journal article·2025-10Open access

Optical dilatometry and sintering studies of Cr2O3-doped UO2

Sarah Vallely, Ritesh Mohun, David W. Williams, P. John Thomas, Mattias Puide, David T. Goddard, William E. Lee, Simon C. Middleburgh

Abstract

Optical dilatometry has been used to study the sintering behaviour of Cr 2 O 3 -doped UO 2 and such observations have been compared to undoped UO 2 , enabling a visual and measurable comparison of their behaviour during this important manufacturing step. Sintering UO 2 and Cr 2 O 3 -doped UO 2 pellets at different temperatures allowed for grain nucleation and growth to be assessed. Optical dilatometry was implemented to visually assess differences in the densification of UO 2 and Cr 2 O 3 -doped UO 2 . The rate of sintering and extent of shrinkage was found to be higher for the doped pellet, with the Cr 2 O 3 -doped pellet decreasing in volume by ∼40 %, compared to only ∼20 % for the undoped pellet. The temperature at which shrinkage commenced was also approximately 100 – 200 °C lower for the doped sample than for the undoped variant. This indicates that there is a difference between the sintering processes of the two systems. The possible contribution of the CrUO 4 secondary phase to large grain growth has also been examined through Differential Scanning Calorimetry (DSC) in reducing conditions. A change occurring at approximately 1250 °C for CrUO 4 was observed. This temperature corresponds to the end of shrinkage and start of grain growth for Cr 2 O 3 -doped UO 2 pellets, as shown in the optical dilatometry experiments, which could be indicative of the commencement of the large-grain growth process.
Source: openalex_inverted_index · Quality: baseline

Research context

OpenAlex topics: Nuclear Materials and Properties · Radioactive element chemistry and processing · Nuclear materials and radiation effects

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (33)

Show source-provided references
1. Fission gas release and swelling in UO2 doped with Cr2O310.1016/0022-3115(80)90272-X ↗
2. The effect of grain size on the swelling and gas release properties of uo2 during irradiation10.1016/0022-3115(74)90061-0 ↗
3. Advanced doped UO2 pellets in LWR applications10.1080/18811248.2006.9711184 ↗
4. Raman spectroscopy coupled to principal component analysis for studying UO2 nuclear fuels with different grain sizes due to the chromia addition10.1016/j.jnucmat.2020.152581 ↗
5. Factors governing microstructure development of Cr2O3-doped UO2 during sintering10.1016/S0022-3115(01)00626-2 ↗
6. On the solubility of chromium sesquioxide in uranium dioxide fuel10.1016/S0022-3115(02)01693-8 ↗
7. Solution of trivalent cations into uranium dioxide10.1016/j.jnucmat.2011.10.006 ↗
8. Thermodynamics of chromium in UO2 fuel: a solubility model10.1016/j.jnucmat.2013.12.021 ↗
9. Chromia doped UO2 fuel: investigation of the lattice parameter10.1016/j.jnucmat.2012.02.025 ↗
10. The +2 oxidation state of Cr incorporated into the crystal lattice of UO210.1038/s43246-020-0014-5 ↗
11. Cr2+ solid solution in UO2 evidenced by advanced spectroscopy10.1038/s42004-022-00784-3 ↗
12. Deconvoluting Cr states in Cr-doped UO2 nuclear fuels via bulk and single crystal spectroscopic studies10.1038/s41467-023-38109-0 ↗
13. Kardoulaki · 2019
14. Performance and properties evolution of near-term accident tolerant fuel: Cr-doped UO210.1016/j.jnucmat.2024.155022 ↗
15. Effect of step wise variation of oxygen potential during the isothermal sintering on the grain growth behavior in Cr2O3 doped UO2 pellets10.1016/j.jnucmat.2012.05.034 ↗
16. An evaluation of tri-valent oxide (Cr2O3) as a grain enlarging dopant for UO2 nuclear fuels fabricated under reducing environment10.1016/j.jnucmat.2021.153053 ↗
17. Barsoum · 2019
18. High temperature chromium volatilization from Cr2O3 powder and Cr2O3-doped UO2 pellets in reducing atmospheres10.1016/j.jnucmat.2012.01.001 ↗
19. Enrichment of chromium at grain boundaries in chromia doped UO210.1016/j.jnucmat.2023.154250 ↗
20. Formation of (Cr,Al)UO4 from doped UO2 and its influence on partition of soluble fission products10.1016/j.jnucmat.2013.07.038 ↗
21. Phase analysis of uranium oxides after reaction with stainless steel components and ZrO2 at high temperature by XRD, XAFS, and SEM/EDX10.1016/j.jnucmat.2019.03.055 ↗
22. The system Cr2O3 UO2 O210.1016/0022-1902(62)80104-3 ↗
23. H.R. Hoekstra, R.H. Marshall, Some uranium-transition element double oxides, in: Lanthanide/Actinide Chemistry, American Chemical Society, 1967: pp. 211–227. https://doi.org/10.1021/ba-1967-0071.ch016.10.1021/ba-1967-0071.ch016 ↗
24. High temperature dilatometry of simulated oxide nuclear fuel10.1088/1757-899X/130/1/012032 ↗
25. Densification behaviour of UO2 in six different atmospheres10.1016/S0022-3115(02)00934-0 ↗
26. Fabrication of UO2 Porous Pellets on a Scale of 30 kg-U/Batch at the PRIDE Facility10.1155/2015/376173 ↗
27. Microstructure of irradiated uranium dioxide10.1080/18811248.1967.9732711 ↗
28. ISO 643:2024, ISO (n.d.). https://www.iso.org/standard/82221.html (accessed January 19, 2025).
29. Diffusion in undoped and Cr-doped amorphous UO210.1016/j.jnucmat.2023.154270 ↗
30. Sintering crystalline solids. I. Intermediate and final state diffusion models10.1063/1.1736107 ↗
31. Chromium doped UO2-based ceramics: synthesis and characterization of model materials for modern nuclear fuels10.3390/ma14206160 ↗
32. Atomic parameters and magnetic structure of UCrO
33. Study on the relation between the crystal structure and thermal stability of FeUO4 and CrUO410.1016/j.jnucmat.2022.153847 ↗