Uranium (III) precipitation in molten ...
Type de document :
Article dans une revue scientifique
URL permanente :
Titre :
Uranium (III) precipitation in molten chloride by wet argon sparging
Auteur(s) :
Vigier, Jean-François [Auteur]
Laplace, Annabelle [Auteur]
Renard, Catherine [Auteur]
Miguirditchian, Manuel [Auteur]
Abraham, Francis [Auteur]
Unité de Catalyse et Chimie du Solide - UMR 8181 [UCCS]
Unité de Catalyse et Chimie du Solide (UCCS) - UMR 8181
Laplace, Annabelle [Auteur]
Renard, Catherine [Auteur]
Miguirditchian, Manuel [Auteur]
Abraham, Francis [Auteur]
Unité de Catalyse et Chimie du Solide - UMR 8181 [UCCS]
Unité de Catalyse et Chimie du Solide (UCCS) - UMR 8181
Titre de la revue :
Journal of Nuclear Materials
Numéro :
474
Pagination :
19-27
Date de publication :
2016-06
Discipline(s) HAL :
Chimie/Matériaux
Résumé en anglais : [en]
In the context of pyrochemical processes for nuclear fuel treatment, the precipitation of uranium (III) in molten salt LiCl-CaCl2 (30–70 mol%) at 705 °C is studied. First, this molten chloride is characterized with the ...
Lire la suite >In the context of pyrochemical processes for nuclear fuel treatment, the precipitation of uranium (III) in molten salt LiCl-CaCl2 (30–70 mol%) at 705 °C is studied. First, this molten chloride is characterized with the determination of the water dissociation constant. With a value of 10−4.0, the salt has oxoacid properties. Then, the uranium (III) precipitation using wet argon sparging is studied. The salt is prepared using UCl3 precursor. At the end of the precipitation, the salt is totally free of solubilized uranium. The main part is converted into UO2 powder but some uranium is lost during the process due to the volatility of uranium chloride. The main impurity of the resulting powder is calcium. The consequences of oxidative and reductive conditions on precipitation are studied. Finally, coprecipitation of uranium (III) and neodymium (III) is studied, showing a higher sensitivity of uranium (III) than neodymium (III) to precipitation.Lire moins >
Lire la suite >In the context of pyrochemical processes for nuclear fuel treatment, the precipitation of uranium (III) in molten salt LiCl-CaCl2 (30–70 mol%) at 705 °C is studied. First, this molten chloride is characterized with the determination of the water dissociation constant. With a value of 10−4.0, the salt has oxoacid properties. Then, the uranium (III) precipitation using wet argon sparging is studied. The salt is prepared using UCl3 precursor. At the end of the precipitation, the salt is totally free of solubilized uranium. The main part is converted into UO2 powder but some uranium is lost during the process due to the volatility of uranium chloride. The main impurity of the resulting powder is calcium. The consequences of oxidative and reductive conditions on precipitation are studied. Finally, coprecipitation of uranium (III) and neodymium (III) is studied, showing a higher sensitivity of uranium (III) than neodymium (III) to precipitation.Lire moins >
Langue :
Anglais
Audience :
Internationale
Vulgarisation :
Non
Établissement(s) :
ENSCL
CNRS
Centrale Lille
Univ. Artois
Université de Lille
CNRS
Centrale Lille
Univ. Artois
Université de Lille
Collections :
Équipe(s) de recherche :
Chimie du solide et matériaux du nucléaire
Chimie, matériaux et procédés pour un nucléaire durable (CIMEND)
Chimie, matériaux et procédés pour un nucléaire durable (CIMEND)
Date de dépôt :
2019-09-25T14:04:29Z