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Radiolytic corrosion of uranium dioxide induced by He2+ localized irradiation of water: Role of the produced H2O2 distance

Authors :
Ferid Haddad
Johan Vandenborre
Ali Traboulsi
G. Blain
Bernard Humbert
Massoud Fattahi
Laboratoire SUBATECH Nantes (SUBATECH)
Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université de Nantes (UN)-Mines Nantes (Mines Nantes)
Institut des Matériaux Jean Rouxel (IMN)
Université de Nantes - UFR des Sciences et des Techniques (UN UFR ST)
Université de Nantes (UN)-Université de Nantes (UN)-Centre National de la Recherche Scientifique (CNRS)-Institut de Chimie du CNRS (INC)-Ecole Polytechnique de l'Université de Nantes (EPUN)
Université de Nantes (UN)-Université de Nantes (UN)
Cyclotron ARRONAX
Source :
Journal of Nuclear Materials, Journal of Nuclear Materials, Elsevier, 2015, 467, pp.832-839. ⟨10.1016/j.jnucmat.2015.10.061⟩
Publication Year :
2015
Publisher :
Elsevier BV, 2015.

Abstract

The short-range (few μm in water) of the α-emitting from the spent fuel involves that the radiolytic corrosion of this kind of sample occurs at the solid/solution interface. In order to establish the role of localization of H 2 O 2 species produced by the He 2+ particle beam in water from the surface, we perform UO 2 radiolytic corrosion experiment with different distance between H 2 O 2 production area and UO 2 surface. Then, in this work, the radiolytic corrosion of UO 2 particles by oxidative species produced by 4 He 2+ radiolysis of water was investigated in open to air atmosphere. The dose rate, the localization of H 2 O 2 produced by water radiolysis and the grain boundaries present on the surface of the particles were investigated. UO 2 corrosion was investigated by in situ (during irradiation) characterization of the solid surface, analysis of H 2 O 2 produced by water radiolysis and quantification of the uranium species released into the solution during irradiation. Characterization of the UO 2 particles, surface and volume, was realized by Raman spectroscopy. UV–vis spectrophotometry was used to monitor H 2 O 2 produced by water radiolysis and in parallel the soluble uranium species released into the solution were quantified by inductively coupled plasma mass spectrometry. During the He 2+ irradiation of ultra-pure water in contact with the UO 2 particles, metastudtite phase was formed on the solid surface indicating an oxidation process of the particles by the oxidative species produced by water radiolysis. This oxidation occurred essentially on the grain boundaries and was accompanied by migration of soluble uranium species (U(VI)) into the irradiated solution. Closer to the surface the localization of H 2 O 2 formation, higher the UO 2 oxidation process occurs, whereas the dose rate had no effect on it. Simultaneously, closer to the surface the localization of H 2 O 2 formation lower the H 2 O 2 concentration measured in solution. Moreover, the metastudtite was the only secondary phase formed whatever the irradiation conditions. One hypothesis proposed in this work is the H 2 O 2 may undergo a dismutation reaction leading to the formation of OH at the UO 2 surface.

Details

ISSN :
00223115
Volume :
467
Database :
OpenAIRE
Journal :
Journal of Nuclear Materials
Accession number :
edsair.doi.dedup.....926ea806223b7fdc163073d112bf161c
Full Text :
https://doi.org/10.1016/j.jnucmat.2015.10.061