A method for separating nickel-molybdenum uranium ore

By using flotation and anion exchange resin treatment to process nickel-molybdenum-uranium ore, the problem of separating nickel, molybdenum and uranium was solved, the resource recovery rate was improved and uranium pollution was reduced, and efficient beneficiation and separation of nickel-molybdenum-uranium ore was achieved.

CN112827642BActive Publication Date: 2026-04-17NANHUA UNIV
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Patent Information

Application Number
CN202011493520.2
Authority / Receiving Office
CN · China
Patent Type
Patents(China)
Current Assignee / Owner
Filing Date
2020-12-17
Publication Date
2026-04-17
Estimated Expiration
2040-12-17

AI Technical Summary

Technical Problem

Existing technologies are insufficient for the effective separation and recovery of nickel, molybdenum, and uranium, leading to resource waste and uranium pollution.

Method used

Nickel-molybdenum-uranium ore is mixed with dispersants, activators, inhibitors, collectors and frothers for frothing and flotation, followed by acid leaching and treatment with a strongly basic anion exchange resin, including solid-liquid separation, rinsing and pH adjustment, to obtain nickel-molybdenum concentrate and uranium concentrate.

Benefits of technology

It achieves high recovery rates of nickel and molybdenum (greater than 80%), and uranium leaching and recovery rates (greater than 96%), reducing resource waste and uranium pollution.

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Abstract

This invention provides a method for separating nickel-molybdenum-uranium ore through beneficiation and metallurgy, belonging to the field of beneficiation and metallurgical technology. The separation method provided by this invention includes the following steps: mixing nickel-molybdenum-uranium ore, a dispersant, an activator, an inhibitor, a collector, and a frother, followed by sequential frothing and flotation to obtain nickel-molybdenum concentrate and uranium-bearing tailings; subjecting the uranium-bearing tailings to acid leaching to obtain a leachate and tailings; adsorbing the leachate with a strongly basic anion exchange resin, followed by sequential solid-liquid separation, rinsing, and pH adjustment to obtain a uranium concentrate. Example results show that the recovery rates of nickel and molybdenum obtained by this invention are greater than 80%, the uranium leaching rate is greater than 96%, and the uranium recovery rate is greater than 91%.
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