrinsic defects that are detrimental to the protection property of the Cr coatings.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Automated analysis of grain morphology in TEM images using convolutional neural network with CHAC algorithm

Xinyuan Xu, Zefeng Yu, Wei-Ying Chen, Aiping Chen, Arthur Motta, Xing Wang

Summary: This study presents an automated approach for characterizing grain morphology in TEM images recorded during ion irradiation. By combining a machine learning model and a computer vision algorithm, comparable results to human analysis can be achieved with significantly reduced analysis time. Researchers can train their own models following the procedures described in this study to automate grain morphology analysis of their own TEM images.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Model development for oxidation and degradation behavior of accident tolerant Cr coating on Zr alloy cladding under high temperature steam atmosphere

Shihao Wu, Dong Wang, Yapei Zhang, Koji Okamoto, Marco Pellegrini, Wenxi Tian, Suizheng Qiu, G. H. Su

Summary: The oxidation and degradation mechanisms of Cr coating on Zr alloy cladding under high temperature steam atmosphere are summarized, and a mathematical analysis model is established to predict the changes in coating thickness. The model is applied in the analysis of structure evolution under different conditions.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Numerical and experimental development of cupronickel filler brazed joints for divertor and first wall components in DEMO fusion reactor

V. Diaz-Mena, J. de Prado, M. Roldan, I. Izaguirre, M. Sanchez, M. Rieth, A. Urena

Summary: The brazeability of a cupronickel alloy was evaluated as a filler alloy for high-temperature joining of tungsten to steel. The study investigated the brazing conditions and the impact of the selected filler on the joint quality using numerical software. The results showed different metallurgical interactions and diffusion phenomena between the filler alloy and the base materials at different temperatures. The study emphasized the importance of selecting a suitable filler to mitigate residual stresses in the joints.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Defect-specific strength factors and superposition model for predicting strengthening of ion irradiated Fe18Cr alloy

Pengcheng Zhu, Yajie Zhao, Yan-Ru Lin, Jean Henry, Steven J. Zinkle

Summary: This study investigates the effect of heavy-ion irradiation on radiation hardening in high-purity binary alloy Fe18Cr. Nanoindentation testing and high-quality TEM imaging were conducted to extract hardness and microstructure information. The strength factor was accurately calculated based on the detailed TEM characterization of irradiated microstructures, and a refined hardening superposition method was applied to quantify the mechanical properties of ion-irradiated materials.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Synthesis and characterization of sodium-aluminophosphate based glass-ceramics containing NZP phase for HLW immobilization

Bin Wu, Haixia Ning, Hanzhen Zhu, Jianjun Chen, Kang Wang, Daiyu Zhang, Fu Wang, Qilong Liao

Summary: This study discusses the effects of ZrO2 and B2O3 on the phase composition and properties of SAP-based glass-ceramics. The results show that ZrO2 addition improves the formation of NZP phase while restricting the crystallization of AlPO4 phases. The correct ratios of ZrO2 and B2O3 allow only the formation of NZP phase within the SAP glass.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

High temperature oxidation of cold spray Cr-coated accident tolerant zirconium-alloy cladding with Nb diffusion barrier layer

Hwasung Yeom, Greg Johnson, Benjamin Maier, Tyler Dabney, Kumar Sridharan

Summary: Cr-Nb bilayer coatings were developed using cold spray deposition to improve the limiting operational temperature of Cr-coated Zr-alloy system. The coatings exhibited outstanding oxidation resistance at high temperatures and formed continuous intermetallic compound layers at the interfaces.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Irradiation creep measurement and microstructural analysis of chromium nitride-coated zirconium alloy using pressurized tubes

Padhraic L. Mulligan, Andrew T. Nelson, Chad M. Parish, Patrick A. Champlin, Xiang Chen, Daniel Morrall, Jason M. Harp

Summary: Environmental barrier coatings are being developed to reduce oxidation and embrittlement in Zr-based materials. Chromium nitride is a candidate for this application, but understanding its impact on irradiation-induced creep and microstructure is critical.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Determination of impurity distribution in IG-11/110 nuclear graphite using TOF-SIMS

Dexuan Yan, Xinlei Cao, Ke Shen

Summary: This study investigated the purification mechanism of polycrystalline graphite by comparing IG-11 graphite with IG-110 nuclear grade graphite. The analysis revealed that metallic impurities in IG-11 were primarily segregated within graphite porosities, while IG-110 demonstrated a significant reduction in impurities. This research contributes to the development of innovative graphite purification techniques for greater purity and stronger oxidation resistance.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Study of multi-pebble oxidation process in high-temperature gas-cooled reactor

Wei Xu, Wei Peng, Lei Shi, Qi Sun

Summary: This paper investigates the oxidation and shape evolution of matrix graphite in high temperature gas-cooled reactors during air-ingress accidents. A reaction kinetics model is established and computational fluid dynamics with a dynamic mesh method is used to simulate the oxidation process. The results show that the geometric shape of graphite changes significantly with increasing flow rate, and the graphite pebbles tend to form a structure with a narrow front and wide tail.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Synthesis and characterization of super occluded LiCl-KCl in zeolite-4A as a chloride salt waste form intermediate

Allison Harward, Casey Elliott, Michael Shaltry, Krista Carlson, Tae-Sic Yoo, Guy Fredrickson, Michael Patterson, Michael F. Simpson

Summary: This paper investigates the hygroscopic properties of eutectic LiCl-KCl absorbed into zeolite-4A. The study finds that water absorption and corrosion worsen with increasing salt loading. It also suggests that the salt can be stored in a non-inert atmosphere for a certain period of time.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Hermeticity of SiC/SiC composite and monolithic SiC tubes irradiated under radial high-heat flux

Takaaki Koyanagi, Xunxiang Hu, Christian M. Petrie, Gyanender Singh, Caen Ang, Christian P. Deck, Weon-Ju Kim, Daejong Kim, James Braun, Yutai Katoh

Summary: This study provides critical experimental data on the effects of irradiation on the hermeticity of SiC composite cladding, finding that irradiation can cause a decrease in hermeticity and cracking, and coating the outer surface can mitigate the cracking issue.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Theoretical estimation of multiple hydrogen isotope content in metal layers slowly co-deposited from plasmas

S. Krat, A. Prishvitsyn, Yu. Gasparyan

Summary: This study proposes a probabilistic and diffusion-based model to describe the co-deposition of multiple hydrogen isotopes with slowly grown metal layers. The model calculates the relative concentrations of different hydrogen isotopes in the co-deposited metal layers. It is found that if hydrogen isotopes have different detrapping energies, only the isotope with the highest detrapping energy shows a monotonic decrease in concentration with deposition temperature. Furthermore, the study evaluates the uncertainty of tritium concentration in the co-deposited layer based on the uncertainty in detrapping energy of tritium and deuterium, predicting a >10% tritium concentration uncertainty for a 0.01 eV difference.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Computational study of thermophysical properties of cerium doped UO2: Effect of oxidation states

Tijo Vazhappilly, Arup Kumar Pathak

Summary: This study investigates the effect of Ce atom substitution in UO2 on its thermophysical properties using density functional theory. The results show that the Ce substitution levels and the oxidation state of Ce/U atoms strongly influence the band structure and specific heat capacity of the UO2 lattice. These findings provide important insights into the fuel properties of UO2 under reactor conditions.

JOURNAL OF NUCLEAR MATERIALS (2024)