Characterization of the Corrosion Layer onto Stoichiometric Uranium Oxide Created by Liquid Sodium toward a Kinetic Modeling
We studied two scenarios of the interaction between uranium dioxide and liquid sodium in conditions similar to in-reactor conditions for defective fuel pins in contact with sodium: scenario 1 with a constant oxygen potential and scenario 2 with a given starting amount of oxygen. The samples after interaction were characterized by X-ray diffraction, grazing incidence X-ray diffraction, scanning electron microscopy, energy-dispersive X-ray spectroscopy, and transmission electron microscopy. The experimental results show that the reaction between liquid sodium containing dissolved oxygen and stoichiometric UO<sub>2</sub> leads to the production of a corrosion layer, which develops uniformly on the surface without any dependence upon UO<sub>2</sub> grain orientation or grain size. Depending on the oxygen feeding, the crystallographic phases of the corrosion layer change. If trisodium uranate Na<sub>3</sub>UO<sub>4</sub> is the only phase obtained in scenario 2, for the first time, it is observed that both Na<sub>3</sub>UO<sub>4</sub> and NaUO<sub>3</sub> phases are formed within the corrosion layer in scenario 1.
Authors
- Loïc Favergeon (ORCID: https://orcid.org/0000-0001-8181-867X)
- L. Desgranges (ORCID: https://orcid.org/0000-0002-6327-3482)
- Concettina Andrello
- Daniel Freis
Institutions
- Université Claude Bernard Lyon 1 (FR)
- Centre National de la Recherche Scientifique (FR)
- European Commission (BE)
- Mines Saint-Étienne (FR)
- CEA Cadarache (FR)
Publication Details
- Journal
- Inorganic Chemistry
- Published
- 2025-04-17
- DOI
- https://doi.org/10.1021/acs.inorgchem.5c00242
- Primary Topic
- Radioactive element chemistry and processing
- Type
- article
- Field-Weighted Citation Impact
- 0.00