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

• Published in: Journal of nuclear materials Vol. 453; no. 1-3; pp. 214 - 219
• Main Authors: Remy, E., Picart, S., Delahaye, T., Jobelin, I., Lebreton, F., Horlait, D., Bisel, I., Blanchart, P., Ayral, A.
• Format: Journal Article
• Language: English
• Published: Elsevier B.V 01.10.2014; Elsevier
• Subjects: Chemical Sciences; Condensed Matter; Cristallography; Density; Material chemistry; Materials Science; Microspheres; Mixed oxides; Nuclear engineering; Pellets; Physics; Polymers; Precursors; Resins
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/j.jnucmat.2014.06.048

[Display omitted] •Dust free process for (U,Am)O2 transmutation target fabrication.•Synthesis of U0.9Am0.1O2 mixed oxide microspheres from ion exchange resin.•Fabrication of dense U0.9Am0.1O2 pellet with 95% TD from mixed oxide microspheres. 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 U0.9Am0.1O2±δ is described as well as its characterisation. The use of this free-flowing precursor allows the pressing and sintering of one pellet of U0.9Am0.1O2±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.