Actinide removal from spent salts
AssigneeThe Regents of the University of California
InventorsPeter C. Hsu, Erica H. von Holtz, David L. Hipple, Leslie J. Summers, Martyn G. Adamson
Life of this patent
Estimating the term…
Loading patent…
AssigneeThe Regents of the University of California
InventorsPeter C. Hsu, Erica H. von Holtz, David L. Hipple, Leslie J. Summers, Martyn G. Adamson
Estimating the term…
A method for removing actinide contaminants (uranium and thorium) from the spent salt of a molten salt oxidation (MSO) reactor is described. Spent salt is removed from the reactor and analyzed to determine the contaminants present and the carbonate concentration. The salt is dissolved in water, and one or more reagents are added to precipitate the thorium as thorium oxide and/or the uranium as either uranium oxide or as a diuranate salt. The precipitated materials are filtered, dried and packaged for disposal as radioactive waste. About 90% of the thorium and/or uranium present is removed by filtration. After filtration, salt solutions having a carbonate concentration >20% can be dried and returned to the reactor for re-use. Salt solutions containing a carbonate concentration <20% require further clean-up using an ion exchange column, which yields salt solutions that contain less than 0.1 ppm of thorium or uranium.
A method for removing actinides from a spent salt of a molten salt reactor, comprising:
A method for removing actinides from a spent salt of a molten salt reactor, comprising:
A method for removing actinides from a spent salt of a molten salt reactor, wherein the spent salt contains less than 20% by weight carbonate, comprising the following steps:
Dependencies are inferred from the claim text.