Process for metals leaching and recovery from radioactive wastes
AssigneeHer Majesty the Queen in Right of Canada as Represented by the Minister of Natural Resources Canada
InventorsNicolas Reynier, Rolando Lastra, Nabil Bouzoubaa, Mark Chapman
Life of this patent
Estimating the term…
Abstract
Provided is a process for recovering metals from solid radioactive waste, preferably uranium, cesium, mercury, thorium, rare earths or combinations thereof. The process comprises a leaching step and a separation step. The leaching step comprises contacting the solid radioactive waste with an aqueous inorganic acid and a leaching salt to produce a mixture of a metal-rich leachate and a metal-poor waste, which are separated in the separation step. Also provided is a process for recovering metals from solid radioactive waste comprising an attrition step, a leaching step, a washing step, a combination step and a recovery step.
Claims44
A process for recovering metals from cemented radioactive waste comprising the metals, the process comprising:
- a) a leaching step comprising contacting the cemented radioactive waste with an aqueous inorganic acid at a concentration between about 0.1 M and about 2 M, and a leaching salt, at a temperature lower than about 100° C., to solubilize at least a portion of the metals present in the cemented radioactive waste, thereby producing a mixture of a metal-rich leachate and a metal-poor waste;
- and
- b) a separation step comprising separating the metal-rich leachate from the metal-poor waste.
A process for recovering metals from cemented radioactive waste comprising the metals, wherein the metals comprise uranium, cesium, mercury, thorium, rare earth or combination thereof;
- the process comprising:
- a) an attrition step comprising mixing the cemented radioactive waste with water to solubilize at least a portion of the metals present in the waste providing an aqueous mixture;
- and separating the aqueous mixture to provide a metal-rich liquid, a metal-depleted waste and a metal-rich sludge;
- b) a leaching step comprising contacting the metal-rich sludge from step a) with an aqueous inorganic acid at a concentration between about 0.1 M and about 2 M, and a leaching salt, at a temperature lower than about 100° C., to solubilize at least a portion of the metals present in the cemented radioactive waste, thereby producing a mixture of a metal-rich leachate and a metal-poor waste;
- and separating the metal-rich leachate and metal-poor waste;
- c) a washing step comprising contacting the metal-poor waste from step b) with an aqueous solution, at a temperature lower than about 100° C., solubilize a substantial amount of the metals to produce a metal-rich solution and metal-poor waste, and separating the metal-rich solution and metal-poor waste;
- d) a combination step comprising combining the metal-rich liquid of step a), the metal-rich leachate of step b) and the metal-rich solution of step c) to provide a metal-rich combined solution;
- e) a recovery step comprising contacting the metal-rich combined solution with an ion exchange resin favoring the metals extraction;
- or contacting the metal-rich combined solution with a coagulant at a pH favoring precipitation of the metals.
Dependencies are inferred from the claim text.