Method for synchronously extracting and separating uranium and molybdenum

An extraction and volume percentage technology, applied in the field of hydrometallurgy, can solve the problems of high investment, increase the difficulty and cost of wastewater treatment, and achieve the effects of reducing accumulation, reducing the amount of suspended solids and reducing consumption.

Inactive Publication Date: 2016-04-13
BEIJING RESEARCH INSTITUTE OF CHEMICAL ENGINEERING AND METALLURGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

The above two methods include the introduction of chloride ions and ammonia ions. Chloride ions have high requirements for equipment anti-corrosion and are not suitable for non-chlorine leaching systems, while ammonia roots require large-scale ammonia circulation equipment, which requires high investment. In addition, a large amount of Chloride ion and ammonia ion wastewater will increase the difficulty and cost of wastewater treatment

Method used

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  • Method for synchronously extracting and separating uranium and molybdenum

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0020] Extraction solution: pH0.73, ρ(U)0.64 / L, ρ(Mo)8.12g / L, ρ(SiO 2 )0.25g / L, ρ(SO 4 2- ) 121.9g / L, ρ(Al) 1.13g / L, ρ(∑Fe) 2.24g / L, Eh-410mV.

[0021] Co-extracted uranium and molybdenum organic phase: 7.5% N235+20% TBP+72.5% sulfonated kerosene

[0022] Co-extraction of uranium and molybdenum operating conditions: comparison: O / A=3, flow ratio A / O=1.5, contact time 3min.

[0023] Organic phase loaded with uranium and molybdenum: ρ(Mo) 12.1g / L, ρ(U) 0.94g / L

[0024] Uranium molybdenum raffinate aqueous phase: ρ(Mo)<20mg / L, ρ(U)<5mg / L

[0025] Molybdenum-uranium-loaded organic reverse extraction of uranium: stripping agent: 200g / L sulfuric acid solution

[0026] Operating conditions for stripping uranium: comparison: O / A=1.5, flow ratio A / O=4, contact time 3min

[0027] Uranium stripping solution: ρ(U)~3.7g / L

[0028] Re-extracted uranium organic phase composition: 5% P204+5% TBP+90% sulfonated kerosene

[0029] Operating conditions for re-extracting uranium: compariso...

Embodiment 2

[0037] Extraction solution: pH0.64, ρ(U)0.667 / L, ρ(Mo)6.28g / L, ρ(SiO 2 )0.29g / L, ρ(SO 4 2- ) 101.9g / L, ρ(Al) 1.28g / L, ρ(∑Fe) 1.934g / L, Eh-408mV.

[0038] Co-extracted uranium and molybdenum organic phase: 7.5% N235+20% TBP+72.5% sulfonated kerosene

[0039] Co-extraction of uranium and molybdenum operating conditions: comparison: O / A=3, flow ratio A / O=2, contact time 3min.

[0040] Organic phase loaded with uranium and molybdenum: ρ(Mo)~12.5g / L, ρ(U)~1.31g / L

[0041] Uranium molybdenum raffinate aqueous phase: ρ(Mo)<20mg / L, ρ(U)<5mg / L

[0042] Molybdenum-uranium-loaded organic reverse extraction of uranium: stripping agent: 200g / L sulfuric acid solution

[0043] Operating conditions for stripping uranium: comparison: O / A=1.5, flow ratio A / O=3, contact time 3min

[0044] Uranium stripping solution: ρ(U)~3.9g / L

[0045] Re-extracted uranium organic phase composition: 5% P204+5% TBP+90% sulfonated kerosene

[0046] Operating conditions for re-extracting uranium: compariso...

Embodiment 3

[0054]Extraction solution: pH0.84, ρ(U)1.34 / L, ρ(Mo)5.84g / L, ρ(SiO 2 )0.232g / L, ρ(SO 4 2- ) 114.2g / L, ρ(Al) 0.98g / L, ρ(∑Fe) 2.38g / L, Eh-389mV.

[0055] Co-extracted uranium and molybdenum organic phase: 7.5% N235+20% TBP+72.5% sulfonated kerosene

[0056] Co-extraction of uranium and molybdenum operating conditions: comparison: O / A=3, flow ratio A / O=2, contact time 3min.

[0057] Organic phase loaded with uranium and molybdenum: ρ(Mo)~11.6g / L, ρ(U)~2.6g / L

[0058] Uranium molybdenum raffinate aqueous phase: ρ(Mo)<20mg / L, ρ(U)<5mg / L

[0059] Molybdenum-uranium-loaded organic reverse extraction of uranium: stripping agent: 200g / L sulfuric acid solution

[0060] Operating conditions for stripping uranium: comparison: O / A=1.5, flow ratio A / O=1.5, contact time 3min

[0061] Uranium stripping solution: ρ(U)~3.9g / L

[0062] Re-extracted uranium organic phase composition: 5% P204+5% TBP+90% sulfonated kerosene

[0063] Operating conditions for re-extracting uranium: comparison...

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Abstract

The invention belongs to the technical field of hydrometallurgy, and particularly relates to a method for synchronously extracting and separating uranium and molybdenum. Overcoming the defects in the prior art is the purpose, a method for acid leaching of uranium and molybdenum in a solution is provided, wherein the method is simple in technology, high in uranium and molybdenum recycling rate, capable of not introducing complex ions and environmental-friendly, and the method is suitable for industrial application. Efficient uranium and molybdenum separation can be achieved through N235 uranium and molybdenum co-extraction-200 g / L sulfuric acid solution uranium back extraction-ammonium hydroxide molybdenum back extraction-P204 uranium re-extraction-Na2CO3 uranium repeated back extraction, and the uranium and molybdenum extraction rate is high and can reach more than 99.5%. The contact frequency between an extraction stock solution and an organic phase can be reduced through co-extraction of uranium and molybdenum, the generating amount of suspended matter in the extraction residual water phase is reduced, and the entrainment loss of the organic phase is reduced. Circular utilization of a P204 extraction residual solution (200 g / L sulfuric acid solution) is achieved, and the consumption amount of reagent sulfuric acid is reduced. The accumulation of sodium sulfate in the uranium sediment motor liquor can be reduced. The complex ions hard to treat are not introduced in the whole technology process, and later waste water treatment is facilitated.

Description

technical field [0001] The invention belongs to the technical field of hydrometallurgy, and in particular relates to a method for synchronously extracting and separating uranium and molybdenum. Background technique [0002] There are many extraction and separation methods for uranium and molybdenum, and the commonly used separation methods include selective precipitation, extraction and separation, and ion exchange. [0003] The selective precipitation method is divided into two types, the diuranate precipitation method and the lead salt selective precipitation method. The diuranate precipitation method is suitable for treating feed solutions with high uranium content and low molybdenum concentration (uranium molybdenum in the solution Concentration ratio greater than 15), when processing low-concentration uranium solution, a large amount of waste water and waste salt will be produced, and the utilization rate of residual acid and alkali in the leaching solution is low; whil...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C22B60/02C22B34/34C22B3/40
CPCC22B34/34C22B60/026C22B3/26
Inventor 向秋林师留印杨剑飞曾毅君刘会武刘忠臣陈天宝黄永刘智
Owner BEIJING RESEARCH INSTITUTE OF CHEMICAL ENGINEERING AND METALLURGY
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