Oxidation of the spent nuclear fuel matrix under interim storage conditions
The present thesis, entitled "Oxidation of the spent nuclear fuel matrix under interim storage conditions", deals with important aspects regarding the storage of nuclear fuel. Oxidation of spent nuclear fuel (SNF) with undetected cladding defects during dry storage might challenge its inte...
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| Tipo de recurso: | tesis doctoral |
| Fecha de publicación: | 2024 |
| País: | España |
| Institución: | Universidad Complutense de Madrid (UCM) |
| Repositorio: | Docta Complutense |
| Idioma: | inglés |
| OAI Identifier: | oai:docta.ucm.es:20.500.14352/103248 |
| Acceso en línea: | https://hdl.handle.net/20.500.14352/103248 |
| Access Level: | acceso abierto |
| Palabra clave: | 621.039.54(043.2) Combustibles nucleares Química 23 Química |
| Sumario: | The present thesis, entitled "Oxidation of the spent nuclear fuel matrix under interim storage conditions", deals with important aspects regarding the storage of nuclear fuel. Oxidation of spent nuclear fuel (SNF) with undetected cladding defects during dry storage might challenge its integrity if high oxygen-content uranium oxides (U3O8), characterised by a specific volume about 36% higher than UO2's, are formed. The formation of U3O8 could lead to failure propagation, and pulverisation of the fuel pellet. This could hinder the future retrieval of the fuel or even cause the release of radioactive material. As a consequence, an accurate characterisation of the processes involved under anticipated conditions is of utmost significance for nuclear safety, especially taking into account the foreseen lifetime extension of storage facilities of SNF... |
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