Development of UO2/PuO2 dispersed in uranium matrix CERMET fuel system for fast reactors

• Published in: Journal of nuclear materials 2012-08, Vol.427 (1-3), p.12-17
• Main Authors: Sinha, V.P., Hegde, P.V., Prasad, G.J., Pal, S., Mishra, G.P.
• Format: Article
• Language: English
• Subjects: Applied sciences; Cermets; Controled nuclear fusion plants; Dispersion; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fission nuclear power plants; Fuels; Installations for energy generation and conversion: thermal and electrical energy; Nuclear engineering; Nuclear fuels; Nuclear power generation; Nuclear reactor components; Nuclear reactors; Pellets; Preparation and processing of nuclear fuels; Uranium
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/j.jnucmat.2012.04.008

CERMET fuel with either PuO2 or enriched UO2 dispersed in uranium metal matrix has a strong potential of becoming a fuel for the liquid metal cooled fast breeder reactors (LMR’s). In fact it may act as a bridge between the advantages and disadvantages associated with the two extremes of fuel systems (i.e. ceramic fuel and metallic fuel) for fast reactors. At Bhabha Atomic Research Centre (BARC), R & D efforts are on to develop this CERMET fuel by powder metallurgy route. This paper describes the development of flow sheet for preparation of UO2 dispersed in uranium metal matrix pellets for three different compositions i.e. U–20wt%UO2, U–25wt%UO2 and U–30wt%UO2. It was found that the sintered pellets were having excellent integrity and their linear mass was higher than that of carbide fuel pellets used in Fast Breeder Test Reactor programme (FBTR) in India. The pellets were characterized by X-ray diffraction (XRD) technique for phase analysis and lattice parameter determination. The optical microstructures were developed and reported for all the three different U–UO2 compositions.