Oxidation and anion lattice defect signatures of hypostoichiometric lanthanide-doped UO2
Introduction
Uranium dioxide nuclear fuel that has undergone fission is the most chemically complex material known, at first containing hundreds of radionuclides with a range of half-lives [1,2]. The UO2 structure is able to incorporate certain of these fission products, predominantly the lanthanides, as well as transuranic elements produced by neutron capture reactions. However, as a nuclear fuel package ages, its chemical composition, radiation field, and emitted heat evolves dynamically. The gaseous fission products incompatible with the UO2 structure become confined to bubbles distributed between fuel grains which eventually escape through cracks and cladding, while other elements exsolve as metallic particles and oxide phases, producing complex chemical and microstructural features that have been nearly wholly reproduced in the laboratory (i.e., as SIMFUEL) [[3], [4], [5]]. Understanding the stability and alteration behavior of used nuclear fuel (UNF) remains one of the greatest challenges to ensure safe reuse and long-term disposal, as well as environmentally sound stewardship of the legacy and future UNF generated by nuclear activities.
As a result of their high fission yield, lanthanides (Ln) are among the most abundant, stable and miscible elements found in UNF [6,7]. Although these and other fission products compatible within the UO2 structure can stabilize it from oxidation, various defects are introduced to the cation and anion sublattices (hypostoichiometry) due to their different charges and sizes compared to UIV, which can force local redox reactions to satisfy charge balance, chiefly, via UIV → UV [8]. Stable configurations occur for hypostoichiometric UO2-x up to x = 0.34–0.35 [9,10], with other experiments revealing that oxygen vacancies are stabilized by lanthanide dopants [[11], [12], [13]], and are highly mobile and randomly distributed [14,15] in contrast to the Willis-type cuboctahedral clustering of interstitial O preferred in hyperstochiometric UO2+x [[16], [17], [18]]. Used fuel is known to have different oxidation and dissolution characteristics than fresh fuel due to the complexity of its fission product inventory [19], and many studies have shown these effects are dictated by the size and charge of the substituting elements [9,[20], [21], [22], [23], [24], [25]]. In general, trivalent cation dopants slow UO2 oxidation by hindering U3O8 formation. As described by Desgranges et al. (2011), a random distribution of trivalent dopants limits the formation of cuboctahedra, preventing the necessary shear-transformation of the crumpled sheets in α-U4O9 into the U3O8-type sheet structure [26].
Using a coprecipitation method we have synthesized and sintered a series of UO2 pellets containing low concentrations (1 and 5 at%) of homogeneously distributed lanthanide elements (Ce, Nd, and Yb) with hypostoichiometric oxygen content. By combining powder X-ray diffraction (PXRD) and Raman spectroscopic analysis with two laser wavelengths, we identify the effect of lanthanide size on the hypostoichiometric anion defect structures and detail how their spectroscopic trends and signatures change with oxidation, as monitored during thermogravimetric analysis (TGA) and differential scanning calorimetry (DSC) experiments. A majority of the data presented here for Nd- and Yb-doped UO2-x, as far as we know, have not yet appeared in the literature. Furthermore, we observe a profound effect of delayed oxidation in 5 at% Yb doped UO2-x, and compare these results to previous studies of Ln-doped UO2 with small trivalent dopants, Y, Lu, and Gd.
Section snippets
Sample synthesis
Ln-doped UO2 samples were prepared via coprecipitation with ammonium diuranate (ADU). To an aqueous solution of 0.5 M uranyl nitrate (International Bio-Analytical Industries, Inc.) was added 1 at% and 5 at% (metals basis) of the respective dopant-nitrate crystals. Ytterbium(III) nitrate hexahydrate, cerium(III) nitrate hexahydrate, and neodymium(III) nitrate hexahydrate were obtained from Alfa Aesar with 99.99% purity. Concentrated ammonium hydroxide was added slowly to the dopant-uranyl
PXRD
Powder X-ray diffraction was used to determine phase purity after synthesis and to obtain the unit cell parameters of freshly sintered pure UO2 and (U1-yMy)O2-x samples, M = Ce, Nd, Yb. The pure pellet and all pellets synthesized with lanthanide dopants are composed of single-phase solid solutions of Ln2O3-UO2 with the fluorite-type structure. The cell parameters from Rietveld refinement with whole pattern fitting are presented in Table 1, along with the measured anion and cation contents from
Conclusions
A series of (U1-yMy)O2-x samples with M = Ce, Nd, and Yb (1 and 5 at%) have been synthesized, sintered, and analyzed by XRD, Raman spectroscopy, electron microprobe, and TGA/DSC. In agreement with prior studies, our PXRD data show that an increase in lanthanide dopant concentration caused a contraction of the UO2 structure due to the cooperative effects of smaller cation size and shorter U/Ln–O bonds caused by hypostoichiometry, indicated by the Rietveld-refined lattice parameters. Oxygen
Author contributions
Travis Olds: Supervision, Investigation, Formal analysis, Conceptualization, Methodology, Writing – Original draft preparation, Software
Samuel Karcher: Investigation, Formal analysis Data curation, Visualization, Writing – Reviewing and Editing
Kyle Kriegsman: Data curation, Software, Methodology
Xiaofeng Guo: Supervision, Methodology, Writing – Reviewing and Editing
John McCloy: Project administration, Supervision, Funding acquisition, Writing – Original Draft, Writing – Review & Editing
Declaration of competing interest
The authors declare that they have no known competing financial interests or personal relationships that could have appeared to influence the work reported in this paper.
Acknowledgements
This research was funded by the U.S. Department of Energy in support of the Nuclear Energy University Program – Used Nuclear Fuel Disposition program, award # DE-NE0008689. The authors also thank the US Department of Energy Office of River Protection for funding through 89304017CEM000001 for purchase of the Raman microscope system used in this work. K.W.K and X.G acknowledge the institutional funds from the Department of Chemistry at WSU and the facility support from the Nuclear Science Center
References (50)
- et al.
Microstructural features of SIMFUEL — simulated high-burnup UO2-based nuclear fuel
J. Nucl. Mater.
(1991) - et al.
Processing and microstructural characterisation of a UO2-based ceramic for disposal studies on spent AGR fuel
J. Nucl. Mater.
(2015) Thermodynamics of fluorite type solid solutions containing plutonium, lanthanide elements or alkaline earth metals in uranium dioxide host lattices
J. Nucl. Mater.
(1988)- et al.
Stabilization of UO2
J. Inorg. Nucl. Chem.
(1961) - et al.
Oxygen potential of hypo-stoichiometric Lu-doped UO2
J. Nucl. Mater.
(2008) - et al.
Oxygen potential of hypo-stoichiometric La-doped UO2
J. Nucl. Mater.
(2011) - et al.
Oxygen potentials of (U, Gd)O2 ± x solid solutions in the temperature range 1000–1500°C
J. Nucl. Mater.
(1983) - et al.
Assessment of structures and stabilities of defect clusters and surface energies predicted by nine interatomic potentials for UO2
J. Nucl. Mater.
(2013) - et al.
Computer simulation of defect clusters in UO2 and their dependence on composition
J. Nucl. Mater.
(2015) - et al.
Effect of fission products on air-oxidation of LWR spent fuel
J. Nucl. Mater.
(1993)
Effect of Ce doping on UO2 structure and its oxidation behavior
J. Nucl. Mater.
Effect of a trivalent dopant, Gd3+, on the oxidation of uranium dioxide
J. Nucl. Mater.
Thermochemistry of rare earth doped uranium oxides LnxU1−xO2−0.5x+y (Ln = La, Y, Nd)
J. Nucl. Mater.
On the relation between lattice parameter and O/M ratio for uranium dioxide-trivalent rare earth oxide solid solution
J. Nucl. Mater.
Synthesis and characterization of Th1−xLnxO2−x/2 mixed-oxides
Mater. Res. Bull.
Electronic transitions, crystal field effects and phonons in UO2
Phys. Rep.
Quantification of irradiation-induced defects in UO2 using Raman and positron annihilation spectroscopies
Acta Mater.
The reaction of water on polycrystalline UO2: pathways to surface and bulk oxidation
J. Nucl. Mater.
Raman spectra of stoichiometric and hyperstoichiometric uranium dioxide
J. Nucl. Mater.
Nuclear fuel in a reactor accident
Science
Spent Nuclear Fuel
Elements
Preparation and characterization of UO2-based AGR SIMFuel
MRS Proceedings
The stability of fission products in uranium dioxide
Philos. Trans. Phys. Sci. Eng.
Peculiar behavior of (U,Am)O2−δ compounds for high americium contents evidenced by XRD, XAS, and Raman spectroscopy
Inorg. Chem.
Defect structure and the phase diagram of uranium dioxide
High Temp.
Cited by (28)
Impact of fission product (Ce, Sn, Sr, Se) oxides on UO<inf>2</inf> oxidation to U<inf>3</inf>O<inf>8</inf>
2024, Progress in Nuclear EnergyInfluence of Nd doping on the structural and electrochemical properties of uranium dioxide
2024, Journal of Nuclear MaterialsThe effect of cerium, neodymium, and ytterbium doping on UO<inf>2</inf> dissolution
2024, Journal of Nuclear MaterialsOxidation of accident tolerant fuels models based on Cr-doped UO<inf>2</inf> for the safety of nuclear storage facilities
2023, Journal of Nuclear MaterialsEnergetics of oxidation and formation of uranium monocarbide
2023, Journal of Nuclear MaterialsThermal air oxidation of UO2: Joint effect of precursor's nature and particle size distribution
2023, Progress in Nuclear Energy