ZrO2—CeO2 Ceramics Doped with Yttrium: Comparison
Please note this is a comparison between Version 3 by Lindsay Dong and Version 2 by Camila Xu.

The synthesis of ZrO2—CeO2 ceramics was carried out using solid-phase mechanochemical synthesis followed by thermal sintering of the obtained mixtures. ZrO2 and CeO2 powders in equal mole fractions (0.5:0.5) were chosen as initial components for synthesis. 

  • oxide ceramics
  • inert matrices
  • phase transformations

1. Introduction

Over the past few years, special attention has been paid to the search for new types of compounds and compositions for the creation of fuel elements with dispersed nuclear fuel, as well as materials for inert nuclear fuel matrices. Interest in these types of research is due to the need to increase the level of safety of nuclear reactors, the transition to uranium-free fuel and a decrease in the concentration of accumulated plutonium and nuclear waste [1][2][3]. The search for new types of materials is also due to the need to operate these materials under conditions of increased temperatures (more than 700 °C) and an increased radiation background, including neutron radiation, which initiates transmutation reactions, the product of which is the accumulation of helium, as well as interaction with fission fragments [4][5]. A distinctive feature of new types of inert matrix materials is the possibility of their operation at high temperatures due to the use of refractory oxide ceramics in them, as well as increased radiation resistance, which allows them to be operated much longer than conventional materials.
In this regard, for inert matrices of dispersed nuclear fuel in particular ceramics, the following requirements are put forward, which they must meet [6][7][8][9][10]. First, the inert matrix material should have good mechanical properties such as hardness, crack resistance and strength. At the same time, these materials must not only withstand short-term effects but also maintain stability for a long time of operation and, as a result, withstand the mechanical impact of the pressure of gaseous fission products, as well as the consequences of transmutation effects. Second, the material must be stable to phase changes capable of occurring as a result of prolonged radiation exposure or thermal conductivity. Additionally, the material must be highly compatible with the fuel composition, heat transfer agent and containment material. Thirdly, the material should have high thermal conductivity and low thermal expansion coefficients, which should ensure a good transfer of thermal energy from the fuel to the coolant.
Oxide ceramics such as ZrO2, CeO2, MgO, Al2O3 and Y2O3 [11][12][13][14][15], as well as various more complex oxide systems, are considered some of the promising material candidates for inert matrices of dispersed nuclear fuel [11][12][13][14][15]. Interest in them is due to the fact that the most studied nuclear fuels are UO2 and PuO2 oxide fuel, as well as their physicochemical, structural and mechanical properties and small sections of thermal neutron capture. Among the variety of oxide ceramics, great interest is shown in zirconium dioxide (ZrO2), the distinctive features of which are high chemical stability, mechanical and strength properties, as well as high compatibility, both with heat carriers and materials of fuel element shells [16][17]. However, despite the great prospects for the use of ZrO2 ceramics, there is one significant drawback, which lies in polymorphic phase transformations resulting both from elevated temperatures and from irradiation [18][19]. To eliminate this drawback, as a rule, various dopants are used, the addition of which leads to an increase in stability for polymorphic transformations as well as an increase in the strength and mechanical properties [20]. Another promising material among oxides is CeO2, which has high thermal and radiation stability as well as a number of properties that allow its use not only as inert matrices but also as a solid-fuel oxide element or catalyst [21][22][23].
One of the areas of research in the field of searching for and studying the properties of new types of materials based on oxide matrices is the creation of composite structures having several types of phases—the so-called cermets—which have a set of properties of components used in their production as well as increased resistance to external influences [24][25][26][27][28][29][30].
Based on the foregoing, the purpose of this work is to obtain ZrO2—CeO2 ceramics doped with yttrium of a complex multiphase composition with the formation of interstitial or substitutional solid solutions. The choice of zirconium and cerium oxides as components of the composite ceramics is due to their properties, which together should give a unique combination. The choice of yttrium as a dopant is due to the fact that, as a rule, yttrium is added to increase resistance to external influences, as well as to strengthen materials [31][32][33].

2. ZrO2—CeO2 Ceramics Doped with Yttrium

Figure 1 shows the results of the morphological changes in the synthesized ceramics, depending on the dopant concentration. In the case of the undoped ceramics, the particle shape was cubic or diamond-shaped grains, the size of which varied from 50 nm to several hundred nanometers. At the same time, most of the grains were agglomerates consisting of 5–10 grains stuck together. In the case of the doped ceramics, there were clear changes in the morphology and particle size, and the changes were directly dependent on the concentration of the dopant. At a dopant concentration of 0.10 mol, the structure exhibited small spherical grains, which were combined with larger grains to form agglomerates. At a dopant concentration of 0.15 mol, large grains were practically not observed, and the particles were porous formations of small grains. In the case of an increase in the dopant concentration to 0.20–0.25 mol, compaction of the agglomerates was observed, and at a concentration of 0.25 mol, the structure was dense agglomerates without visible cavities between the grains. This behavior may have been due to a change in the phase composition of the ceramics, depending on the dopant concentration, which led to a change in the nucleation processes upon annealing.

Figure 1. SEM images of morphological features of ZrO2—CeO2 ceramics, depending on the concentration of the yttrium dopant: (a) 0.00 mol, (b) 0.10 mol, (c) 0.15 mol, (d) 0.20 mol and (e) 0.25 mol.
Figure 2 shows the X-ray diffraction patterns obtained for a series of samples with different concentrations of yttrium dopant. A common observation for all the obtained diffraction patterns is that the shape and intensity of the reflections, as well as the ratio of the reflection areas to the background area, allowed us to conclude that the synthesized ceramics obtained by thermal sintering had a high structural ordering degree. At the same time, the main change in the X-ray diffraction patterns, depending on the dopant concentration, was the shift in reflections relative to the reference lines of the corresponding phases, determined using the full-profile analysis method. Such changes due to the substitution effect with an increasing dopant concentration could be due to both structural distortions and the formation of intercalation or replacement phases. These two factors were taken into account in the analysis and determination of the phase composition of the synthesized ceramics.
Figure 2. (a) X-ray diffraction patterns of the studied samples, depending on the dopant concentration. (b) Detailed representation of change in the position of diffraction reflections when determining the phase composition.

References

  1. Lombardi, C.; Luzzi, L.; Padovani, E.; Vettraino, F. Thoria and inert matrix fuels for a sustainable nuclear power. Prog. Nucl. Energy 2008, 50, 944–953.
  2. Ledergerber, G.; Degueldre, C.; Heimgartner, P.; Pouchon, M.; Kasemeyer, U. Inert matrix fuel for the utilisation of plutonium. Prog. Nucl. Energy 2001, 38, 301–308.
  3. Nandi, C.; Grover, V.; Bhandari, K.; Bhattacharya, S.; Mishra, S.; Banerjee, J.; Prakash, A.; Tyagi, A. Exploring YSZ/ZrO2—PuO2 systems: Candidates for inert matrix fuel. J. Nucl. Mater. 2018, 508, 82–91.
  4. Golovkina, L.S.; Orlova, A.I.; Nokhrin, A.V.; Boldin, M.S.; Lantsev, E.A.; Chuvil’deev, V.N.; Sakharov, N.V.; Shotin, S.V.; Zelenov, A.Y. Spark Plasma Sintering of fine-grained ceramic-metal composites YAG: Nd-(W, Mo) based on garnet-type oxide Y2.5Nd0.5Al5O12 for inert matrix fuel. J. Nucl. Mater. 2018, 511, 109–121.
  5. Ang, C.; Snead, L.; Kato, Y. A logical approach for zero-rupture Fully Ceramic Microencapsulated (FCM) fuels via pressure-assisted sintering route. J. Nucl. Mater. 2020, 531, 151987.
  6. Savchyn, V.P.; Popov, A.I.; Aksimentyeva, O.I.; Klym, H.; Horbenko, Y.Y.; Serga, V.; Moskina, A.; Karbovnyk, I. Cathodoluminescence characterization of polystyrene-BaZrO3 hybrid composites. Low Temp. Phys. 2016, 42, 597–600.
  7. Van Vuuren, A.J.; Skuratov, V.; Ibrayeva, A.; Zdorovets, M. Microstructural Effects of Al Doping on Si3N4 Irradiated with Swift Heavy Ions. Acta Phys. Pol. A 2019, 136, 241–244.
  8. Settar, A.; Abboudi, S.; Lebaal, N. Effect of inert metal foam matrices on hydrogen production intensification of methane steam reforming process in wall-coated reformer. Int. J. Hydrogen Energy 2018, 43, 12386–12397.
  9. Manara, D.; Naji, M.; Mastromarino, S.; Elorrieta, J.; Magnani, N.; Martel, L.; Colle, J.-Y. The Raman fingerprint of plutonium dioxide: Some example applications for the detection of PuO2 in host matrices. J. Nucl. Mater. 2018, 499, 268–271.
  10. Mikhailov, D.A.; Orlova, A.I.; Malanina, N.V.; Nokhrin, A.V.; Potanina, E.A.; Chuvil’deev, V.N.; Boldin, M.S.; Sakharov, N.V.; Belkin, O.A.; Kalenova, M.Y.; et al. A study of fine-grained ceramics based on complex oxides ZrO2-Ln2O3 (Ln = Sm, Yb) obtained by Spark Plasma Sintering for inert matrix fuel. Ceram. Int. 2018, 44, 18595–18608.
  11. Monge, M.A.; González, R.; Muñoz Santiuste, J.E.; Pareja, R.; Chen, Y.; Kotomin, E.A.; Popov, A.I. Photoconversion and dynamic hole recycling process in anion vacancies in neutron-irradiated MgO crystals. Phys. Rev. B 1999, 60, 3787–3791.
  12. Monge, M.A.; González, R.; Muñoz-Santiuste, J.E.; Pareja, R.; Chen, Y.; Kotomin, E.; Popov, A. Photoconversion of F+ centers in neutron-irradiated MgO. Nucl. Instrum. Methods Phys. Res. Sect. B Beam Interact. Mater. At. 2000, 166, 220–224.
  13. Kadyrzhanov, K.K.; Tinishbaeva, K.; Uglov, V.V. Investigation of the effect of exposure to heavy Xe22+ ions on the mechanical properties of carbide ceramics. Eurasian Phys. Tech. J. 2021, 17, 46–53.
  14. Popov, A.; Lushchik, A.; Shablonin, E.; Vasil’Chenko, E.; Kotomin, E.; Moskina, A.; Kuzovkov, V. Comparison of the F-type center thermal annealing in heavy-ion and neutron irradiated Al2O3 single crystals. Nucl. Instrum. Methods Phys. Res. Sect. B Beam Interact. Mater. At. 2018, 433, 93–97.
  15. Degueldre, C.; Hellwig, C. Study of a zirconia based inert matrix fuel under irradiation. J. Nucl. Mater. 2003, 320, 96–105.
  16. Chauvin, N.; Konings, R.; Matzke, H. Optimisation of inert matrix fuel concepts for americium transmutation. J. Nucl. Mater. 1999, 274, 105–111.
  17. Vu, T.M.; Hartanto, D.; Chu, T.N.; Pham, N.V.H.; Bui, T.H. Sensitivity and uncertainty analysis of neutronic and kinetic parameters for CERCER and CERMET fueled ADS using SERPENT 2 and ENDF/B-VIII.0. Ann. Nucl. Energy 2021, 168, 108912.
  18. Costa, D.R.; Liu, H.; Lopes, D.A.; Middleburgh, S.C.; Wallenius, J.; Olsson, P. Interface interactions in UN-X-UO2 systems (X= V, Nb, Ta, Cr, Mo, W) by pressure-assisted diffusion experiments at 1773 K. J. Nucl. Mater. 2022, 561, 153554.
  19. Alin, M.; Kozlovskiy, A.L.; Zdorovets, M.V.; Uglov, V.V. Study of the mechanisms of the t-ZrO2→ c-ZrO2 type polymorphic transformations in ceramics as a result of irradiation with heavy Xe22+ ions. Solid State Sci. 2022, 123, 106791.
  20. Ivanov, I.A.; Alin, M.; Koloberdin, M.V.; Sapar, A.; Kurakhmedov, A.E.; Kozlovskiy, A.L.; Zdorovets, M.V.; Uglov, V.V. Effect of irradiation with heavy Xe22+ ions with energies of 165–230 MeV on change in optical characteristics of ZrO2 ceramic. Opt. Mater. 2021, 120, 111479.
  21. Zhang, Y.; Chen, H.X.; Duan, L.; Fan, J.B.; Ni, L.; Ji, V. A comparison study of the structural and mechanical properties of cubic, tetragonal, monoclinic, and three orthorhombic phases of ZrO2. J. Alloys Compd. 2018, 749, 283–292.
  22. Aksimentyeva, O.I.; Savchyn, V.P.; Dyakonov, V.P.; Piechota, S.; Horbenko, Y.Y.; Opainych, I.Y.; Demchenko, P.Y.; Popov, A.; Szymczak, H. Modification of Polymer-Magnetic Nanoparticles by Luminescent and Conducting Substances. Mol. Cryst. Liq. Cryst. 2014, 590, 35–42.
  23. Kim, S.-E.; Yoon, J.-K.; Shon, I.-J. Mechanochemical Synthesis and Rapid Consolidation of Nanostructured Nb-ZrO2 Composite. J. Nanosci. Nanotechnol. 2020, 20, 4253–4256.
  24. Shelyug, A.; Navrotsky, A. Thermodynamic stability of the fluorite phase in the CeO2− CaO− ZrO2 system. J. Nucl. Mater. 2019, 517, 80–85.
  25. Kumar, R.; Chauhan, V.; Gupta, D.; Upadhyay, S.; Ram, J.; Kumar, S. Advancement of High–k ZrO2 for Potential Applications: A Review. Indian J. Pure Appl. Phys. (IJPAP) 2021, 59, 811–826.
  26. Alekseeva, L.S.; Nokhrin, A.V.; Boldin, M.S.; Lantsev, E.A.; Orlova, A.I.; Chuvil’Deev, V.N.; Sakharov, N.V. Preparation of Fine-Grained CeO2–SiC Ceramics for Inert Fuel Matrices by Spark Plasma Sintering. Inorg. Mater. 2020, 56, 1307–1313.
  27. Hudák, I.; Skryja, P.; Bojanovský, J.; Jegla, Z.; Krňávek, M. The Effect of Inert Fuel Compounds on Flame Characteristics. Energies 2021, 15, 262.
  28. Mareš, K.V.; John, J. Recycling of isotopically modified molybdenum from irradiated CerMet nuclear fuel: Part 1—concept design and assessment. J. Radioanal. Nucl. Chem. 2019, 320, 227–233.
  29. Baron, R.; Wejrzanowski, T.; Milewski, J.; Szablowski, L.; Szczęśniak, A.; Fung, K.-Z. Manufacturing of γ -LiAlO2 matrix for molten carbonate fuel cell by high-energy milling. Int. J. Hydrogen Energy 2018, 43, 6696–6700.
  30. Sharma, S.K.; Grover, V.; Tyagi, A.; Avasthi, D.; Singh, U.; Kulriya, P. Probing the temperature effects in the radiation stability of Nd2Zr2O7 pyrochlore under swift ion irradiation. Materialia 2019, 6, 100317.
  31. Mistarihi, Q.M.; Park, W.; Nam, K.; Yahya, M.-S.; Kim, Y.; Ryu, H.J. Fabrication of oxide pellets containing lumped Gd2O3 using Y2O3-stabilized ZrO2 for burnable absorber fuel applications. Int. J. Energy Res. 2018, 42, 2141–2151.
  32. Wen, T.; Yuan, L.; Tian, C.; Yan, Z.; Liu, Z.; Yu, J. Electrical conductivity behavior of ZrO2-MgO-Y2O3 ceramic: Effect of heat treatment temperature. J. Aust. Ceram. Soc. 2022, 1–7.
  33. Marek, I.O.; Dudnik, O.V.; Korniy, S.A.; Red’ko, V.P.; Danilenko, M.I.; Ruban, O.K. Effect of Heat Treatment in the Temperature Range 400−1300 °C on the Properties of Nanocrystalline ZrO2− Y2O3− CeO2 Powders. Powder Metall. Met. Ceram. 2022, 60, 1–11.
More