C22B34/34

Opportunities for recovery augmentation process as applied to molybdenum production

A copper/molybdenum separation processor is provided featuring a slurry/media mixture stage configured to receive a conditioned pulp containing hydrophobic molybdenite and hydrophilic copper, iron and other minerals that is conditioned with sodium hydrosulfide together with an engineered polymeric hydrophobic media, and provide a slurry/media mixture; and a slurry/media separation stage configured to receive the slurry/media mixture, and provide a slurry product having a copper concentrate and a polymerized hydrophobic media product having a molybdenum concentrate that are separately directed for further processing. The slurry/media mixture stage include a molybdenum loading stage configured to contact the conditioned pulp with the engineered polymeric hydrophobic media in an agitated reaction chamber, and load the hydrophobic molybdenite on the engineered polymeric hydrophobic media.

Purification process
10767243 · 2020-09-08 · ·

A process for purifying Mo-99 from an acidic solution obtained by dissolving an irradiated solid target comprising uranium in an acidic medium, or from an acidic solution comprising uranium and which has previously been irradiated in a nuclear reactor, or from an acidic solution comprising uranium and which has been used as reactor fuel in a homogeneous reactor, the process comprising contacting the acidic solution with an adsorbent comprising a zirconium oxide, zirconium hydroxide, zirconium alkoxide, zirconium halide and/or zirconium oxide halide, and eluting the Mo-99 from the adsorbent using a solution of a strong base, the eluate then being subjected to a subsequent purification process involving an alkaline-based Mo-99 chromatographic recovery step on an anion exchange material. Also provided is apparatus for carrying out the process.

Purification process
10767243 · 2020-09-08 · ·

A process for purifying Mo-99 from an acidic solution obtained by dissolving an irradiated solid target comprising uranium in an acidic medium, or from an acidic solution comprising uranium and which has previously been irradiated in a nuclear reactor, or from an acidic solution comprising uranium and which has been used as reactor fuel in a homogeneous reactor, the process comprising contacting the acidic solution with an adsorbent comprising a zirconium oxide, zirconium hydroxide, zirconium alkoxide, zirconium halide and/or zirconium oxide halide, and eluting the Mo-99 from the adsorbent using a solution of a strong base, the eluate then being subjected to a subsequent purification process involving an alkaline-based Mo-99 chromatographic recovery step on an anion exchange material. Also provided is apparatus for carrying out the process.

METHOD FOR PREPARING HIGH-MELTING-POINT METAL POWDER THROUGH MULTI-STAGE DEEP REDUCTION

The invention relates to a method for preparing high-melting-point metal powder through multi-stage deep reduction, and belongs to the technical field of preparation of powder. The method includes the following steps of mixing dried high-melting-point metal oxide powder with magnesium powder and performing a self-propagating reaction, placing an intermediate product into a closed reaction kettle, leaching the intermediate product with hydrochloric acid as a leaching solution so as to obtain a low-valence oxide Me.sub.xO precursor of the low-valence high-melting-point metal; uniformly mixing the precursor with calcium powder, pressing the mixture, placing the pressed mixture into a vacuum reduction furnace, heating the vacuum reduction furnace to 700-1200 C., performing deep reduction for 1-6 h, leaching a deep reduction product with hydrochloric acid as a leaching solution and performing treatment, so as to obtain the high-melting-point metal powder.

Methods of separating medical isotopes from uranium solutions
10734126 · 2020-08-04 · ·

Provided are methods to separate an isotope from a first solution including uranium. The methods may include (a) cleaning the first solution to form a second solution including the uranium and a third solution including the isotope; (b) oxidizing the third solution to form an oxidized isotope; and (c) separating the oxidized isotope.

PROCESS FOR THE SELECTIVE REMOVAL OF COPPER COMPOUNDS AND OTHER IMPURITIES WITH RESPECT TO MOLYBDENUM AND RHENIUM, FROM MOLYBDENITE CONCENTRATES

Disclosed is a process for the selective removal of copper compounds, and other impurities with respect to molybdenum and rhenium, from concentrates of molybdenite (MoS.sub.2) with a copper content that is higher than 0.5% in dry weight.

PROCESS FOR THE SELECTIVE REMOVAL OF COPPER COMPOUNDS AND OTHER IMPURITIES WITH RESPECT TO MOLYBDENUM AND RHENIUM, FROM MOLYBDENITE CONCENTRATES

Disclosed is a process for the selective removal of copper compounds, and other impurities with respect to molybdenum and rhenium, from concentrates of molybdenite (MoS.sub.2) with a copper content that is higher than 0.5% in dry weight.

SEPARATION OF COPPER AND MOLYBDENUM SULFIDES FROM PYRITE USING A SEA WATER/DESALINATED WATER HYBRID PROCESS
20200040428 · 2020-02-06 ·

A copper/molybdenum separation system uses sea water in the roughing circuit and desalinated water in cleaning circuit. In both roughing circuit and cleaning circuit, hydrophobic engineered media are used to recover the mineral particles of interest. The cleaning circuit includes a molybdenum loading stage configured to contact the conditioned pulp with the engineered media in an agitated reaction chamber, and load the hydrophobic molybdenite on the engineered media.

SEPARATION OF COPPER AND MOLYBDENUM SULFIDES FROM PYRITE USING A SEA WATER/DESALINATED WATER HYBRID PROCESS
20200040428 · 2020-02-06 ·

A copper/molybdenum separation system uses sea water in the roughing circuit and desalinated water in cleaning circuit. In both roughing circuit and cleaning circuit, hydrophobic engineered media are used to recover the mineral particles of interest. The cleaning circuit includes a molybdenum loading stage configured to contact the conditioned pulp with the engineered media in an agitated reaction chamber, and load the hydrophobic molybdenite on the engineered media.

Preparation of chitosan-based microporous composite material and its applications

Microporous glutaraldehyde-crosslinked chitosan sorbents include a plurality of nanoparticles of a high Z element. The nanoparticles are disposed in the cross-linked chitosan-gluteraldehyde composite matrix and integrated with the cross-linked chitosan-gluteraldehyde composite matrix to reduce primary impact of high radiation flux and minimize radiolytic effect on said cross-linked chitosan-gluteraldehyde composite matrix. The plurality of nanoparticles is made from the high Z element such as hafnium (Hf). Methods of making and using the microporous glutaraldehyde-crosslinked chitosan sorbents, and a generator for the radioisotope .sup.99Mo containing the sorbents.