Method for reprocessing and separating spent nuclear fuels

Chemistry of inorganic compounds – Treating mixture to obtain metal containing compound – Radioactive metal

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423251, 423252, 423254, 423DIG12, 252627, 75 841A, C01G 5600, C01G 4300, C01F 1500, G21C 1948

Patent

active

043991084

ABSTRACT:
Spent nuclear fuels, including actinide fuels, volatile and non-volatile fission products, are reprocessed and separated in a molten metal solvent housed in a separation vessel made of a carbon-containing material. A first catalyst, which promotes the solubility and permeability of carbon in the metal solvent, is included. By increasing the solubility and permeability of the carbon in the solvent, the rate at which actinide oxides are reduced (carbothermic reduction) is greatly increased. A second catalyst, included to increase the affinity for nitrogen in the metal solvent, is added to increase the rate at which actinide nitrides form after carbothermic reduction is complete.

REFERENCES:
patent: 3794482 (1974-02-01), Anderson et al.
patent: 3843765 (1974-10-01), Anderson et al.
patent: 3843766 (1974-10-01), Anderson et al.
patent: 3867510 (1975-02-01), Miller et al.
Smithells, Colin J., "Metals Reference Book, vol. II", 4th Ed., Plenum Press, New York, 1967, pp. 436, 438, 460, 493, 550, 621-625.

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