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

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 f...

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Autores principales: Milena-Pérez, A., Bonales, L. J., Rodríguez-Villagra, N., Galán, H.
Formato: Online Artículo Texto
Lenguaje:English
Publicado: Nature Publishing Group UK 2023
Materias:
Acceso en línea:https://www.ncbi.nlm.nih.gov/pmc/articles/PMC9898559/
https://www.ncbi.nlm.nih.gov/pubmed/36737473
http://dx.doi.org/10.1038/s41598-023-29265-w
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author Milena-Pérez, A.
Bonales, L. J.
Rodríguez-Villagra, N.
Galán, H.
author_facet Milena-Pérez, A.
Bonales, L. J.
Rodríguez-Villagra, N.
Galán, H.
author_sort Milena-Pérez, A.
collection PubMed
description 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(2) (SNF matrix) is exposed to air at high-enough temperature, formation of U(3)O(8) 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(3)O(8) 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.
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spelling pubmed-98985592023-02-05 Exploring the impact of temperature and oxygen partial pressure on the spent nuclear fuel oxidation during its dry management Milena-Pérez, A. Bonales, L. J. Rodríguez-Villagra, N. Galán, H. Sci Rep Article 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(2) (SNF matrix) is exposed to air at high-enough temperature, formation of U(3)O(8) 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(3)O(8) 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. Nature Publishing Group UK 2023-02-03 /pmc/articles/PMC9898559/ /pubmed/36737473 http://dx.doi.org/10.1038/s41598-023-29265-w Text en © The Author(s) 2023 https://creativecommons.org/licenses/by/4.0/Open Access This article is licensed under a Creative Commons Attribution 4.0 International License, which permits use, sharing, adaptation, distribution and reproduction in any medium or format, as long as you give appropriate credit to the original author(s) and the source, provide a link to the Creative Commons licence, and indicate if changes were made. The images or other third party material in this article are included in the article's Creative Commons licence, unless indicated otherwise in a credit line to the material. If material is not included in the article's Creative Commons licence and your intended use is not permitted by statutory regulation or exceeds the permitted use, you will need to obtain permission directly from the copyright holder. To view a copy of this licence, visit http://creativecommons.org/licenses/by/4.0/ (https://creativecommons.org/licenses/by/4.0/) .
spellingShingle Article
Milena-Pérez, A.
Bonales, L. J.
Rodríguez-Villagra, N.
Galán, H.
Exploring the impact of temperature and oxygen partial pressure on the spent nuclear fuel oxidation during its dry management
title Exploring the impact of temperature and oxygen partial pressure on the spent nuclear fuel oxidation during its dry management
title_full Exploring the impact of temperature and oxygen partial pressure on the spent nuclear fuel oxidation during its dry management
title_fullStr Exploring the impact of temperature and oxygen partial pressure on the spent nuclear fuel oxidation during its dry management
title_full_unstemmed Exploring the impact of temperature and oxygen partial pressure on the spent nuclear fuel oxidation during its dry management
title_short Exploring the impact of temperature and oxygen partial pressure on the spent nuclear fuel oxidation during its dry management
title_sort exploring the impact of temperature and oxygen partial pressure on the spent nuclear fuel oxidation during its dry management
topic Article
url https://www.ncbi.nlm.nih.gov/pmc/articles/PMC9898559/
https://www.ncbi.nlm.nih.gov/pubmed/36737473
http://dx.doi.org/10.1038/s41598-023-29265-w
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