Résumé
A part of fourth generation of nuclear power plant’s aim is to recycle plutonium, preserve uranium supplies and produce homogenous plutonium-rich fuels. Therefore, various routes of nitrates to oxides conversion are studied ; within them Solution Combustion Synthesis can be used to synthesize various actinides oxides with a low energy supply and a powder characteristics control. The first step is to obtain a network gel dissolving nitrates precursors (surrogates or actinides) and organic fuel in distilled water and deshydrate. The sol-gel reaction can be obtain in a furnace or on hot plate, according to the powder characteristics wanted. Various fuel and nitrates, fuel-to-nitrate ratio, heating modes and crucible geometry were studied in order to obtain a powder which characteristics are compatible with pellet shaping and sintering. These parameters seem to allow to control actinide oxidation state to some extent (uranium/glycine system for example). It is also possible to obtain powders with low carbon content, high specific surface and a controlled oxydation step without any calcination step. Before igntion, precursors gel were studied by IR and Raman spectroscopy. Ignition was studied in TG-DTA and final oxides were characterized by XDR, BET, SEM, carbon content.