Electrolysis of uranium nitride containing fission product elements (Mo, Pd, Nd) in a molten LiCl-KCl eutectic

Conference · Sun Jul 01 04:00:00 EDT 2007

OSTI ID:20979668

Satoh, Takumi; Iwai, Takashi; Arai, Yasuo ^[1]

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1. Japan Atomic Energy Agency, Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki-ken, 311-1393 (Japan)

The electrolysis of burnup-simulated uranium nitride, UN, containing representative solid fission product elements (Mo, Pd, Nd) was investigated in the molten LiCl-KCl eutectic salt with 0.54 wt% UCl{sub 3} from the view point of application of pyrochemical reprocessing to nitride fuel cycle. It was found from cyclic voltammetry and anodic polarization curve measurement that anodic dissolution of UN began at about -0.75 V vs. Ag/AgCl reference electrode in all samples. After the electrolysis at the constant anodic potential of -0.65 {approx} -0.60 V vs. Ag/AgCl, most of UN was dissolved into LiCl- KCl as UCl{sub 3} at the anode, and U was recovered in the liquid Cd cathode in all samples. Further, Nd was dissolved into LiCl-KCl as NdCl{sub 3}, while Mo and Pd were not dissolved but remained at the anode. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 20979668
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ANODES
BURNUP
CATHODES
DISSOLUTION
ELECTROLYSIS
EUTECTICS
FISSION PRODUCTS
FUEL CYCLE
LITHIUM CHLORIDES
MOLYBDENUM
NEODYMIUM
NEODYMIUM CHLORIDES
PALLADIUM
POTASSIUM CHLORIDES
PYROCHEMICAL REPROCESSING
SALTS
SILVER CHLORIDES
URANIUM CHLORIDES
URANIUM NITRIDES
VOLTAMETRY