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Exploring the impact of temperature and oxygen partial pressure on the spent nuclear fuel oxidation during its dry management.

Authors :
Milena-Pérez A
Bonales LJ
Rodríguez-Villagra N
Galán H
Source :
Scientific reports [Sci Rep] 2023 Feb 03; Vol. 13 (1), pp. 1966. Date of Electronic Publication: 2023 Feb 03.
Publication Year :
2023

Abstract

The management of Spent Nuclear Fuel (SNF) comprises different stages in which security is demonstrated. Nevertheless, fundamental research can lead to other design options that must be considered. Currently, one of the focuses is the dry interim storage option, as the shortest-term solution until final repositories are available. During this stage, one concern is the oxidation of the fuel. If UO <subscript>2</subscript> (SNF matrix) is exposed to air at high-enough temperature, formation of U <subscript>3</subscript> O <subscript>8</subscript> takes place. The larger volume of this phase could entail stresses on the SNF clad, which is the first barrier to prevent radioactive material release. It is known that this oxidation is a temperature-dependent reaction and ensuring an inert atmosphere discards any effect during SNF dry management. However, at what extent temperature and oxygen concentration would have an impact on the U <subscript>3</subscript> O <subscript>8</subscript> formation is not established, being the available experimental data very scarce. We follow this oxidation in representative ranges of temperature and oxygen concentration of dry storage facilities by using in-situ Raman spectroscopy. The results show that temperature is a more-affecting factor than the oxygen concentration at the studied conditions. Therefore, efforts to limit temperatures would yield more benefits in preserving fuel matrix integrity.<br /> (© 2023. The Author(s).)

Details

Language :
English
ISSN :
2045-2322
Volume :
13
Issue :
1
Database :
MEDLINE
Journal :
Scientific reports
Publication Type :
Academic Journal
Accession number :
36737473
Full Text :
https://doi.org/10.1038/s41598-023-29265-w