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.

A solution for leaching metals from clay containing ore and a method of leaching ore is described. The solution comprises a cyanide; a wetting agent; and a clay stabilizing polymer.

The proposed invention relates to processes for extracting and concentrating radionuclides and can be used in radiochemical technologies when treating liquid radioactive waste. The method for isolating americium from liquid radioactive waste and for separating americium from rare earth elements in a single extraction cycle involves joint extraction of americium and rare earth elements from a nitric acid radioactive solution with a neutral solution of an organic extraction agent in a polar fluorinated solvent; washing an obtained organic phase saturated with metals; and selective back extraction of americium, wherein the extraction agent for joint extraction is N,N,N,N-tetraalkylamide of diglycolic acid, and a solution for back extraction is a composition of 5-20 g/l of a complexone, 5-60 g/l of a nitrogen-containing organic acid and 60-240 g/l of a salting-out agent.

The proposed invention relates to processes for extracting and concentrating radionuclides and can be used in radiochemical technologies when treating liquid radioactive waste. The method for isolating americium from liquid radioactive waste and for separating americium from rare earth elements in a single extraction cycle involves joint extraction of americium and rare earth elements from a nitric acid radioactive solution with a neutral solution of an organic extraction agent in a polar fluorinated solvent; washing an obtained organic phase saturated with metals; and selective back extraction of americium, wherein the extraction agent for joint extraction is N,N,N,N-tetraalkylamide of diglycolic acid, and a solution for back extraction is a composition of 5-20 g/l of a complexone, 5-60 g/l of a nitrogen-containing organic acid and 60-240 g/l of a salting-out agent.

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 method for obtaining .sup.225AC from .sup.225Ra having the steps of assembling a column having an inorganic stationary phase; priming the column to immobilize .sup.226Ra .sup.225Ra and natural decay products therefrom; immobilizing the .sup.226Ra, .sup.225Ra, .sup.224Ra, and natural decay products therefrom onto a stationary phase within the column; and eluting the column containing the .sup.225Ra with an aqueous sulfate solution to obtain a milking effluent that contains .sup.225AC. Also provided is a method for obtaining pure .sup.225AC from its isotope parents, the method comprising assembling a column having a stationary phase comprising an inorganic material; priming the column with the isotope parents to immobilize .sup.225Ac, and natural decay products of .sup.225AC; immobilizing the .sup.225Ac, and natural decay products therefrom onto the stationary phase within the column .sup.226Ra, .sup.225Ra, .sup.224Ra; and eluting the column containing the .sup.225AC to obtain an effluent that contains the isotope parents.

A process for recovering uranium from components contaminated with uranium oxide includes providing a cleaning apparatus with a cleaning solution for dissolving the uranium oxide of the components, carrying out a cleaning process by introducing a batch of components into the cleaning apparatus, and carrying out a measurement for determining the uranium content of the components. The cleaning and the measuring are repeated if a limit value for the uranium content is exceeded. The components are discharged from the process if the uranium content falls below a limit value. The cleaning is carried out on a plurality of successive batches of components until a control measurement indicates an unsatisfactory cleaning action of the cleaning solution. The uranium oxide dissolved in the cleaning solution is recovered after indication of the unsatisfactory cleaning action.

A solution for leaching metals from clay containing ore and a method of leaching ore is described. The solution comprises a cyanide; a wetting agent; and a clay stabilizing polymer.

A useful metal may be recovered from a solution of a nitrate salt of a metal cation or a metal oxycation, by adding the solution of the nitrate salt to a formation column having an inlet and an outlet nozzle, the solution of the nitrate salt being added in a dropwise fashion through the inlet. The formation column contains a recirculating solution containing a base selected from the group consisting of ammonia, ammonium hydroxide, an alkali metal hydroxide, and an alkaline earth metal hydroxide. The nitrate salt reacts with the base in the recirculating solution to produce a metal oxide salt or a metal hydroxide salt as a precipitate. The precipitate and the recirculating solution exit the formation column through the outlet nozzle and are captured the precipitate in a basket beneath the formation column while recovering the recirculating solution in a catch tank under the basket. The recovered recirculating solution is pumped from the catch tank to the formation column. The nitrate salt of the metal cation may be a nitrate salt of a radioactive metal cation, e.g., uranium or a uranyl cation.

A method for recovering thorium and rare earth elements from rare earth waste residues includes the steps of (1) mixing rare earth waste residues with an inorganic acid and heating to obtain a stock solution containing thorium and rare earth elements; (2) extracting thorium and rare earth elements from the stock solution with an organic phase containing an extractant; (3) washing the organic phase obtained after extraction in step (2) with a washing solution to move rare earth elements into the aqueous phase and leave thorium in the organic phase; (4) back-extracting the organic phase containing thorium obtained in step (3) with a back-extraction solution to extract move thorium in the organic phase into the aqueous phase. The extractant contains alkyl phosphonic acid monoalkyl ester and dialkylphosphinic acid.