The present disclosure provides systems and methods for fast molten salt reactor fuel-salt preparation. In one implementation, the method may comprise providing fuel assemblies having fuel pellets, removing the fuel pellets and spent fuel constituents from the fuel assemblies, granulating the removed fuel pellets or process feed to a chlorination process, processing the granular spent fuel salt into chloride salt by ultimate reduction and chlorination of the uranium and associated fuel constituents chloride salt solution, enriching the granular spent fuel salt, chlorinating the enriched granular spent fuel salt to yield molten chloride salt fuel, analyzing, adjusting, and certifying the molten chloride salt fuel for end use in a molten salt reactor, pumping the molten chloride salt fuel and cooling the molten chloride salt fuel, and milling the solidified molten chloride salt fuel to predetermined specifications.

Methods and systems directed to the separation of tritium from an aqueous stream are described. The separation method is a multi-stage method that includes a first stage during which tritium of a tritium-contaminated aqueous stream is adsorbed onto a separation phase, a second stage during which the adsorbed tritium is exchanged with hydrogen in a gaseous stream to provide a gaseous stream with a high tritium concentration, and a third stage during which the tritium of the gaseous stream is separated from the gaseous stream as a gaseous tritium product.

Systems and methods for long term disposal of high level nuclear waste in deep geologic formations are described. Such systems and method may include largely intact spent nuclear fuel rods in a disassembled form that may be placed into waste-capsules (e.g., carrier tubes); which may then be placed into various well boreholes. Example embodiments may provide waste-capsules capable of containing and disposing of waste generated from spent nuclear fuel, including means for harvesting the nuclear waste from cooling pools and operationally processing the waste fuel assemblies for inclusion in the waste-capsules with various engineered barriers; along with storage in horizontal well boreholes drilled into closed deep geologic formations.

Methods and systems directed to the separation of tritium from an aqueous stream are described. The separation method is a multi-stage method that includes a first stage during which tritium of a tritium-contaminated aqueous stream is adsorbed onto a separation phase, a second stage during which the adsorbed tritium is exchanged with hydrogen in a gaseous stream to provide a gaseous stream with a high tritium concentration, and a third stage during which the tritium of the gaseous stream is separated from the gaseous stream as a gaseous tritium product.

A methyl iodide adsorber, comprising a zeolite containing at least one iodide-adsorbing metal or a compound thereof, wherein the zeolite is a hydrophobic zeolite. Also, a use of the adsorber and a method for the adsorption of methyl iodide.

To effectively reduce the radioactivity concentration in reactor water. In an embodiment, a method of repairing a fuel assembly in a nuclear reactor, comprising: applying a compound containing at least one substance selected from the group consisting of TiO.sub.2, TiCl.sub.4, Ti(OH).sub.4, TiF.sub.4, TiCl.sub.3, TiN, TiC, Ti(SO.sub.4).sub.2, Ti.sub.3O.sub.5, Ti(NO.sub.3).sub.4, Al.sub.3O.sub.3, Al(OH).sub.3, AlCl.sub.3, Al(NO.sub.3).sub.3, Al.sub.2(SO.sub.4).sub.3, WO.sub.2, WO.sub.3, WC.sub.16, WF.sub.6, (NH.sub.4).sub.10W.sub.12O.sub.41.5H.sub.2O, H.sub.2WO.sub.4 and H.sub.4WO.sub.5 to a surface of a fuel rod of the fuel assembly.

Systems and methods for long term disposal of high level nuclear waste in deep geologic formations are described. Such systems and method may include largely intact spent nuclear fuel rods in a disassembled form that may be placed into waste-capsules (e.g., carrier tubes); which may then be placed into various well boreholes. Example embodiments may provide waste-capsules capable of containing and disposing of waste generated from spent nuclear fuel, including means for harvesting the nuclear waste from cooling pools and operationally processing the waste fuel assemblies for inclusion in the waste-capsules with various engineered barriers; along with storage in horizontal well boreholes drilled into closed deep geologic formations.

A method of decommissioning a nuclear reactor including a vessel defining an inner chamber and reactor internal components positioned within the inner chamber includes removing at least some of the internal components and repackaging at least some of the removed internal components in at least one of the first and second predefined sections of the vessel defining a cutting zone between the at least first and second predefined sections. The method further includes disposing the vessel in a container, and encapsulating the internal components in the vessel and encapsulating the vessel in the container to generate a package. A package including components from a decommissioned and dismantled nuclear reactor includes a vessel and a plurality of components encapsulated in the vessel.

This invention relates to the vitrification of radioactive waste products. According to this invention, a glass composition, which is suitable for low-level radioactive waste resins, and a method of vitrifying the low-level radioactive waste resins using the same are provided to significantly reduce the volume of radioactive waste products and to vitrify low-level radioactive waste products using the glass composition, which is suitable for vitrifying the low-level radioactive waste resins, thereby maximally delaying or completely preventing the leakage of radioactive materials from a glass solidified body.

A method of decommissioning a nuclear reactor including a vessel defining an inner chamber and reactor internal components positioned within the inner chamber includes removing at least some of the internal components and repackaging at least some of the removed internal components in at least one of the first and second predefined sections of the vessel defining a cutting zone between the at least first and second predefined sections. The method further includes disposing the vessel in a container, and encapsulating the internal components in the vessel and encapsulating the vessel in the container to generate a package. A package including components from a decommissioned and dismantled nuclear reactor includes a vessel and a plurality of components encapsulated in the vessel.