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Fabrication of uranium–americium mixed oxide pellet from microsphere precursors: Application of CRMP process

Authors :
E. Remy
I. Jobelin
Thibaud Delahaye
Sébastien Picart
I. Bisel
André Ayral
Denis Horlait
Philippe Blanchart
Florent Lebreton
EDF R&D (EDF R&D)
EDF (EDF)
CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN))
Commissariat à l'énergie atomique et aux énergies alternatives (CEA)
Département de recherche sur les procédés pour la mine et le recyclage du combustible (DMRC)
Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)
Groupe d'Etudes des Matériaux Hétérogènes (GEMH)
Université de Limoges (UNILIM)-Institut des Procédés Appliqués aux Matériaux (IPAM)
Université de Limoges (UNILIM)-Université de Limoges (UNILIM)
Institut Européen des membranes (IEM)
Université Montpellier 2 - Sciences et Techniques (UM2)-Ecole Nationale Supérieure de Chimie de Montpellier (ENSCM)-Institut de Chimie du CNRS (INC)-Centre National de la Recherche Scientifique (CNRS)
Centre National de la Recherche Scientifique (CNRS)-Ecole Nationale Supérieure de Chimie de Montpellier (ENSCM)-Université Montpellier 2 - Sciences et Techniques (UM2)-Institut de Chimie du CNRS (INC)-Université de Montpellier (UM)
Source :
Journal of Nuclear Materials, Journal of Nuclear Materials, 2014, 453 (1-3), pp.214-219. ⟨10.1016/j.jnucmat.2014.06.048⟩, Journal of Nuclear Materials, Elsevier, 2014, 453 (1-3), pp.214-219. ⟨10.1016/j.jnucmat.2014.06.048⟩
Publication Year :
2014
Publisher :
HAL CCSD, 2014.

Abstract

Mixed uranium–americium oxides are one of the materials envisaged for Americium Bearing Blankets dedicated to transmutation in fast neutron reactors. Recently, several processes have been developed in order to validate fabrication flowchart in terms of material specifications such as density and homogeneity but also to suggest simplifications for lowering industrial costs and hazards linked to dust generation of highly contaminating and irradiating compounds. This study deals with the application of an innovative route using mixed oxide microspheres obtained from metal loaded resin bead calcination, called Calcined Resin Microsphere Pelletization (CRMP). The synthesis of mixed oxide microsphere precursor of U 0.9 Am 0.1 O 2± δ is described as well as its characterisation. The use of this free-flowing precursor allows the pressing and sintering of one pellet of U 0.9 Am 0.1 O 2± δ . The ceramic obtained was characterised and results showed that its microstructure is dense and homogeneous and its density attains 95% of the theoretical density. This study validates the scientific feasibility of the CRMP process applied to the fabrication of uranium and americium-containing materials.

Details

Language :
English
ISSN :
00223115
Database :
OpenAIRE
Journal :
Journal of Nuclear Materials, Journal of Nuclear Materials, 2014, 453 (1-3), pp.214-219. ⟨10.1016/j.jnucmat.2014.06.048⟩, Journal of Nuclear Materials, Elsevier, 2014, 453 (1-3), pp.214-219. ⟨10.1016/j.jnucmat.2014.06.048⟩
Accession number :
edsair.doi.dedup.....2c8186fe97001ef5fc513ed15c809510
Full Text :
https://doi.org/10.1016/j.jnucmat.2014.06.048⟩