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.

Systems and methods for efficient, effective, and safe separation and isolation of multiple isotopes (e.g., Mo, Zr, Ba, Sr, Te, and lanthanide isotopes) from fission products includes use of a plurality of chromatography columns, each containing a chromatographic resin formulated to target one or more particular isotopes. The system is operable in a series configuration to load the multiple columns by a single pass of the sample. Then, the system may be transitioned (e.g., using valves) to a parallel configuration in which multiple columns of the system may be operated simultaneously to elute targeted isotopes. Additional parallel operations of the columns, using different eluent compositions, may be used to elute different targeted isotopes. The system may be reconditioned in preparation for a subsequent sample.

The disclosure relates to a beneficiation process for uranium ore comprising a hydrocyclone step that produces an underflow fraction containing uranium values for further processing and an overflow fraction containing fine particulate waste material

The disclosure relates to a beneficiation process for uranium ore comprising a hydrocyclone step that produces an underflow fraction containing uranium values for further processing and an overflow fraction containing fine particulate waste material

In a process for producing uranium and/or at least one rare earth element selected from the group consisting of cerium, dysprosium, erbium, europium, gadolinium, holmium, lanthanum, lutetium, neodymium, praseodymium, promethium, samarium, scandium, terbium, thulium, ytterbium and yttrium out of an ore, the ore is mixed with sulphuric acid with a concentration of at least 95 wt.-% to a mixture, wherein the mixture is granulated to pellets. The pellets are fed into at least one fluidized bed fluidized by a fluidizing gas for a thermal treatment at temperatures between 200 and 1000 C. The at least one fluidized bed is developed such that it at least partly surrounds a gas supply tube for a gas or a gas mixture fed into the reactor and the gas or gas mixture is used as a heat transfer medium.

Described is a process for the refinement of a quartz powder, comprising the step of separating microparticles of refractory minerals, in particular minerals containing rare earth metal compounds, from the quartz powder by an elutriation step.

A process for producing a daughter radionuclide from a parent radionuclide includes a) loading the parent radionuclide on a first solid medium contained in a generator and onto which the parent radionuclide is retained and whereby the daughter radionuclide is formed by radioactive decay of the parent radionuclide; b) eluting this medium with a A0 solution so as to recover a A1 solution comprising the daughter radionuclide; c) optionally adjusting the pH of the A1 solution so as to obtain a A1 solution, d) loading this A1 or A1 solution onto the head of a second solid medium contained in a chromatography column; e) first washing said second solid medium with a A2 solution; f) second washing said second solid medium with a A2 solution; g) eluting the daughter radionuclide with a A3 solution. The first washing step is conducted from head to tail of the column and the second washing step and the second eluting step are conducted from tail to head of the column.

Disclosed are a method of manufacturing a uranium target, the method including (a) a step of preparing a conjugate including a matrix and a uranium target green compact formed in the matrix; and (b) a step of performing thermo-mechanical treatment through additional heat treatment at 530 C. to 600 C. during a hot rolling pass in a process of hot-rolling the conjugate, and a method of extracting radioactive Mo-99 using the uranium target.

The invention relates to a beneficiation process for uranium ores comprising clay and carbonate minerals, the process comprising: performing a hydrocyclone step to obtain a hydrocyclone underflow fraction substantially comprising the uranium component; treating the hydrocyclone underflow fraction to effect a separation of carbonate and uranium minerals; and recovering the uranium-bearing minerals to produce a uranium concentrate.

The invention relates to a beneficiation process for uranium ores comprising clay and carbonate minerals, the process comprising: performing a hydrocyclone step to obtain a hydrocyclone underflow fraction substantially comprising the uranium component; treating the hydrocyclone underflow fraction to effect a separation of carbonate and uranium minerals; and recovering the uranium-bearing minerals to produce a uranium concentrate.