Effect of the oxidation front penetration on in-clad hydrogen migration
| dc.contributor.author | Feria, F. | |
| dc.contributor.author | Herranz, L.E. | |
| dc.date.accessioned | 2024-02-08T11:52:04Z | |
| dc.date.available | 2024-02-08T11:52:04Z | |
| dc.date.issued | 2018 | |
| dc.description | In LWR fuel claddings the embrittlement due to hydrogen precipitates (i.e., hydrides) is a degrading mechanism that concerns in nuclear safety, particularly in dry storage. A relevant factor is the radial distribution of the hydrogen absorbed, especially the hydride rim formed. Thus, a reliable assessment of fuel performance should account for hydrogen migration. Based on the current state of modelling of hydrogen dynamics in the cladding, a 1D radial model has been derived and coupled with the FRAPCON code. The model includes the effect of the oxidation front progression on in-clad hydrogen migration, based on experimental observations found (i.e., dissolution/diffusion/re-precipitation of the hydrogen in the matrix ahead of the oxidation front). A remarkable quantitative impact of this new contribution has been shown by analyzing the hydrogen profile across the cladding of several high burnup fuel scenarios (>60 GW d/tU); other potential contributions like thermodiffusion and diffusion in the hydride phase hardly make any difference. Comparisons against PIE measurements allow concluding that the model accuracy notably increases when the effect of the oxidation front is accounted for in the hydride rim formation. In spite of the promising results, further validation would be needed | es_ES |
| dc.description.abstract | El artículo se centra en un aspecto directamente relacionado con la seguridad nuclear: el mantenimiento de la integridad del combustible durante su irradiación en el reactor y, más concretamente, del recubrimiento metálico que separa los productos de fisión generados del resto de sistemas. Esto es, la denominada primera barrera de confinamiento de los reactores nucleares. La oxidación del combustible nuclear durante su vida en el reactor supone, entre otros aspectos, la absorción de una fracción del hidrógeno generado. Este proceso supone un empeoramiento de las propiedades mecánicas del combustible y la distribución del hidrógeno a través de la vaina de zircaloy es una variable de primera importancia | es_ES |
| dc.description.sponsorship | El trabajo descrito se realizó en el marco del proyecto ITAST, financiado por ENRESA | es_ES |
| dc.identifier.doi | http://dx.doi.org/10.1016/j.jnucmat.2018.01.011 | |
| dc.identifier.uri | https://hdl.handle.net/20.500.14855/2458 | |
| dc.language.iso | eng | es_ES |
| dc.publisher | Elsevier Ltd. | es_ES |
| dc.rights.accessRights | open access | es_ES |
| dc.subject | Clad oxidation | es_ES |
| dc.subject | hydrogen distribution | es_ES |
| dc.title | Effect of the oxidation front penetration on in-clad hydrogen migration | es_ES |
| dc.type | journal article | es_ES |
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