Defect‐fluorite Gd2Zr2O7 ceramics under helium irradiation: Amorphization, cell volume expansion, and multi‐stage bubble formation

Huang, Zhangyi; Ma, Ning; Qi, Jianqi; Guo, Xiaofeng; Yang, Ming‐Bo; Tang, Zhe; Zhang, Yutong; Han, Yong; Wu, Di; Lu, Tiecheng

doi:10.1111/jace.16364

Cited by 27 publications

(7 citation statements)

References 30 publications

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“…Interestingly, at a fluence of 5 × 10 17 ions/cm 2 bubble formation in Stage 4 was seen for the submicron sample (634 nm), while for the nanograined Gd 2 Zr 2 O 7 ceramic, such phenomenon was not observed (see Figure C). This probably suggests a delayed He bubble formation for nanograin Gd 2 Zr 2 O 7 ceramic, which has been proved in our previous study . Surface blisters as large as 60 nm are imaged for the submicron Gd 2 Zr 2 O 7 ceramic (see the AFM images in Figure ).…”

Section: Resultssupporting

confidence: 76%

“…This probably suggests a delayed He bubble formation for nanograin Gd 2 Zr 2 O 7 ceramic, which has been proved in our previous study. 40 Surface blisters as large as 60 nm are imaged for the submicron Gd 2 Zr 2 O 7 ceramic (see the AFM images in Figure 10). This indicates that the grain boundaries, instead of the inner grains, are the favorable nucleation sites for the formation of He bubbles, which prefer to align and distribute themselves along grain boundaries.…”

Section: F I G U R E 3 X-ray Penetration Of Gdmentioning

confidence: 99%

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He irradiation‐induced lattice distortion and surface blistering of Gd₂Zr₂O₇ defect‐fluorite ceramics

et al. 2020

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Gd2Zr2O7 ceramics with different grain sizes ranging from nanoscale to submicron scale (91, 204, and 634 nm) were irradiated at room temperature using 190 keV He ions with doses ranging from 5 × 1016 to 5 × 1017 ions/cm2. We fully characterized the pre‐ and post‐irradiation samples using grazing‐incidence X‐ray diffraction (GIXRD), scanning electron microscope (SEM), and atomic force microscope (AFM) as the grain size and degree of irradiation vary. The results suggested that all three Gd2Zr2O7 samples demonstrate outstanding radiation tolerance to displacement damage by retaining their crystallinity after irradiation at 5 × 1017 ions/cm2. which is equal to 16 displacement per atom (dpa) at peak positions. Although lattice expansion was observed at a He irradiation at 5 × 1016 ions/cm2 and beyond, the lattice remained stable for the nanograin ceramic, while the degree of distortion for the sample with the largest grain size (634 nm) continuously increased. Moreover, a delayed He bubble evolution process was seen for the nanograin ceramic, which did not appear for the submicron‐grained sample. Interestingly, the grain size‐dependent surface blistering was also found to be a function of ion fluence. After He irradiation at 5 × 1017 ions/cm2 the AFM root‐mean‐square(RMS) roughness variation for Gd2Zr2O7 ceramics of 91, 204, and 634 nm were 4.8, 7.0, and 11.1 nm, respectively.

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Section: Resultssupporting

confidence: 76%

Section: F I G U R E 3 X-ray Penetration Of Gdmentioning

confidence: 99%

He irradiation‐induced lattice distortion and surface blistering of Gd₂Zr₂O₇ defect‐fluorite ceramics

et al. 2020

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“…The grain boundary plays a significant role in shrinking the radiation-induced defects, and inhibiting the multi-stage He bubble formation process in Gd 2 Zr 2 O 7 nanograin ceramics. [80] When irradiated by 190 keV He ion beam up to a fluence of 5 × 10 17 ions/cm 2 , the average grain size of Gd 2 Zr 2 O 7 ceramics changes from 55 to 221 nm, the degree of post irradiation cell volume expansion increases from 0.56% to 1.02%, and the amorphization fraction increases from 6.8% to 11.1%. The further experiments indicate that Gd 2 Zr 2 O 7 samples with different grain sizes of 91, 204, and 634 nm all demonstrate outstanding radiation tolerance to displacement damage by retaining their crystallinity after irradiation at 5 × 10 17 ions/cm 2 , equally to 16 dpa at peak positions.…”

Section: Nanocrystalline Ceramics Materialsmentioning

confidence: 99%

Recent Progress on Interfaces in Nanomaterials for Nuclear Radiation Resistance

Jiang

et al. 2022

ChemNanoMat

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Interfaces including grain boundaries and heterophase interfaces could withstand the radiation damage via providing sites for trapping the defects. With the urgent demand for high radiation-tolerance nanostructured materials, exploration of the structural properties, especially the role of the interfaces on the radiation response in the nanomaterials, is of significant essentialness in developing the design of new radiation-resistant materials. Herein, the recent progress and development of two main kinds of interfaces, namely the grain boundaries in nanocrystalline and the hetero-phase interfaces in nanolayered materials and nano-composites, in nanostructured materials that are designed for radiation tolerance are summarized. In addition, the radiation response and resistant mechanism under irradiation conditions of the nanocrystalline materials like metals, single-phase alloys, and ceramics, as well as the nanocomposites like nanolayered metals, nanolayered ceramics, metal-carbon nanocomposite, and nanoparticle dispersed steels, are reviewed. Finally, challenges and perspectives are proposed to offer advice for the development of radiation resistance nanomaterials.

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“…As a rule, gas swelling processes are long-term processes accompanied by a long-term accumulation of radiation damage or implanted helium, xenon, or krypton ions, followed by the formation and filling of cavities or pores, forming gas-filled bubbles [11][12][13]. With an increase in the concentration of gases in the bubbles, an increase in the internal pressure occurs, which in turn leads to expansion and an increase in the volume of the bubble; due to the achievement of critical pressure, their rupture occurs, accompanied by the destruction of the surface layer and the destruction of the material [14,15]. At the same time, in most cases, this problem is acute for materials in which helium accumulates, which have high mobility and the ability to agglomerate, as well as concentrate in a small surface layer (no more than 1-2 microns), can seriously disrupt the stability of the material, as well as to reduce its thermophysical parameters [16,17].…”

Section: Introductionmentioning

confidence: 99%

Study of Radiation-Induced Damage Processes in CeZrO4–YZrO3 Ceramics Caused by Helium Irradiation

et al. 2022

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Composite oxide ceramics CeZrO4–YZrO3 obtained by mechanochemical synthesis were chosen as objects of study. The most dangerous type of radiation defect in structural materials is associated with helium accumulation in the structure of the near-surface layer. This can lead to the destruction and swelling of the material, resulting in a decrease in its strength and thermal characteristics. During the studies, it was found that the most significant structural changes (deformation of the crystal lattice, the magnitude of microdistortions of the crystal lattice) are observed with irradiation fluence above 5×1016 ion/cm2, while the nature of the changes is exponential. X-ray diffraction analysis found that the nature of the crystal structure deformation has a pronounced type of stretching due to the accumulation of implanted helium and its subsequent agglomeration. A comparative analysis with data on microdistortions of the crystal lattice and the values of microhardness and softening of ZrO2 and CeO2 showed that two-phase ceramics of the cubic type CeZrO4-YZrO3 are more resistant to radiation-induced degradation than single-phase ZrO2 and CeO2. Results of strength and thermophysical characteristics showed that the presence of two phases increases resistance to destruction and disorder, leading to a decrease in strength and thermal conductivity.

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Defect‐fluorite Gd₂Zr₂O₇ ceramics under helium irradiation: Amorphization, cell volume expansion, and multi‐stage bubble formation

Cited by 27 publications

References 30 publications

He irradiation‐induced lattice distortion and surface blistering of Gd₂Zr₂O₇ defect‐fluorite ceramics

He irradiation‐induced lattice distortion and surface blistering of Gd₂Zr₂O₇ defect‐fluorite ceramics

Recent Progress on Interfaces in Nanomaterials for Nuclear Radiation Resistance

Study of Radiation-Induced Damage Processes in CeZrO4–YZrO3 Ceramics Caused by Helium Irradiation

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Defect‐fluorite Gd2Zr2O7 ceramics under helium irradiation: Amorphization, cell volume expansion, and multi‐stage bubble formation

Cited by 27 publications

References 30 publications

He irradiation‐induced lattice distortion and surface blistering of Gd2Zr2O7 defect‐fluorite ceramics

He irradiation‐induced lattice distortion and surface blistering of Gd2Zr2O7 defect‐fluorite ceramics

Recent Progress on Interfaces in Nanomaterials for Nuclear Radiation Resistance

Study of Radiation-Induced Damage Processes in CeZrO4–YZrO3 Ceramics Caused by Helium Irradiation

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Defect‐fluorite Gd₂Zr₂O₇ ceramics under helium irradiation: Amorphization, cell volume expansion, and multi‐stage bubble formation

He irradiation‐induced lattice distortion and surface blistering of Gd₂Zr₂O₇ defect‐fluorite ceramics

He irradiation‐induced lattice distortion and surface blistering of Gd₂Zr₂O₇ defect‐fluorite ceramics