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.

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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
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article

Characterization of the Corrosion Layer onto Stoichiometric Uranium Oxide Created by Liquid Sodium toward a Kinetic Modeling

Loïc Favergeon, L. Desgranges, Concettina Andrello, Daniel Freis
Inorganic Chemistry
Radioactive element chemistry and processing
article

Characterization of the Corrosion Layer onto Stoichiometric Uranium Oxide Created by Liquid Sodium toward a Kinetic Modeling

Loïc Favergeon, L. Desgranges, Concettina Andrello, Daniel Freis
article en

Abstract

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.

Inorganic ChemistryVol. 64(16)
Université Claude Bernard Lyon 1 (FR), Centre National de la Recherche Scientifique (FR), European Commission (BE), Mines Saint-Étienne (FR), CEA Cadarache (FR)
Openalex Percentile: Top 93%
Radioactive element chemistry and processing
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Characterization of the Corrosion Layer onto Stoichiometric Uranium Oxide Created by Liquid Sodium toward a Kinetic Modeling — Loïc Favergeon, L. Desgranges, et al. · Inorganic Chemistry (2025) | TGRS Research Map | TGRS