Method for reprocessing and separating spent nuclear fuels

A method for reprocessing and separating spent nuclear fuels comprising actinide fuels, volatile and non-volatile fission products, in a molten tin solvent, comprising:

• providing a separation vessel formed of a carbon-containing material, said separation vessel defining a reaction region housing said molten tin solvent and a reflux region positioned adjacent to and above said reaction region, said separation vessel including an aperture disposed within a vessel wall member in a position adjacent said reflux region;
• adding a first catalyst to said tin solvent which increases the solubility of carbon in said solvent;
• maintaining said reaction region at a temperature sufficient to convert said actinide fuels to a solubilized state;
• maintaining said reflux region at a temperature sufficient to reflux said tin solvent, said reflux temperature being lower than said reaction region temperature;
• introducing spent nuclear fuels into said tin solvent;
• forming CO within said molten tin solvent from actinide fuels which are oxides;
• allowing CO and volatile fission products within said molten tin solvent, along with some molten tin, to evaporate and flow into said reflux region;
• removing CO and volatile fission products which are not condensable at said reflux temperature from said reflux region through said vessel aperture, leaving evaporated tin and condensable fission products in said reflux region;
• and
• allowing evaporated tin and condensable fission products disposed within said reflux region which are condensable at said reflux temperature to cool sufficiently and return to said molten tin solvent in said reaction region.

A method for reprocessing and separating spent nuclear fuels comprising actinide fuels, volatile and non-volatile fission products, comprising:

• providing a separation vessel formed from a carbon-containing material housing a molten metal solvent, said separation vessel including an aperture disposed within a vessel wall member;
• introducing spent nuclear fuels into said separation vessel;
• forming CO within said molten metal solvent from actinide fuels which are oxides;
• removing CO and volatile fission products from said separation vessel;
• introducing a nitriding catalyst into said vessel which increases the affinity for nitrogen in said molten metal solvent;
• introducing a non-oxidizing nitrogen-containing atmosphere into said separation vessel;
• forming solid nitrides from said actinide fuels within said molten metal solvent;
• and
• separating said solid actinide nitrides from said molten metal solvent and non-volatile fission products.