Modified Purex first-cycle extraction for neptunium recovery

Conference · Tue Jul 01 00:00:00 EDT 2008

OSTI ID:21230364

Dinh, Binh; Moisy, Philippe; Baron, Pascal; Calor, Jean-Noel; Espinoux, Denis; Lorrain, Brigitte; Benchikouhne-Ranchoux, Magali ^[1]

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1. Departement de radiochimie et procedes, Commissariat a l'energie atomique, Centre de Valrho BP 17171 30207, Bagnols-sur-Ceze CEDEX (France)

A new PUREX first-cycle flowsheet was devised to enhance the extraction yield of neptunium at the extraction step of this cycle. Simulation results (using a qualified process-simulation tool), le d to raising the nitric acid concentration of the feed from 3 M to 4.5 M to allow extraction of more than 99% of the neptunium. This flowsheet was operated in the shielded process cell of ATALANTE facility using pulsed columns and mixer-settlers banks. A 15 kg quantity of genuine oxide fuel of average burn up of 52 GWd/t with cooling time of nearly five years was treated, and the neptunium extraction yield obtained was greater than 99.6%. (authors)

• Research Organization: Chemical Sciences Division, Oak Ridge National Laboratory (United States)
• OSTI ID: 21230364
• Resource Relation: Conference: ISEC 2008: International Solvent Extraction Conference on Solvent Extraction: Fundamentals to Industrial Applications, Tucson, AZ (United States), 15-19 Sep 2008; Other Information: Country of input: France; 3 refs; Related Information: In: Proceedings of ISEC 2008, International Solvent Extraction Conference - Solvent Extraction: Fundamentals to Industrial Applications, by Moyer, Bruce A. (ed.), 1740 pages.
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
07 ISOTOPES AND RADIATION SOURCES
BURNUP
COOLING TIME
EXTRACTION COLUMNS
MIXER-SETTLERS
NEPTUNIUM
NITRIC ACID
NUCLEAR FUELS
SIMULATION
SOLVENT EXTRACTION