Dopant effect on the spent fuel matrix dissolution of new advanced fuels: Cr-doped UO2 and Cr/Al-doped UO2

dc.contributor.authorRodríguez-Villagra, Nieves
dc.contributor.authorRiba, O.
dc.contributor.authorMilena-Pérez, Abel
dc.contributor.authorCobos, J.
dc.contributor.authorBonales, L.J.
dc.contributor.authorFernández-Carretero, S.
dc.contributor.authorCoene, E.
dc.contributor.authorSilva, O.
dc.contributor.authorDuro, L.
dc.date.accessioned2026-01-13T06:13:07Z
dc.date.available2026-01-13T06:13:07Z
dc.date.issued2022
dc.description.abstractTo improve the fundamental understanding of the processes controlling spent fuel alteration under deep geological conditions, the influence of dopants (Cr and Cr/Al) on UO 2 matrix stability is evaluated for “modern”types of light water reactor (LWR) fuels with additives. The uranium dissolution behavior of as-prepared 0.06 wt%Cr and 0.05 wt%Cr/0.02 wt%Al doped UO 2 pellets is studied in simplified ground- water containing 19 mM HCO 3 −in autoclaves under hydrogen atmosphere. Sintered disks were ex- posed to simulated highly carbonated conditions, representative of a repository scenario of water in- trusion after a hypothetical canister failure. The uranium concentration released was ∼10 −7 M for the 0.05 wt%Cr/0.02 wt%Al doped UO 2 pellet and ∼10 −6 M for 0.06 wt%Cr doped UO 2 pellets, after 170 days. The results indicate that the amount of dissolved uranium is slightly lower compared to previous studies in absence of a reductant gas phase, but clearly above the solubility of UO 2 (am, hyd). The initial mea- sured pH was 8.9 ±0.1, which gradually approached a constant value of ∼9.2 ±0.1. Solid characterization at the end of the dissolution experiment, by SEM, Raman spectroscopy and XRD shows that the surface of all pellets remains almost unaltered. The experimental results indicate a potential oxidative dissolution of UO 2 , which could be attributed to the presence/intrusion of dissolved oxygen in the prepared synthetic groundwater. In order to identify the mechanism of uranium release, the datasets from the batch experi- ments are simulated with a PHREEQC model previously calibrated with results of existing spent fuel UOx leaching experiments. The model includes the geochemical processes that are relevant for the studied experimental conditions: (i) non-oxidative dissolution of UO 2 , (ii) UO 2 oxidation with O 2 , (iii) dissolu- tion of U(VI) by carbonate water, (iv) reduction of oxidized U(VI) on the surface pellet by activated H 2 . The ability to activate the dissolved H 2 is studied by implementing a kinetically controlled process of H 2 activation on the Cr surface in the model.es_ES
dc.identifier.citationJ. Nuclear Mater., 568 (2022), Article 153880es_ES
dc.identifier.doihttps://doi.org/10.1016/j.jnucmat.2022.153880
dc.identifier.urihttps://hdl.handle.net/20.500.14855/5470
dc.language.isoenges_ES
dc.rights.accessRightsopen accesses_ES
dc.subjectUO2es_ES
dc.subjectDopinges_ES
dc.subjectLeaching experimentses_ES
dc.subjectChromiumes_ES
dc.titleDopant effect on the spent fuel matrix dissolution of new advanced fuels: Cr-doped UO2 and Cr/Al-doped UO2es_ES
dc.typejournal articlees_ES
dc.type.hasVersionAMes_ES

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2022 N. Rodríguez-Villagra, O. Riba, A. Milena-Pérez et al. Journal of Nuclear Materials 568 (2022) 153880.pdf
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