JOURNAL OF LUMINESCENCE
·
2021
·
IF 3.599
Lei Yu,Kuibao Zhang,Weiwei Li,Baozhu Luo
In this study, Sm-doped Gd 2 Zr 2 O 7 transparent ceramics were successfully prepared by high temperature vacuum sintering using combustion synthesized nanopowders . X-ray diffraction, solid ultraviolet absorption spectrophotometer and fluorescence spectrometer were employed to investigate the structural evolution and photoluminescence properties of as-prepared samples. The Sm-doped Gd 2 Zr 2 O 7 nanopowders are in defective fluorite structure, which transforms into pyrochlore structure after high temperature sintering . The 3% Sm-doped sample exhibits high in-line transmittance of 74.7% at the wavelength of 1000 nm. The fluorescence lifetimes of all samples excited at 404 nm and detected at 615 nm are in millisecond scale, and the concentration quenching occurs when the Sm doping concentration reaches to 10%.
研究领域:
材料科学
·
光学
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产品关联
DOI
高影响因子
CERAMICS INTERNATIONAL
·
2018
·Vol. 44
·期 12
·14020-14025
·
IF 3.057
Xirui Lu,Xiaoyan Shu,Xudong Liu,Yi Xie,Lan Wang,Dadong Shao
Considering the urgent demand of nuclear waste disposal, a comprehensive study on the irradiation performance of nuclear waste forms is extremely necessary, especially on those containing multiple-nuclides with multiple-valence. The irradiation effects of Gd 2 Zr 2 O 7 pyrochlore bearing simulated trialkyl phosphine oxides (TRPO) waste (consisting of ZrO 2 , MoO 3 , RuO 2 and PdO) were studied in this work. Gd 10.685 Mo 4.734 Zr 28.924 Ru 1.000 Pd 1.745 O 91.825 and Gd 8.883 Mo 9.901 Zr 33.760 Ru 2.089 Pd 3.644 O 118.368 were irradiated by 1.5 MeV Xe 20+ to fluences from 1 × 10 12 to 1 × 10 15 ions/cm 2 at room temperature. The results showed an irradiation induced disordering with slight micro-swelling. In addition, the ion irradiation tolerance of the solid solutions decreased as the TRPO waste content increased. The decrease and shift of Raman peaks indicated the structural disordering and inner stress after irradiation. The micromorphology and element distribution of the irradiated surface remained almost unchanged. The structural evolution from pyrochlore to fluorite and even amorphous structure were disclosed in this study.
研究领域:
核材料科学
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辐射效应
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陶瓷固化体
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核废料固化
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DOI
高影响因子
JOURNAL OF ALLOYS AND COMPOUNDS
·
2019
·
IF 4.175
Jingxian Yang,Xiaoyan Shu,Fen Luo,Lan Wang,Yucheng Gu,Jianjun Wu,Xirui Lu
The disposal of strontium (Sr) from nuclear reactions has been a great challenge in the nuclear industry. Based on four kinds of occupation methods, a series of SrO-doped Gd 2 Zr 2 O 7 compositions with the general formula Gd 2-2 x /3 Sr x Zr 2 O 7 , Gd 2 Zr 2- x /2 Sr x O 7 , Gd 2- x Sr x Zr 2 O 7- x /2 and Gd 2 Zr 2- x Sr x O 7- x (0.0 ≤ x ≤ 2.0) were prepared by a high temperature sintering method solid state route. The influences of Sr substitution on the structure modifications, solid nuclear mobility, microstructure, and element distribution were studied. Our results show that the four sets of samples reach the maximum solid solubility within the range of x > 2.0, 1.5 < x ≤ 2.0, 1.0 < x ≤ 1.5, 1.0 < x ≤ 1.5, respectively. It was found out that the compound phase of SrZrO 3 and pyrochlore appeared in all the samples. In addition, the amount of the SrZrO 3 increases while the amount of the pyrochlore decrease and that of Sr 2+ increases.
研究领域:
材料科学
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核废料管理
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陶瓷
·
固态化学
✓ 已验证
DOI
高影响因子
CERAMICS INTERNATIONAL
·
2015
·
IF 2.605
Long Fan,Xiaoyan Shu,Xirui Lu,Yi Xie,Yi Ding,Tao Duan,Bingrong Dang,Yanlin Wu
The present work explores the potential of Gd 2 Zr 2 O 7 pyrochlore based materials for incorporation of trialkyl phosphine oxides (TRPO) waste which is a mixture of multi-nuclides with multi-valence. A series of (Gd,A) 2 (Zr,B) 2 O 7 ceramics were synthesized to investigate the influence of multi-nuclides incorporation on phase structure and aqueous stability of Gd 2 Zr 2 O 7 . XRD and BSE results show that all the ceramics exhibit a single pyrochlore structure. Raman spectroscopy reveals that the degree of structural order for (Gd,A) 2 (Zr,B) 2 O 7 solid solutions increases with enhanced TRPO waste content. In addition, aqueous stability testing was carried out using the MCC-1 static leach test method. The results demonstrate that the normalized release rates of the elements in TRPO waste are kept in a low value below 10 −4 g m −2 d −1 . La shows the highest normalized release rate of all the involved elements, while Zr exhibits the best chemical stability.
研究领域:
材料科学
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核化学与放射化学
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环境科学
✓ 已验证
DOI
高影响因子
JOURNAL OF NUCLEAR MATERIALS
·
2026
·
IF 3.3
Haojie Zhang,Yutong Zhang,Mao Deng,Yanli Shi,Kailei Lu,Shuyi Zhu,Zhangyi Huang,Qi Jianqi,Tiecheng Lu
Dense nanocrystalline ceramics exhibit excellent chemical durability comparable to coarse-grained counterparts. • A unique crystalline, multilayered surface film was observed on nanocrystalline surfaces for the first time. • Sharp interfacial chemical gradients confirm the leaching mechanism is governed by coupled dissolution-reprecipitation. Introducing a high density of grain boundaries into ceramic waste forms has been shown to significantly enhance their irradiation resistance. However, this strategy is likely to compromise their leaching resistance. To date, this view still lacks experimental verification. Furthermore, the corrosion behavior and nuclide leaching mechanisms of nanocrystalline ceramic waste forms remain unclear. Herein, x TRPO-(1- x )Gd 2 Zr 2 O 7 ( x = 0.3 and 0.5) ceramics with grain sizes ranging from the nanoscale (53.6 nm) to the micron scale (13.4 µm) were synthesized, and their chemical durability was investigated via semi-dynamic leaching tests. The normalized leaching rates ( LR i ) for both micron- and nanograined ceramics fell within the range of 10 -5 ∼10 -6 g·m -2 ·d -1 after 42 days, indicating good chemical durability, although the nano-grained ceramics exhibited slightly higher release rates. We demonstrate distinct surface alteration behaviors for the first time: an amorphous film formed on the micron-grained samples, whereas a crystalline, multilayered structure developed on the nano-grained samples after leaching. Both alteration layers can act as protective barriers against aqueous corrosion, contributing to reduced long-term release rates. These findings provide valuable insights into performance prediction and material design for next-generation ceramic waste forms.
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DOI
高影响因子
CERAMICS INTERNATIONAL
·
2020
·Vol. 46
·期 11
·18888-18894
·
IF 3.83
Yiqian Guo,Wenting He,Hongbo Guo
Ceramic materials for the thermal barrier coating (TBC) application of Gd 2 Zr 2 O 7 (GZO), (Gd 0.94 Yb 0.06 ) 2 Zr 2 O 7 (GYb 0.06 Z), (Gd 0.925 Sc 0.075 ) 2 Zr 2 O 7 (GSc 0.075 Z), (Gd 0.865 Sc 0.075 Yb 0.06 ) 2 Zr 2 O 7 (GSc 0.075 Yb 0.06 Z), and (Gd 0.8 Sc 0.1 Yb 0.1 ) 2 Zr 2 O 7 (GSc 0.1 Yb 0.1 Z) were successfully synthesized by chemical co-precipitation. The effects of the doping of Sc 2 O 3 and Yb 2 O 3 on the phases, thermo-physical and mechanical properties of the ceramics were investigated. The results show that both Yb 2 O 3 and Sc 2 O 3 doping promoted the phase transition of GZO from pyrochlore to fluorite. All the Sc 2 O 3 -doped samples exhibited enhanced fracture toughness, as compared to the undoped sample. Furthermore, the GSc 0.075 Yb 0.06 Z sample revealed a thermal conductivity of ~0.8 W/mK at 1200 °C, which was nearly 30% lower than that of the undoped sample. The associated mechanisms related to the effects of the doping on the thermophysical and mechanical properties are discussed.
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DOI
高影响因子
JOURNAL OF THE EUROPEAN CERAMIC SOCIETY
·
2016
·
IF 2.933
Xiaoyan Shu,Long Fan,Yi Xie,Weidong Zhu,Sheqi Pan,Yi Ding,Fangting Chi,Yanlin Wu,Xirui Lu
It is necessary to study the self-irradiation effects of nuclear waste forms under α-decay in the long term storage. In the present work, accelerated irradiation experiments were performed on (Gd 1-4 x U 2 x ) 2 (Zr 1- x U x ) 2 O 7 ( x = 0, 0.10, 0.14) samples using 0.5 MeV alpha-particle irradiation at fluences ranging from 1 × 10 14 to 1 × 10 17 ions/cm 2 at room temperature . Irradiation induced microstructural evolution was examined by grazing incidence X-ray diffraction (GIXRD), Raman spectroscopy and Field-emission scanning electron microscopy (FESEM). The results show that the main crystal structure is kept, however, weaker structural ordering is leaded as a result of intensified irradiation. And the radiation resistance is enhanced by the growing uranium content in the discussed range. Moreover, the irradiation effects as a function of depth have been discussed. Raman spectra reveal that the vibration intensity of atomic bonds are changed due to increased irradiation. In addition, the microtopography and element distribution have been kept after irradiation.
研究领域:
核材料
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辐照效应
·
陶瓷固化体
·
材料科学
·
核化学
✓ 已验证
DOI
高影响因子
CERAMICS INTERNATIONAL
·
2023
·
IF 5.2
Zhangyi Huang,Jiaochun Zheng,Yutong Zhang,Yang Shi,Junjing Duan,Ruichong Chen,Tiecheng Lu,Zhijun Wang,Jianqi Qi,Haomin Wang
Gd 2 Zr 2 O 7 (GZO)-based ceramic waste form has attracted broad interest due to its potential applications in the long-term disposal of high-level nuclear waste . However, its high-capacity isomorphic immobilization and leaching mechanism are not well understood yet. Herein, GZO-based waste form with a single pyrochlore phase and homogeneous element distribution, achieving an isomorphic waste load as high as 50 wt%, was fabricated successfully. Isomorphism failure of the waste form is due to the Ln 6 MoO 12 (Ln is lanthanides) formation and direct precipitation of PdO from the oversaturated solid solution. Chemical durability tests showed that the 42-day leaching rates of nearly all elements in the waste form with the maximum waste load were only between 10 −6 and 10 −5 gm −2 d −1 . The leaching of 0.5SW·0.5GZO over a period of 42 days is primarily controlled by dissolution, leading to a gradual restructuring of the surface in two distinct stages: the formation of an amorphous passivation film and the agglomeration of amorphous precipitates. Notably, the formation of the amorphous passivation film stands as the primary factor influencing the leaching rate of the waste form.
研究领域:
核废料管理
·
材料科学
·
放射性废物处理
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产品关联
DOI
高影响因子
CERAMICS INTERNATIONAL
·
2017
·
IF 2.986
Jin Wang,Junxia Wang,Yibing Zhang,Yuxiang Li,Yuancheng Teng,Zhe Wang,Hongbin Tan
A series of Nd and Ce co-doped (Gd 1−x Nd x ) 2 (Zr 1−x Ce x ) 2 O 7 (0 ≤ x ≤ 1) pyrochlores were synthesized by flux method at 900–1000 °C using nitrates as starting materials and a small amount of NaF as fluxing agent . The influences of contents of Nd/Ce, fluxing agent and reaction temperature on the phase structure of the pyrochlores were systematically investigated by X-ray diffraction (XRD) and Raman spectroscopy (Raman). The chemical stability of Nd and Ce co-doped pyrochlore bulk ceramics was also evaluated. XRD and Raman results showed that the crystalline phase of (Gd 1−x Nd x ) 2 (Zr 1−x Ce x ) 2 O 7 (0 ≤ x ≤ 1) pyrochlores always remained a single disordered defect-fluorite structure for any x value. XRD, Raman spectrum and SEM-EDX results revealed that the Nd and Ce could be co-doped at the Gd-site and Zr-site of the Gd 2 Zr 2 O 7 pyrochlore structure, respectively. The normalized release rates of Gd, Zr, Nd and Ce in (Gd 1−x Nd x ) 2 (Zr 1−x Ce x ) 2 O 7 pyrochlore bulk ceramics (x = 0.25, 0.5 and 0.75) remained relatively constant in a low value below 10 −4 g m −2 d −1 at 90 °C for 7 days, exhibiting superior chemical stability.
研究领域:
材料科学
·
核废料管理
✓ 已验证
DOI
高影响因子
MATERIALS CHEMISTRY AND PHYSICS
·
2022
·
IF 4.778
Guilin Wei,Xudong Liu,Shunzhang Chen,Dadong Shao,Wenqing Yuan,Xirui Lu,Yi Xie,Xiaoyan Shu
A rapid and efficient method is preferred for immobilizing nuclear wastes . In this study, Ce 4+ , a simulated tetravalent actinide ( An 4+ ) nuclear waste, was directly introduced into the Gd 2 Zr 2 O 7 matrix (as-prepared) via spark plasma sintering (SPS) at different temperatures (1725, 1750, 1775, and 1800 °C) without a complicated lattice occupancy design. The solubility of CeO 2 could be achieved to 18.8 wt %. Most of the sintered specimens exhibited the fluorite phase, but two samples sintered at 1775 °C exhibited the pyrochlore phase due to the Ce 4+ →Ce 3+ transformation. Moreover, the samples sintered at various temperatures exhibited highly densified microstructures, in which Gd, Zr, and Ce were evenly distributed, indicating adequate immobilization results. By increasing the doping content to 60 mol%, the grain boundary of the sample sintered at 1800 °C became almost indistinguishable and exhibited slight vitrification, which was confirmed by transmission electron microscopy results. These results afforded a rapid and effective method for the immobilization of nuclear wastes in the as-prepared matrix without considering the lattice occupation.
研究领域:
材料科学
·
核废料管理
✓ 已验证
产品关联
DOI
高影响因子
CERAMICS INTERNATIONAL
·
2023
·
IF 5.2
Chenglu Lian,Zhihua Long,Wei Qian,Zhichen Guan,Kun Huo,Yinqun Hua,Jie Cai
Thermal barrier coating materials play a crucial role ensuring the efficient and stable operation of gas turbines. The thermophysical and mechanical properties of GZ 1-x -GT x (x = 0, 0.1, 0.3, 0.5) composite ceramics, as well as the corrosion resistance properties against calcium magnesium aluminum silicate (CMAS) at 1250 °C, were investigated. The results indicated that the overall properties of Gd 2 Zr 2 O 7 -GdTaO 4 composite ceramics significantly improved with an increase in the second phase GdTaO 4 content. Among all the ceramics designed, GZ 0.5 -GT 0.5 exhibited the lowest thermal conductivity (0.920 W m −1 K −1 at 800 °C) and the highest fracture toughness (2.02 MPa m 1/2 ). Additionally, the molten CMAS interacted with the Gd 2 Zr 2 O 7 -GdTaO 4 composite ceramics, forming a dense apatite layer, which positively contributed to inhibiting CMAS infiltration. Considering its excellent thermal, mechanical, and corrosion resistance properties, Gd 2 Zr 2 O 7 -GdTaO 4 composite ceramics are considered a promising material for thermal barrier coatings.
研究领域:
材料科学
·
能源工程
✓ 已验证
产品关联
DOI
高影响因子
CERAMICS INTERNATIONAL
·
2025
·
IF 5.6
Xi Peng,Qi Ni,Guilin Wei,Fuxin Liu,Xiaoyan Shu,Fen Luo,Congcong Ding,Xirui Lu
The treatment of high-level radioactive waste with trialkyl phosphine oxide (TRPO) results in radioactive residues, necessitating the effective management of TRPO process waste to protect the environment. In this study, TRPO waste was immobilized in Gd 2 Zr 2 O 7 for the first time using solid-state reactive sintering at 1300 °C. XRD and Raman analysis results demonstrate that the waste solubility exceeds 50 wt .%, indicating a high incorporation capacity. With increasing TRPO waste addition, the pyrochlore phase initially transitioned to fluorite before reverting to pyrochlore. Valence state analysis suggests that fluorite-to-pyrochlore transition was driven by redox reactions of Ce at high temperatures, where Ce 4+ was reduced to Ce 3+ . The incorporation of Ce 3+ into the A-site of Gd 2 Zr 2 O 7 led to an increase in the r A /r B ratio, reaching a range of 1.46 to 1.78. In sample N5 (50 wt .% waste content), a Vickers hardness of 12.03 GPa was achieved, corresponding to the largest grain size and highest densification. Leaching experiments indicated that the normalized leaching rates of Nd and Ce after 42 d were both 10 -6 g·m -2 ·L -1 . These results suggest that variable valence elements in TRPO waste significantly influence the Gd 2 Zr 2 O 7 structure, and that samples synthesized under low-temperature sintering conditions exhibit excellent mechanical and chemical stability.
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产品关联
DOI
高影响因子
危险品化学品经营许可证（带存储）