Patent Number: 
Section: claims

1. A system for processing spent nuclear fuel from fuel assemblies having fuel tubes into fast molten salt reactor fuel, the system comprising components including at least:means for chlorinating and processing the spent fuel into chloride salt by ultimate reduction and chlorination, including reacting the spent fuel with anhydrous hydrogen chloride (AHCl);a fluidized bed configured to receive spent fuel gasses and to convert the spent fuel gases to chlorinated fuel salts; andmeans for chlorinating the spent fuel salt to yield molten chloride fuel salt for a fast molten salt reactor. 2. The system of claim 1, further comprising:at least one of a first mill, configured to granulate the spent fuel in an atmosphere that is at least semi-voided, and a second mill, configured to mill the molten chloride fuel salt to predetermined specifications for the fast molten salt reactor. 3. The system of claim 1, further comprising:at least one tray configured to receive the molten chloride fuel salt and to allow the molten chloride fuel salt to cool to solidify. 4. The system of claim 3, wherein the tray is configured to receive the molten chloride fuel salt and to allow the molten chloride fuel salt to cool to solidify in the form of bars, sticks, or canisters. 5. The system of claim 1, further comprising means for enriching the spent fuel salt. 6. The system of claim 5, wherein the means for chlorinating and processing the spent fuel into chloride salt includes reacting the enriched spent fuel salt with AHCl. 7. The system of claim 1, further comprising means for enriching the spent fuel salt with one or more of uranium-235 (U235), plutonium-239 (Pu239), or mixed oxide (MOX). 8. The system of claim 1, further comprising a rod puller disassembly table configured for receiving the fuel assemblies and for removing the spent fuel from the fuel assemblies. 9. The system of claim 1, further comprising a laser configured for slitting or slicing the fuel tubes for allowing removal of the spent fuel. 10. The system of claim 1, further comprising an oxide reduction tank configured for enriching the spent fuel salt. 11. The system of claim 1, wherein the means for chlorinating includes a molten chloride salt bath, and wherein the chlorinating step occurs by immersion in the molten chloride salt bath. 12. The system of claim 1, further comprising means for enriching the spent fuel salt with enriched uranium. 13. The system of claim 1, further comprising:a site within a secured perimeter;a limited-access facility on the site;the components of the system being located within the limited-access facility;a spent nuclear fuel storage facility located on the site; anda molten salt reactor located on the site. 14. The system of claim 1, wherein the means for chlorinating and processing the spent fuel into chloride salt by ultimate reduction and chlorination produces hydrogen and further comprises converting the hydrogen to water and continuously removing the water. 15. A system for processing spent nuclear fuel from fuel assemblies having fuel tubes into fast molten salt reactor fuel, the system comprising:means for removing spent fuel from the fuel assemblies;a first mill configured for granulating, in an atmosphere that is at least semi-voided, the removed spent fuel into granular spent fuel suitable for chlorination;means for processing the granular spent fuel into chloride salt by ultimate reduction and chlorination, including reacting the granular spent fuel with anhydrous hydrogen chloride (AHCl);means for chlorinating the granular spent fuel salt to yield molten chloride fuel salt by reacting the granular spent fuel salt with AHCl;a fluidized bed configured to receive spent fuel gasses and to convert the spent fuel gases to chlorinated fuel salts; anda second mill configured for milling the molten chloride fuel salt to predetermined specifications. 16. The system of claim 15, further comprising a disassembly table configured for receiving the fuel assemblies and for removing the spent fuel from the fuel assemblies. 17. The system of claim 15, further comprising a laser configured for slitting or slicing the fuel tubes for allowing removal of the spent fuel. 18. The system of claim 15, further comprising an oxide reduction tank configured for enriching the granular fuel salt. 19. A system for processing spent nuclear fuel from fuel assemblies having fuel tubes into fast molten salt reactor fuel, the system comprising:a first mill configured for granulating, in an atmosphere that is at least semi-voided, the removed spent fuel into granular spent fuel suitable for chlorination;means for processing the granular spent fuel into chloride salt by ultimate reduction and chlorination, including reacting the granular spent fuel with anhydrous hydrogen chloride (AHCl);an oxide reduction tank configured for enriching the granular fuel salt;means for chlorinating the enriched granular spent fuel salt to yield molten chloride fuel salt by reacting the enriched granular spent fuel salt with AHCl;a fluidized bed configured to receive spent fuel gasses and to convert the spent fuel gases to chlorinated fuel salts; anda second mill configured for milling the molten chloride fuel salt to predetermined specifications. 20. A system for processing spent nuclear fuel from fuel assemblies having fuel tubes into fast molten salt reactor fuel, the system comprising components including at least:means for chlorinating and processing the spent fuel into chloride salt by ultimate reduction and chlorination, including reacting the spent fuel with anhydrous hydrogen chloride (AHCl) wherein hydrogen is produced, converting the hydrogen to water, and continuously removing the water; andmeans for chlorinating the spent fuel salt to yield molten chloride fuel salt for a fast molten salt reactor.