# US 4,392,995 A · Molten tin reprocessing of spent nuclear fuel elements > Agents: this data is available as JSON from the patentgrep API and MCP server — see https://patentgrep.com/llms.txt - Number: US 4,392,995 A - Document ID: US4392995A - Status: Granted - Kind: A - Application number: 06/218,242 - Filed: 1980-12-19 - Granted: 1983-07-12 - Earliest claimed: 1980-12-19 - Assignees: The United States of America as represented by the United States Department of Energy - Inventors: Richard A. Heckman - Web page: https://patentgrep.com/patent/US4392995A ## CPC - G21C 19/48: Non-aqueous processes - Y02E 30/30: Nuclear fission reactors - Y02W 30/50: Reuse, recycling or recovery technologies - G21C: NUCLEAR REACTORS (fusion reactors, hybrid fission-fusion reactors G21B; nuclear explosives G21J) - Y02E: REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION - Y02W: CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT ## Abstract A method and apparatus for reprocessing spent nuclear fuel is described. Within a containment vessel, a solid plug of tin and nitride precipitates supports a circulating bath of liquid tin therein. Spent nuclear fuel is immersed in the liquid tin under an atmosphere of nitrogen, resulting in the formation of nitride precipitates. The layer of liquid tin and nitride precipitates which interfaces the plug is solidified and integrated with the plug. Part of the plug is melted, removing nitride precipitates from the containment vessel, while a portion of the plug remains solidified to support the liquid tin and nitride precipitates remaining in the containment vessel. The process is practiced numerous times until substantially all of the precipitated nitrides are removed from the containment vessel. ## Claims ### Claim 1 A method for reprocessing spent nuclear fuel in an apparatus having liquid tin dispersed within a containment vessel, and a solid plug of tin and nitride precipitates disposed within said containment vessel to interface with and support said liquid tin therein, comprising: feeding spent nuclear fuel into said containment vessel; immersing said spent nuclear fuel in said liquid tin under an atmosphere of nitrogen, resulting in the formation of nitride precipitates from said nuclear fuel, whereby said nitride precipitates are dispersed throughout said liquid tin; solidifying a layer of liquid tin and nitride precipitates which interfaces with said plug, to thereby integrate said layer with said plug; melting an end portion of said plug remote from an end of said plug which interfaces with molten tin, whereby said melted end portion may be removed, while leaving a sufficient amount of said plug solidified to provide support for said liquid tin and nitride precipitates remaining in said containment vessel; and removing said melted portion of said plug from said containment vessel. ### Claim 2 (depends on 1) The method for reprocessing spent nuclear fuel as defined in claim 1, further comprising circulating said liquid tin within said containment vessel, to promote nitrogen mixing and formation of nitride precipitates. ### Claim 3 (depends on 1) The method for reprocessing spent nuclear fuel according to claim 1, wherein said liquid tin dispersed within said containment vessel is maintained at a temperature range of from about 1500.degree. to 1600.degree. C. ### Claim 4 (depends on 1) The method for reprocessing spent nuclear fuel according to claim 1, wherein said end portion of said plug remote from said end of said plug which interfaces with molten tin is melted by circulating a heated fluid at about 300.degree. C. around said end portion. ### Claim 5 A method for reprocessing spent nuclear fuels in an apparatus having liquid tin disposed within a containment vessel, and a solid plug comprising tin and nitrides precipitates, said plug having a top section and a bottom section, with the top section interfacing with and supporting said liquid tin within the containment vessel; comprising the steps of: (a) fedding spent nuclear fuel into said containment vessel; (b) immersing said spent nuclear fuel in said liquid tin under an atmosphere of nitrogen, thereby forming nitride precipitates from said spent nuclear fuel, said nitride precipitates being dispersed throughout said liquid tin; (c) heating the area of said containment vessel adjacent to and surrounding said bottom section of said plug creating a melted portion, said melted portion of said plug being removable from said containment vessel by gravity or other means, while said top section of said plug remains solidified and provides support for said liquid tin and nitride precipitates remaining in said containment vessel, while slowly descending in said containment vessel; (d) then subsequently cooling the area of said containment vessel adjacent to and surrounding the descending section of said plug to halt its descent, while heating the area of said containment vessel adjacent to said top section of said plug, thereby solidifying the layer of liquid tin and dispersed nitride precipitates which interfaces said top section of said plug, whereby the steps (c) and (d) may be sequentially repeated to thereby effect continuous removal of nitride precipitates from said vessel; and removing said melted bottom section of said plug from said containment vessel. ### Claim 6 (depends on 5) The method for reprocessing spent nuclear fuel as defined in claim 5, further comprising circulating said liquid tin within said containment vessel to promote nitrogen mixing and formation of nitride precipitates. ### Claim 7 (depends on 5) The method for reprocessing spent nuclear fuel according to claim 5, wherein said liquid tin disposed within said containment vessel is maintained at a temperature range of from about 1500.degree. to 1600.degree. C.