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Improved leach resistance of FLiBe by conversion to a substituted fluorapatite

Improved leach resistance of FLiBe by conversion to a substituted fluorapatite

Ortega, L. H., Livingston, R. J., & McDeavitt, S. M.

Nuclear Materials and Energy (2022): 101223.

Considerable work is focused on the development of molten salt fueled nuclear reactors. The treatment of the spent fuel in these systems has unique waste management issues. These typically halogen-based salts are known to be water soluble to various degrees. In addition to leachability issues, radiolysis may destabilize these salts when they are in solid form. FLiBe, a favored candidate for fluoride-salt-fueled reactor applications, presents significant waste management challenges. Conversion of FLiBe to fluorapatite may be an effective means to stabilize the salt for improved long-term stability and storage.


Improved leach resistance of FLiBe by conversion to a substituted fluorapatite

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