This disclosure describes systems and methods for synthesizing UCl.sub.3 from UCl.sub.4. These systems and methods may also be used to directly synthesize binary and ternary embodiments of uranium salts of chloride usable as nuclear fuel in certain molten salt reactor designs. The systems and methods described herein are capable of synthesizing any desired uranium chloride fuel salt that is a combination of UCl.sub.4, UCl.sub.3 and one or more non-fissile chloride compounds, such as NaCl. In particular, the systems and methods described herein are capable of synthesizing any UCl.sub.3UCl.sub.4NaCl or UCl.sub.3NaCl fuel salt composition from UCl.sub.4NaCl.

This disclosure describes systems and methods for synthesizing UCl.sub.3 from UCl.sub.4. These systems and methods may also be used to directly synthesize binary and ternary embodiments of uranium salts of chloride usable as nuclear fuel in certain molten salt reactor designs. The systems and methods described herein are capable of synthesizing any desired uranium chloride fuel salt that is a combination of UCl.sub.4, UCl.sub.3 and one or more non-fissile chloride compounds, such as NaCl. In particular, the systems and methods described herein are capable of synthesizing any UCl.sub.3UCl.sub.4NaCl or UCl.sub.3NaCl fuel salt composition from UCl.sub.4NaCl.

This disclosure describes systems and methods for synthesizing UCl.sub.3 from UCl.sub.4. These systems and methods may also be used to directly synthesize binary and ternary embodiments of uranium salts of chloride usable as nuclear fuel in certain molten salt reactor designs. The systems and methods described herein are capable of synthesizing any desired uranium chloride fuel salt that is a combination of UCl.sub.4, UCl.sub.3 and one or more non-fissile chloride compounds, such as NaCl. In particular, the systems and methods described herein are capable of synthesizing any UCl.sub.3UCl.sub.4NaCl or UCl.sub.3NaCl fuel salt composition from UCl.sub.4NaCl.

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.

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.

This disclosure describes systems and methods for synthesizing UCl.sub.3 from UCl.sub.4. These systems and methods may also be used to directly synthesize binary and ternary embodiments of uranium salts of chloride usable as nuclear fuel in certain molten salt reactor designs. The systems and methods described herein are capable of synthesizing any desired uranium chloride fuel salt that is a combination of UCl.sub.4, UCl.sub.3 and one or more non-fissile chloride compounds, such as NaCl. In particular, the systems and methods described herein are capable of synthesizing any UCl.sub.3UCl.sub.4NaCl or UCl.sub.3NaCl fuel salt composition from UCl.sub.4NaCl.

This disclosure describes systems and methods for synthesizing UCl.sub.3 from UCl.sub.4. These systems and methods may also be used to directly synthesize binary and ternary embodiments of uranium salts of chloride usable as nuclear fuel in certain molten salt reactor designs. The systems and methods described herein are capable of synthesizing any desired uranium chloride fuel salt that is a combination of UCl.sub.4, UCl.sub.3 and one or more non-fissile chloride compounds, such as NaCl. In particular, the systems and methods described herein are capable of synthesizing any UCl.sub.3UCl.sub.4NaCl or UCl.sub.3NaCl fuel salt composition from UCl.sub.4NaCl.

Disclosed herein are embodiments of metal complexes and methods of making the same. The disclosed method embodiments provide a one-step approach to making metal complexes, such as complexes comprising lanthanide metals, rare earth metals, transition metals, main group metals, and/or actinide metals that can be used various applications, such as in separations technology, catalysis (e.g., catalysts for pharmaceutical synthesis and/or catalysts for biomass conversion), nuclear chemistry, LED phosphors, scintillator materials, magnetic materials, and nuclear fuels.

Disclosed herein are embodiments of metal complexes and methods of making the same. The disclosed method embodiments provide a one-step approach to making metal complexes, such as complexes comprising lanthanide metals, rare earth metals, transition metals, main group metals, and/or actinide metals that can be used various applications, such as in separations technology, catalysis (e.g., catalysts for pharmaceutical synthesis and/or catalysts for biomass conversion), nuclear chemistry, LED phosphors, scintillator materials, magnetic materials, and nuclear fuels.