Oxidation and anion lattice defect signatures of hypostoichiometric lanthanide-doped UO2

https://doi.org/10.1016/j.jnucmat.2019.151959Get rights and content

Highlights

  • Oxidation characteristics for hypostoichiometric Ln-doped UO2-x revealed.

  • Two Raman lasers provide spectrally selective information on UO2-x.

  • This is the first oxidation study on hypostoichiometric Yb-doped UO2-x.

  • Yb-doping strongly inhibits U3O8 formation by 180 °C relative to pure UO2.

  • New spectroscopic and oxidation signatures compared with prior studies of UO2-x.

Abstract

A series of sintered UO2 pellets doped with lanthanide (Ce, Nd, Yb) elements were investigated using powder X-ray diffraction, Raman spectroscopy, thermogravimetric analyses and differential scanning calorimetry. A combination of electron microprobe and thermogravimetric analyses, for oxygen content, enabled precise determination of the hypostoichiometry for lanthanide-doped samples at 1 and 5 atom percent. Two Raman laser wavelengths (785 and 455 nm) have afforded greater sensitivity to spectroscopic signatures of the phonon bands (1LO and 2LO) associated with oxidation of (U1-yMy)O2-x and the anion defects introduced by lanthanide substitution. Oxygen hypostoichiometry forces a reduction in the average coordination number surrounding (U,M) sites, which is compensated by a decrease in U–O bond length, and concomitantly the lattice parameter, consistent with the obtained Raman spectra. The evolution of O/M ratio up to (U1-yMy)O2 after oxidation was also examined using Raman spectroscopy, revealing that the ‘defect band’, including a component attributed to oxygen vacancies (∼540 cm−1) and the 1LO phonon (∼575 cm−1) increased in intensity with increasing dopant concentration and upon oxidation. The lanthanide dopants inhibited oxidation to U3O8, most prominently for Yb 5 at%, having been delayed by ∼180 °C. Thermogravimetric analyses reveal an early oxidation feature that may be related to influx of O to satisfy hypostoichiometry up to (U1-yMy)O2, possibly stabilizing a U4O9 or U3O7 intermediate, delaying oxidation to U3O8.

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

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