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1.
To extend the practicability of ceramics in immobilizing nuclear waste with fluctuant composition, structural design should be abandoned. The simulated tetravalent actinide waste An4+ (Ce4+) was directly doped into prepared Gd2Zr2O7, and the waste forms were synthesized by high-temperature solid-state reaction. It has been shown that the maximum loading of CeO2 in Gd2Zr2O7 lies between 20 and 30 wt.%, and Ce elements are uniformly distributed in the matrix. Existing in Ce3+ and Ce4+, cerium ions automatically occupied both the Gd and Zr sites in Gd2Zr2O7 according to valence equilibrium. This occupation causes the change of r(A3+)/r(B4+) and eventually leads to the structure transition from pyrochlore to fluorite. In addition, the normalized leaching rate of the sample with 60 wt.% of dopant was about 2.5 × 10−7 g m−2 d−1 on the 35th day. In this study, a free occupation of simulated waste ions in ceramics was proposed.  相似文献   

2.
Gd2(Zr1−xNbx)2O7+x (0 ≤ x ≤ 0.2) ceramics are prepared via the solid state reaction process at 1973 K for 10 h in air. Gd2(Zr1−xNbx)2O7+x (x = 0.1, 0.2) ceramics exhibit an ordered pyrochlore-type structure, whereas Gd2Zr2O7 has a defective fluorite-type structure. The electrical property of Gd2(Zr1−xNbx)2O7+x ceramics is investigated by electrochemical impedance spectroscopy over a frequency range of 10 Hz to 8 MHz from 623 to 923 K. The electrical conductivity obeys the Arrhenius equation. The grain conductivity of Gd2(Zr1−xNbx)2O7+x ceramics varies with doping different Nb contents, and exhibits a maximum at the Nb content of x = 0.1 in the temperature range of 623-923 K. The conductivity in hydrogen atmosphere is a little bit higher than in air in the temperature range of 723-923 K, which indicates that the doping of Zr4+ by Nb5+ can increase the proton-type conduction and reduce the oxide-ionic conduction. The conduction of Gd2(Zr1−xNbx)2O7+x is not a pure oxide-ionic conductor.  相似文献   

3.
A series of compositions with general stoichiometry Ca1?xZr1?xNd2xTi2O7 has been prepared by high‐temperature solid‐state reaction of component oxides and characterized by powder X‐ray diffraction and electron probe for microanalyses (EPMA). The phase fields in CaZrTi2O7–Nd2Ti2O7 system and distribution of ions in different phases have been determined. Four different phase fields, namely monoclinic zirconolite, cubic perovskite, cubic pyrochlore, and monoclinic Nd2Ti2O7 structure types are observed in this system. The 4M‐polytype of zirconolite structure is stabilized by substitution of Nd3+ ion. The addition of Nd3+ ions form a cubic perovskite structure‐type phase and thus observed in all the compositions with 0.05 ≤ x ≤ 0.80. Cubic pyrochlore structure‐type phase is observed as a coexisting phase in the nominal composition with 0.20 ≤ x ≤ 0.90. Only a subtle amounts of Ca2+ and Zr4+ are incorporated into the perovskite‐type Nd2Ti2O7 structure. EPMA analyses on different coexisting phases revealed that the pyrochlore and perovskite phases have Nd3+‐rich compositions.  相似文献   

4.
A simple and low-energy-consuming approach for preparing ceramic nuclear waste forms is greatly preferred for disposal of ever-increasing amounts of radioactive nuclear wastes. Herein, simulated radionuclide Ce could be rapidly incorporated into Gd2Zr2O7 ceramic via flash sintering technique. Under an electric field of 250 V/cm, Gd2Zr2−xCexO7 (0.0 ≤x ≤ 1.2) waste forms with a single phase of defect-fluorite were flash sintered at relatively low temperatures of 889–997 °C in 60 s. The onset temperature of flash sintering was decreased with the enhancement of Ce content. Furthermore, the density and grain size of Gd2Zr2−xCexO7 waste forms were increased with the increase of the current limit. The nearly full dense Gd2Zr2−xCexO7 waste forms were flash sintered at a current limit of 200 mA. The normalized leaching rates of Gd, Ce, and Zr in Gd2Zr0.8Ce1.2O7 after 28 d were 6.5475 × 10−5, 1.1624 × 10−7, and 1.1613 × 10−7 g·m−2·d−1, respectively, which exhibited a good chemical durability.  相似文献   

5.
Several compositions of NdYb1−xGdxZr2O7 (0 ≤ x ≤ 1.0) ceramics were prepared by pressureless-sintering method at 1973 K for 10 h in air. The relative density, microstructure and electrical conductivity of NdYb1−xGdxZr2O7 ceramics were analyzed by the Archimedes method, X-ray diffraction, scanning electron microscopy and impedance plots measurements. NdYb1−xGdxZr2O7 (0 ≤ x ≤ 0.3) ceramics have a single phase of defect fluorite-type structure, and NdYb1−xGdxZr2O7 (0.7 ≤ x ≤ 1.0) ceramics exhibit a single phase of pyrochlore-type structure; however, the NdYb0.5Gd0.5Zr2O7 composition shows mixed phases of both defect fluorite-type and pyrochlore-type structures. The measured values of the grain conductivity obey the Arrhenius relation. The grain conductivity of each composition in NdYb1−xGdxZr2O7 ceramics gradually increases with increasing temperature from 673 to 1173 K. NdYb1−xGdxZr2O7 ceramics are oxide-ion conductor in the oxygen partial pressure range of 1.0 × 10−4 to 1.0 atm at all test temperature levels. The highest grain conductivity value obtained in this work is 1.79 × 10−2 S cm−1 at 1173 K for NdYb0.3Gd0.7Zr2O7 composition.  相似文献   

6.
A theoretical study of Th accommodation in Gd2Zr2O7 has been performed by density functional theory. Our calculations show that although thorium has only one charge state of Th4+, it can be incorporated into both Gd3+ and Zr4+ sites in Gd2Zr2O7, depending on the chemical environments. Th occupation at Gd3+ site results in charge redistribution and the excess electrons introduced by Th are transferred to the neighboring Zr ions. As compared with the pure state, Th-containing Gd2Zr2O7 pyrochlores are probably more inclined to undergo order-disorder transformation and are less susceptible to radiation-induced amorphization.  相似文献   

7.
Polycrystalline GdSm1?xCaxZr2O7?x/2 (0  x  0.20) ceramics have been prepared by the solid-state reaction method. The effects of CaO addition on the microstructure and electrical properties of the pyrochlore-type GdSmZr2O7 ceramic were investigated. GdSm1?xCaxZr2O7?x/2 (x  0.05) ceramics exhibit a pyrochlore-type structure; however, GdSm1?xCaxZr2O7?x/2 (0.10  x  0.20) ceramics consist of the pyrochlore-type structure and a small amount of CaZrO3. The total conductivity of GdSm1?xCaxZr2O7?x/2 ceramics follows the Arrhenius relation, and gradually increases with increasing temperature from 723 to 1173 K. GdSm1?xCaxZr2O7?x/2 ceramics are oxide-ion conductors in the oxygen partial pressure range of 1.0 × 10?4–1.0 atm at each test temperature. The highest total conductivity is about 1.20 × 10?2 S cm?1 at 1173 K for the GdSm0.9Ca0.1Zr2O6.95 ceramic.  相似文献   

8.
(Gd1−xYbx)2Zr2O7 compounds were synthesized by solid reaction. Yb2O3 doped Gd2Zr2O7 exhibited lower thermal conductivities and higher thermal expansion coefficients (TECs) than Gd2Zr2O7. The TECs of (Gd1−xYbx)2Zr2O7 ceramics increased with increasing Yb2O3 contents. (Gd0.9Yb0.1)2Zr2O7 (GYbZ) ceramic exhibited the lowest thermal conductivity among all the ceramics studied, within the range of 0.8–1.1 W/mK (20–1600 °C). The Young's modulus of GYbZ bulk is 265.6 ± 11 GPa. GYbZ/YSZ double-ceramic-layer thermal barrier coatings (TBCs) were prepared by electron beam physical vapor deposition (EB-PVD). The coatings had an average life of more than 3700 cycles during flame shock test with a coating surface temperature of ∼1350 °C. Spallation failure of the TBC occurred by delamination cracking within GYbZ layer, which was a result of high temperature gradient in the GYbZ layer and low fracture toughness of GYbZ material.  相似文献   

9.
《Ceramics International》2022,48(7):9602-9609
The (La0.2Gd0.2Y0.2Yb0.2Er0.2)2(Zr1-xTix)2O7 (x = 0–0.5) high-entropy ceramics were successfully prepared by a solid state reaction method and their structures and thermo-physical properties were investigated. It was found that the high-entropy ceramics demonstrate pure pyrochlore phase with the composition of x = 0.1–0.5, while (La0.2Gd0.2Y0.2Yb0.2Er0.2)2Zr2O7 shows the defective fluorite structure. The sintered high-entropy ceramics are dense and the grain boundaries are clean. The grain size of high-entropy ceramics increases with the Ti4+ content. The average thermal expansion coefficients of the (La0.2Gd0.2Y0.2Yb0.2Er0.2)2(Zr1-xTix)2O7 high-entropy ceramics range from 10.65 × 10?6 K?1 to 10.84 × 10?6 K?1. Importantly, the substitution of Zr4+ with Ti4+ resulted in a remarkable decrease in thermal conductivity of (La0.2Gd0.2Y0.2Yb0.2Er0.2)2(Zr1-xTix)2O7 high-entropy ceramics. It reduced from 1.66 W m?1 K?1 to 1.20 W m?1 K?1, which should be ascribed to the synergistic effects of mass disorder, size disorder, mixed configuration entropy value and rattlers.  相似文献   

10.
In order to ascertain the structural relationship of zirconolite and pyrochlore for their potential application in HLW immobilization, the Gd-doped zirconolite-pyrochlore composite ceramics (Ca1-xZr1-xGd2xTi2O7) were systematically synthesized with x?=?0.0–1.0 by traditional solid-phase reaction method. The phase evolution and microstructure of the as-prepared samples have been elucidated by XRD and Rietveld refinement, Raman spectroscopy, BSE-EDS and HRTEM analysis. The results showed that zirconolite-2M, zirconolite-4M, perovskite and pyrochlore, four phases were identified in Ca1-xZr1-xGd2xTi2O7 system and could be coexisted at x?=?0.4 composition. With the increase of Gd3+ substitution, the phase evolution was followed by zirconolite-2M→zirconolite-4M→pyrochlore. It is illustrated that the phase transformation from zirconolite-2M to zirconolite-4M was promoted by the preferential substitution of Gd3+ for Ca2+. And the solubility of Gd3+ in zirconolite-2M, zirconolite-4M and pyrochlore increased in sequence. The chemical stability test was also measured by the PCT leaching method. The normalized elemental release rates of Ca, Zr, Ti and Gd in Ca1-xZr1-xGd2xTi2O7 system were fairly low and in the range of 10?6?10?8 g?m?2 d?1, which indicated a potential ceramics composite ensemble of CaZrTi2O7-Gd2Ti2O7 system for nuclear HLW immobilization.  相似文献   

11.
The lithium-doped phases Gd1.7Li0.3Zr2O6.7 and Gd2Zr1.7Li0.3O6.55 with a pyrochlore structure were prepared by the modified Pechini method using citric acid and glycerol. Monitoring of the lithium content by using a nuclear microanalysis showed that a significant loss of lithium occurred after heat treatment above 1200 °C. Dense ceramics with a stoichiometric lithium content can be prepared by a low temperature microwave sintering (1100 °C). The introduction of lithium in the Gd-sublattice was accompanied by a decrease in the unit cell parameter (a = 10.5208 (1) Å vs 10.5346 (2) Å for Gd2Zr2O7) and during doping at the Zr-sites with lithium, the cell parameter increased (10.5720 (1) Å). The doping in both cases led to an increase in the free cell volume. The impedance spectroscopy results showed that the bulk conductivity can be enhanced by the Li+-doping at the Gd3+-site by almost an order of magnitude. The sample Gd2Zr1.7Li0.3O6.55 had a conductivity lower than that of Gd1.7Li0.3Zr2O6.7 due to the possible trapping of oxygen vacancies by a high-charged acceptor defect LiZr???. The conductivity?pO2 measurements showed that the Li-containing phase was a pure oxide-ion conductor at T < 800 °C.  相似文献   

12.
A nitrate–citrate combustion method combined with microwave sintering was firstly employed for the rapid fabrication of the Gd2Zr2O7 matrix immobilizing various amounts of simulated nuclear wastes. Phase evolutions, microstructure changes, element distributions, densification processes and mechanical properties of the as-prepared (1 – x)Gd2Zr2O7·xTRPO (0.0 ≤ x ≤ 0.6) at various temperatures were investigated. Compared to the reported studies, we have increased the immobilization amount of simulated TRPO waste within a crystal structure from 45 to 60 wt%. Td and Tg (the threshold temperatures to trigger accelerated densification and grain growth, respectively) were employed to divide the densification process into three stages. the mechanical properties and the densification stages of the (1 – x)Gd2Zr2O7·xTRPO (0.0 ≤ x ≤ 0.6) ceramics sintered under microwave sintering at various temperatures were finally determined. Fine-grained (1 – x)Gd2Zr2O7·xTRPO (0.0 ≤ x ≤ 0.6) ceramic waste forms with average grain size less than 200 nm and relative density higher than 90% can be obtained by microwave sintering at sintering temperature less than 1400 °C.  相似文献   

13.
《Ceramics International》2016,42(13):14749-14753
Sm2(Zr1–xTix)2O7 (0≤x≤0.15) ceramics have been fabricated by pressureless-sintering method at 1973 K for 10 h in air. The influence of TiO2 doping on microstructure and thermo-optical properties of Sm2(Zr1–xTix)2O7 ceramics is investigated by X-ray diffraction, scanning electron microscopy and Fourier transform infrared spectroscopy measurements. The partial substitution of Ti4+ for Zr4+ results in a significant increase in emissivity at low wavelengths contrasted with undoped Sm2Zr2O7. Sm2(Zr0.85Ti0.15)2O7 ceramic exhibits a high emissivity of above 0.70 at 1073 K in a wavelength range of 3–16 µm, where the highest value at this temperature is more than 0.90 especially in the wavelength range of 9–14 µm. FT-IR spectra and optical absorption spectra unveil the mechanisms of enhanced emissivity in Sm2(Zr1–xTix)2O7 (0.05≤x≤0.15) ceramics in the intermediate infrared range, especially at the wavelengths of 3–8 µm, due to Ti4+ ion substitution for Zr4+ ion.  相似文献   

14.
The resistance of EB‐PVD Gd2Zr2O7 thermal barrier coatings against high‐temperature infiltration and subsequent degradation by molten volcanic ash is investigated by microstructural analysis. At 1200°C, EB‐PVD Gd2Zr2O7 coatings with silica‐rich, artificial volcanic ash (AVA) overlay show a highly dynamic and complex recession scenario. Gd2O3 is leached out from Gd2Zr2O7 by AVA and rapidly crystallizes as an oxyapatite‐type solid‐solution (Ca,Gd)2(Gd,Zr)8(Si,Al)6O26. The second product of Gd2Zr2O7 decomposition is Gd2O3 fully stabilized ZrO2 (Gd‐FSZ). Both reaction products are forming an interpenetrating network filling open coating porosity. However, first‐generation Gd‐oxyapatite and Gd‐FSZ are exhibiting chemical evolution in the long term. The chemical composition of Gd‐oxyapatite does evolve from Ca,Zr enriched to Gd‐rich. AVA continuously leaches out Gd2O3 from Gd‐FSZ followed by destabilization to the monoclinic ZrO2 polymorph. Finally, zircon (ZrSiO4) is formed. In addition to the prevalent formation of Gd‐oxyapatite, a Gd‐, Zr‐, Fe‐, and Ti‐rich oxide is observed. From chemical analysis and electron diffraction it is concluded that this phase belongs to the zirconolite‐type family (zirconolite CaZrTi2O7), exhibiting an almost full substitution Ca2+ + Ti4+ <> Gd3+ + Fe3+. As all Gd2Zr2O7 decomposition products with the exception of ZrSiO4 exhibit considerable solid solubility ranges, it is difficult to conclusively assess the resistance of EB‐PVD Gd2Zr2O7 coatings versus volcanic ash attack.  相似文献   

15.
《Ceramics International》2023,49(8):12696-12701
ZrSiO4-based ceramics have been considered as one of the candidate nuclear waste forms, while the immobilization behavior of mixed-valent uranium in the structure of the ceramics was unclear. Herein, ZrSiO4–U ceramics with a general formula of Zr1-4x(U6+xU5+2x)SiO4 were designed and synthesized. The evolutions of phase and microstructure depending on the content of U were investigated. The ceramics with 0 ≤ x < 0.04 showed a single ZrSiO4 phase, while U3O8 phase was detected when x ≥ 0.04. The results demonstrated that the solubility limit of U in ZrSiO4 ceramic was up to 1.51 at.% or 11.06 wt%. The calculated lattice parameters increased with the increase of U content. The increased parameters provided the evidence of the immobilization of both U5+ and U6+ into ZrSiO4 crystal lattice by replacing Zr4+. Furthermore, the obtained ZrSiO4–U ceramics exhibited good aqueous durability (∼10−5 g m−2 d−1). The results indicated that ZrSiO4-based ceramics can be employed to effectively immobilize mixed-valent U.  相似文献   

16.
《Ceramics International》2020,46(9):13054-13065
Gadolinium zirconate (Gd2Zr2O7) coatings doped by the transition metal Ti and the alkaline earth metal Mg were expected to have improved thermal radiation performance, which could be combined with their excellent thermal barrier properties to comprehensively improve the thermal insulating performance. The results show that the parent Gd2Zr2O7 powder as well as the Gd-site and Zr-site substituted powders crystallize as pyrochlore Gd2Zr2O7 in Fd-3m space group, while all the as-sprayed coatings have the combination of fluorite and a little part of pyrochlore phase. Gd2Zr2O7 ceramic has high mid-infrared emittance and the addition of Ti4+ into Gd2Zr2O7 can enhance the infrared absorption/emittance in a specific wavenumber range, dominantly in the near-infrared (0.75–2.5 μm) band due to the enhancement of electron transition induced by the impurity energy levels linked to the widening of the conduction band. The normal spectral infrared emissivity of Gd2Zr2O7-based coating was higher than 0.88 at 1073 K. The monolayered doped Gd2Zr2O7 coatings present very low thermal cycling lifetime, similar with the parent coating, mainly related with their low fracture toughness, despite (Gd1-xMgx)2Zr2O7 series display lower thermal conductivity than the parent one.  相似文献   

17.
《Ceramics International》2019,45(13):16450-16457
The study underlines the impact of Ti4+ substitution in Gd2Zr2O7 for applications in thermal barrier coatings (TBC). Depending on the Ti4+ content, two different crystal structures of Gd2Zr2O7 namely pyrochlore and fluorite were determined. Ti4+ substitutions in the increasing order induced a gradual contraction of Gd2Zr2O7 unit cell; however, with the accomplishment of concentration dependent crystal structures of either single phase pyrochlore or mixtures of pyrochlore and fluorite. Absorption measurements enunciated the enhanced infra-red reflectance behaviour of Gd2Zr2O7 due to Ti4+ substitutions. A gradual increment in the concentration of Ti4+ substitutions in Gd2Zr2O7 envisaged a simultaneous porous to dense morphological features, which reflected in the resultant mechanical data. Hot corrosion studies ensure the critical role of Ti4+ to retain the crystal structure of Gd2Zr2O7.  相似文献   

18.
《Ceramics International》2020,46(15):24029-24037
Three kinds of Gd2Zr2O7/ZrO2 (GZC) composite fibers with different proportions of Gd2Zr2O7 were prepared by electrospinning method through changing the amount of Gd3+ in precursor solutions. The thermal decomposition, crystallization process, high temperature stability and heat-conducting properties of GZC fibers were fully characterized. The results showed that there were three crystalline phases, tetragonal phase ZrO2, cubic phase ZrO2 and defect fluorite phase Gd2Zr2O7 in all the GZC fibers. The content of Gd2Zr2O7 increased gradually with the increase of Gd3+ in precursor solutions which led to the gradual slowing down of grain growth rate, the decrease of thermal conductivity and the increase of high temperature stability of the obtained composite fibers. The thermal conductivities of all the GZC fiber sheets were lower than that of 7YSZ fiber sheet. The sheets of all the GZC fibers could keep the high temperature stability up to 1300 °C.  相似文献   

19.
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 (Gd1-4xU2x)2(Zr1-xUx)2O7 (x = 0, 0.10, 0.14) samples using 0.5 MeV alpha-particle irradiation at fluences ranging from 1 × 1014 to 1 × 1017 ions/cm2 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.  相似文献   

20.
《Ceramics International》2022,48(15):21125-21133
Solid solutions of Zr1+xMn1-xMo3-2xV2xO12 (0 ≤ x ≤ 0.5) are developed with reduced phase transition temperature (from 362 to 160 K) by introducing V5+ into ZrMnMo3O12. Zr1+xMn1-xMo3-2xV2xO12 adopt monoclinic (P21/a) and orthorhombic (Pbcn) structure at room temperature (RT) for x ≤ 0.1 and x ≥ 0.2, respectively. The formation of bond V–O induces a larger average effective negative charge on oxygen to enhance the repulsive force between them and then strengthens the bond of Mo–O, which reduces the phase transition temperature due to the reduction in effective electronegativity and expands negative thermal expansion (NTE) range covering RT. NTE property in a wide temperature range (from 160 to 673 K) for Zr1.5Mn0.5Mo2VO12 is realized, implying great potential for applications. The NTE property of the materials is induced by low-frequency phonons.  相似文献   

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