A method for recovering one or more of copper, uranium and a precious metal from an ore material, including: (a) forming a heap of the ore material; (b) during active heap irrigation, contacting the heap of the ore material with an iron containing acidic leach liquor having a high chloride content in the presence of an oxygen containing gas, and producing a pregnant leach solution; and (c) recovering one or more of copper, uranium and a precious metal from the pregnant leach solution.

Methods and systems for separation of thorium from uranium and their decay products are provided. The method comprises combining a nuclear fuel feedstock comprising thorium and uranium with a first acid to form a first solution. The first solution is contacted an ion exchange resin that is selective for thorium or uranium. The thorium or uranium is at least partially removed from the first solution by binding the thorium or uranium to the ion exchange resin thereby forming a second solution. The second solution is combined with oxalic acid to precipitate uranium or thorium from the second solution to form a precipitate. The precipitate is separated from the second solution.

A method for recovering one or more of copper, uranium and a precious metal from an ore material, including: (a) forming a heap of the ore material; (b) during active heap irrigation, contacting the heap of the ore material with an iron containing acidic leach liquor having a high chloride content in the presence of an oxygen containing gas, and producing a pregnant leach solution; and (c) recovering one or more of copper, uranium and a precious metal from the pregnant leach solution.

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.

This disclosure describes systems and methods for removing uranium hexafluoride (UF.sub.6) and/or other uranium fluoride (uranium fluorides identified herein generally as UF.sub.x) gases from a hydrogen fluoride (HF) gas stream.

A one-step method for electrokinetic uranium extraction and separation from sandstone-type uranium deposit is provided, including: using an activating leaching agent to adjust pH of activation environment as pH3, converting uranium elements in sandstone-type uranium deposit into positively charged uranyl and its complexes; applying direct current (DC) electric field with voltage gradient of 0.1 V/cm to 2 V/cm between cathode and anode, and allowing the uranium elements to move toward a cathode chamber under the action of the electric field and to undergo selective reduction by receiving electrons to produce a low-valent insoluble uranium-containing substance precipitated on the cathode surface. The present invention, through activating leaching, allows the formation of positively charged uranium ions and their complexes only, and electrophysical effects such as electromigration and electroosmosis promote directional movement of uranium toward cathode, thereby achieving uranium extraction from a sandstone-type uranium deposit.