Patent classifications
G21C19/48
METHOD TO PRODUCE SALTS CONTAINING ACTINIDE HALIDES
A method of producing uranium halides is disclosed in which chlorine gas is introduced into a liquid uranium-nickel alloy. NaCl salt is surrounding the crucible containing the liquid uranium-nickel alloy, producing a eutectic mixture of NaClUCl.sub.3. Upon chlorination, the metal halide dissolves in the matrix salt forming a solution. Adding the reactant metal, uranium to the nickel, the alloy is able to remain molten throughout processing. The liquid metal alloy may be removed from the salt bath, while the halide gas continues to enter the system through the sparge until the desired composition of NaClUCl.sub.3UCl.sub.4 is achieved. The method and system can be used to produce other metal halide salts such as actinide, lanthanide or transition metal halides contained in a matrix salt consisting of alkali and/or alkaline earth halides.
Modular, integrated, automated, compact, and proliferation-hardened method to chemically recycle used nuclear fuel (UNF) originating from nuclear reactors to recover a mixture of transuranic (TRU) elements for advanced reactor fuel to recycle uranium and zirconium
A single integrated system for recycling used nuclear fuel (UNF) emerging from a reactor has a decladding vessel separating fuel pellets from nuclear fuel rods via oxidation to produce U.sub.3O.sub.8. A fluorination vessel is coupled to the decladding vessel to remove hexafluorides from the U.sub.3O.sub.8 produced by the decladding vessel. An electrowinning vessel is coupled to the fluorination vessel removing plutonium and actinides via electrowinning.
Method and system for generating electricity using waste nuclear fuel
A nuclear reactor adapted for generating energy and/or decontaminating nuclear fuel using a plurality of energy beam generating accelerator devices configured for inducing a photo-fission reaction in the nuclear fuel.
Method and system for generating electricity using waste nuclear fuel
A nuclear reactor adapted for generating energy and/or decontaminating nuclear fuel using a plurality of energy beam generating accelerator devices configured for inducing a photo-fission reaction in the nuclear fuel.
MODULAR, INTEGRATED, AUTOMATED, COMPACT, AND PROLIFERATION-HARDENED METHOD TO CHEMICALLY RECYCLE USED NUCLEAR FUEL (UNF) ORIGINATING FROM NUCLEAR REACTORS TO RECOVER A MIXTURE OF TRANSURANIC (TRU) ELEMENTS FOR ADVANCED REACTOR FUEL, AND TO RECYCLE URANIUM AND ZIRCONIUM
A single integrated system for recycling used nuclear fuel (UNF) emerging from a reactor has a decladding vessel separating fuel pellets from nuclear fuel rods via oxidation to produce a uranium compound. A fluorination vessel is coupled to the decladding vessel. A fluorinating agent is injected into the fluorination vessel and reacts with the uranium compound to convert the uranium compound to UF.sub.6. An electrowinning vessel is coupled to the fluorination vessel removing plutonium and actinides via electrowinning.
MODULAR, INTEGRATED, AUTOMATED, COMPACT, AND PROLIFERATION-HARDENED METHOD TO CHEMICALLY RECYCLE USED NUCLEAR FUEL (UNF) ORIGINATING FROM NUCLEAR REACTORS TO RECOVER A MIXTURE OF TRANSURANIC (TRU) ELEMENTS FOR ADVANCED REACTOR FUEL, AND TO RECYCLE URANIUM AND ZIRCONIUM
A single integrated system for recycling used nuclear fuel (UNF) emerging from a reactor has a decladding vessel separating fuel pellets from nuclear fuel rods via oxidation to produce a uranium compound. A fluorination vessel is coupled to the decladding vessel. A fluorinating agent is injected into the fluorination vessel and reacts with the uranium compound to convert the uranium compound to UF.sub.6. An electrowinning vessel is coupled to the fluorination vessel removing plutonium and actinides via electrowinning.
Method of separating and recovering uranium from aluminum-clad metallic nuclear fuel
According to one aspect of the invention, a method for separating and recovering uranium from a nuclear fuel element. The method includes immersing a nuclear fuel element containing nuclear fuel and cladding in a molten metal. The nuclear fuel includes uranium. The cladding is selectively dissolved from the nuclear fuel element when immersed in the molten metal. The nuclear fuel is separated from the cladding. The method then includes loading the nuclear fuel into a permeable basket that is electrically configured as an anode of an electrolytic cell. There are also a molten salt electrolyte and a cathode in the electrolytic cell. Then, the method includes applying an electric charge across the electrolytic cell. The molten salt electrolyte selectively transfers uranium from the anode to the cathode.
Method of separating and recovering uranium from aluminum-clad metallic nuclear fuel
According to one aspect of the invention, a method for separating and recovering uranium from a nuclear fuel element. The method includes immersing a nuclear fuel element containing nuclear fuel and cladding in a molten metal. The nuclear fuel includes uranium. The cladding is selectively dissolved from the nuclear fuel element when immersed in the molten metal. The nuclear fuel is separated from the cladding. The method then includes loading the nuclear fuel into a permeable basket that is electrically configured as an anode of an electrolytic cell. There are also a molten salt electrolyte and a cathode in the electrolytic cell. Then, the method includes applying an electric charge across the electrolytic cell. The molten salt electrolyte selectively transfers uranium from the anode to the cathode.
ELECTROCHEMICAL CELLS FOR DIRECT OXIDE REDUCTION, AND RELATED METHODS
A method of direct oxide reduction includes forming a molten salt electrolyte in an electrochemical cell, disposing at least one metal oxide in the electrochemical cell, disposing a counter electrode comprising a material selected from the group consisting of osmium, ruthenium, rhodium, iridium, palladium, platinum, silver, gold, lithium iridate, lithium ruthenate, a lithium rhodate, a lithium tin oxygen compound, a lithium manganese compound, strontium ruthenium ternary compounds, calcium iridate, strontium iridate, calcium platinate, strontium platinate, magnesium ruthenate, magnesium iridate, sodium ruthenate, sodium iridate, potassium iridate, and potassium ruthenate in the electrochemical cell, and applying a current between the counter electrode and the at least one metal oxide to reduce the at least one metal oxide. Related methods of direct oxide reduction and related electrochemical cells are also disclosed.
ELECTROCHEMICAL CELLS FOR DIRECT OXIDE REDUCTION, AND RELATED METHODS
A method of direct oxide reduction includes forming a molten salt electrolyte in an electrochemical cell, disposing at least one metal oxide in the electrochemical cell, disposing a counter electrode comprising a material selected from the group consisting of osmium, ruthenium, rhodium, iridium, palladium, platinum, silver, gold, lithium iridate, lithium ruthenate, a lithium rhodate, a lithium tin oxygen compound, a lithium manganese compound, strontium ruthenium ternary compounds, calcium iridate, strontium iridate, calcium platinate, strontium platinate, magnesium ruthenate, magnesium iridate, sodium ruthenate, sodium iridate, potassium iridate, and potassium ruthenate in the electrochemical cell, and applying a current between the counter electrode and the at least one metal oxide to reduce the at least one metal oxide. Related methods of direct oxide reduction and related electrochemical cells are also disclosed.