Pyro-chemistry assessment at CEA - Last experimental results

Conference · Sun Jul 01 00:00:00 EDT 2007

OSTI ID:20979622

Lacquement, J; Bourg, S; Boussier, H; Conocar, O; Laplace, A; Baron, P ^[1]; Grandjean, A ^[2]; Warin, D; Boullis, B ^[3]

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1. CEA/DEN/VRH/DRCP, Commissariat a l'Energie Atomique BP 17171, 30207 Bagnols-sur-Ceze Cedex (France)
2. CEA/DEN/VRH/DTCD, Commissariat a l'Energie Atomique BP 17171, 30207 Bagnols-sur-Ceze Cedex (France)
3. CEA/DEN/SAC/DDIN, Commissariat a l'Energie Atomique, BP 17171, 30207 Bagnols-sur-Ceze Cedex (France)

Initially assessed in the frame of the first French act on radioactive waste management (Dec. 91), the pyro-technology is now perceived by the Nuclear Energy Directorate of the Commissariat a l'Energie Atomique (CEA) as a potential alternative to hydrometallurgy in two applications: (i) reprocessing of irradiated targets or dedicated fuels used for the minor actinides transmutation, (ii) reprocessing of Generation IV spent nuclear fuels (e.g. carbide fuel proposed for Gas cooled Fast Reactor or oxide fuel proposed for Sodium Fast Reactor). The R and D program is now mainly focused on the latter application. This paper gives the last experimental results on actinides/fission products separation assessment in molten fluorides either by chemical reductive extraction or electrolysis. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 20979622
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDES
CARBIDES
CEA
ELECTROLYSIS
FAST REACTORS
FISSION PRODUCTS
FLUORIDES
MOLTEN SALTS
NUCLEAR FUELS
OXIDES
PYROCHEMICAL REPROCESSING
REDUCTIVE EXTRACTION
SPENT FUELS
TRANSMUTATION