CN105838877B - A kind of method of soda acid process integration Leaching Uranium from low-grade uranium ore - Google Patents

A kind of method of soda acid process integration Leaching Uranium from low-grade uranium ore Download PDF

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CN105838877B
CN105838877B CN201610424028.7A CN201610424028A CN105838877B CN 105838877 B CN105838877 B CN 105838877B CN 201610424028 A CN201610424028 A CN 201610424028A CN 105838877 B CN105838877 B CN 105838877B
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uranium
leaching
ore
low
uranium ore
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CN105838877A (en
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李密
张晓文
黄婧
丁德馨
房琦
谢超
唐东山
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University of South China
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    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22BPRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B3/00Extraction of metal compounds from ores or concentrates by wet processes
    • C22B3/04Extraction of metal compounds from ores or concentrates by wet processes by leaching
    • C22B3/12Extraction of metal compounds from ores or concentrates by wet processes by leaching in inorganic alkaline solutions
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22BPRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B3/00Extraction of metal compounds from ores or concentrates by wet processes
    • C22B3/04Extraction of metal compounds from ores or concentrates by wet processes by leaching
    • C22B3/06Extraction of metal compounds from ores or concentrates by wet processes by leaching in inorganic acid solutions, e.g. with acids generated in situ; in inorganic salt solutions other than ammonium salt solutions
    • C22B3/08Sulfuric acid, other sulfurated acids or salts thereof
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22BPRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02Obtaining thorium, uranium, or other actinides
    • C22B60/0204Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0217Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
    • C22B60/0221Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching
    • C22B60/0226Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors
    • C22B60/0234Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors sulfurated ion as active agent
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22BPRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02Obtaining thorium, uranium, or other actinides
    • C22B60/0204Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0217Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
    • C22B60/0221Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching
    • C22B60/0247Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using basic solutions or liquors

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  • Engineering & Computer Science (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Geology (AREA)
  • Environmental & Geological Engineering (AREA)
  • Manufacturing & Machinery (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Geochemistry & Mineralogy (AREA)
  • Inorganic Chemistry (AREA)
  • Manufacture And Refinement Of Metals (AREA)

Abstract

The invention discloses a kind of method of soda acid process integration Leaching Uranium from low-grade uranium ore.It is an object of the invention to provide a kind of method of soda acid process integration Leaching Uranium from low-grade uranium ore.It is a feature of the present invention that following steps:A. uranium ore after alkali leaching is obtained with the low-grade uranium ore of dipping by lye to destroy gangue content;B. low-grade uranium ore leachate is obtained to uranium ore leaching after step A alkali leaching with sulfuric acid.The granularity of the low-grade uranium ore is 75 400 μm.The alkali lye is sodium carbonate or sodium hydroxide solution, and concentration of lye is 10 20g/l.Liquid-solid ratio between the alkali lye and the uranium ore soaked is 10:1‑15:1, while mixing slowly using 200 300r/min, soak time is 1 1.5h.The low-grade uranium ore is the uranium ore that uranium content is 0.008 0.04%.The sulfuric acid concentration is 50 80g/l, sulfuric acid:The liquid-solid ratio of ore is 15 20:1, extraction time is 0.5 1h, the 600r/min of mixing speed 400.Present invention is mainly used for the Leaching Uranium from low-grade uranium ore.

Description

A kind of method of soda acid process integration Leaching Uranium from low-grade uranium ore
Technical field
Leached the present invention relates to a kind of method of Leaching Uranium, more particularly to a kind of soda acid process integration from low-grade uranium ore The method of uranium.
Background technology
With the development of Nuclear Power Industry, the demand of natural uranium is growing, in the explored uranium deposit of China, exploits bar Part is good, grade is high, occurrence condition and ore body scale are preferably available for the uranium ore of exploitation few in number, remaining uranium ore resource In the majority with Low-grade uranium ore, with gangue content is high, ore deposit is mutually complicated, the characteristics of be difficult to reclaim.Therefore, uranium in low-grade uranium ore Extraction be increasingly becoming the emphasis of following exploitation.The composition of Low-grade uranium ore is based on silicate gangue, the uranium of extremely low content (0.008%~0.04%) is scattered in gangue mineral in the form of fine, and conventional uranium recovery technology includes acid soak at present Go out and alkaline leaching.Acidic leaching has the advantages that leaching velocity is fast, cost is low, leaching rate is higher, but for low-grade uranium ore For, due to parcel of the gangue particle to uranium thing phase, cause leaching agent to be difficult to be in contact with uranium thing, therefore uranium in conventional acidleach Leaching rate is generally below 70%, although a series of subsequent development Strengthen education means (such as concentrated acid curings, high ferro leaching), but It is restricted because the problems such as reinforcing cost is high, leachate impurity is more, secondary pollution is serious, making to apply.Though alkaline leaching technique Gangue structure can be so destroyed, leachate impurity content is low, but leaching velocity is slow.Based on this, the present invention fully combine acidleach and The advantage of alkali leaching, the method for proposing soda acid combined treatment process Leaching Uranium from low-grade uranium ore.Its basic ideas is sharp first Micropore is leached in the gangue structure destroyed with alkali in uranium ore, manufacture, is then recycled diluted acid leaching uranium, can both be dissociateed uranium Come, improve the leaching rate of uranium, while leaching velocity is fast, the entrance of other impurity is not resulted in during diluted acid leaching yet.
The content of the invention
It is an object of the invention to provide a kind of method of soda acid process integration Leaching Uranium from low-grade uranium ore, to improve The leaching velocity and leaching rate of uranium, meanwhile, acidleach process there will not be other impurities entrance.
To achieve the above object, technical solution of the invention is:A kind of soda acid process integration is from low-grade uranium ore The method of Leaching Uranium, it is characterised in that following steps:
A. uranium ore after alkali leaching is obtained with the low-grade uranium ore of dipping by lye to destroy gangue content;
B. low-grade uranium ore leachate is obtained to uranium ore leaching after step A alkali leaching with sulfuric acid.
The granularity of the low-grade uranium ore is 75-400 μm.
The alkali lye is sodium carbonate or sodium hydroxide solution, and concentration of lye is 10-20g/l.
Liquid-solid ratio between the alkali lye and the uranium ore soaked is 10:1-15:1, while using 200-300r/min Mix slowly, soak time is 1-1.5h.
The low-grade uranium ore is the uranium ore that uranium content is 0.008-0.04%.
The sulfuric acid concentration is 50-80g/l, sulfuric acid:The liquid-solid ratio of ore is 15-20:1, extraction time is 0.5-1h, is stirred Mix speed 400-600r/min.
The beneficial effects of the invention are as follows:
(1) substantial amounts of silica gangue structure is contained in uranium ore, weak base can destroy silica gangue structure;
(2) weak caustic solution can be recycled;
(3) corrosion of the weak-acid leaching process to equipment is small;
(4) the overall leaching rate of uranium is more conventional leaches height.
Brief description of the drawings
Fig. 1 is the process chart of the present invention.
Embodiment
The present invention and its embodiment are described in further detail with reference to the accompanying drawings and examples.
Referring to Fig. 1, it is a feature of the present invention that following steps:
A. uranium ore after alkali leaching is obtained with the low-grade uranium ore of dipping by lye to destroy gangue content;
B. low-grade uranium ore leachate is obtained to uranium ore leaching after step A alkali leaching with sulfuric acid.
The granularity of the low-grade uranium ore is 75-400 μm.
The alkali lye is sodium carbonate or sodium hydroxide solution, and concentration of lye is 10-20g/l.
Liquid-solid ratio between the alkali lye and the uranium ore soaked is 10:1-15:1, while using 200-300r/min Mix slowly, soak time is 1-1.5h.
The low-grade uranium ore is the uranium ore that uranium content is 0.008-0.04%.
The sulfuric acid concentration is 50-80g/l, sulfuric acid:The liquid-solid ratio of ore is 15-20:1, extraction time is 0.5-1h, is stirred Mix speed 400-600r/min.
Embodiments of the invention given below.
Embodiment 1
100g uranium ores (uranium content 0.008%) are taken, particle diameter is 75 microns, in 20g/l Na2CO3Soaked in solution, The liquid-solid ratio that alkali lye is controlled between the uranium ore that is soaked is 10:1, mixing speed is 200r/min, and alkali soak time is 1.5h, filter residue uses 50g/L sulfuric acid leaching, in sulfuric acid:The liquid-solid ratio of ore is 15:1, mixing speed 500r/min condition Lower leaching 1h, total leaching rate of uranium is 88.2%.
Embodiment 2
100g uranium ores (uranium content 0.008%) are taken, particle diameter is 400 microns, is soaked in 20g/l NaOH solution, The liquid-solid ratio that alkali lye is controlled between the uranium ore that is soaked is 15:1, mixing speed is 200r/min, and alkali soak time is 1h, Filter residue uses 60g/L sulfuric acid leaching, in sulfuric acid:The liquid-solid ratio of ore is 15:Stirred under conditions of 1, mixing speed 500r/min Leaching 1h is mixed, total leaching rate of uranium is 87.1%.
Embodiment 3
100g uranium ores (uranium content 0.008%) are taken, particle diameter is 200 microns, is soaked in 10g/l NaOH solution, The liquid-solid ratio that alkali lye is controlled between the uranium ore that is soaked is 15:1, mixing speed is 300r/min, and alkali soak time is 1.25h, filter residue uses 60g/L sulfuric acid leaching, in sulfuric acid:The liquid-solid ratio of ore is 20:1, mixing speed 500r/min bar Leaching 0.5h under part, total leaching rate of uranium is 86.5%.
Embodiment 4
100g uranium ores (uranium content 0.04%) are taken, particle diameter is 200 microns, is soaked in 10g/l NaOH solution, is controlled Liquid-solid ratio between alkaline liquid and the uranium ore soaked is 15:1, mixing speed is 300r/min, and alkali soak time is 1h, filter Slag uses 80g/L sulfuric acid leaching, in sulfuric acid:The liquid-solid ratio of ore is 20:Stirred under conditions of 1, mixing speed 400r/min 0.5h is leached, total leaching rate of uranium is 85.4%.
Embodiment 5
100g uranium ores (uranium content 0.02%) are taken, particle diameter is 100 microns, in 20g/l Na2CO3Soaked in solution, The liquid-solid ratio that alkali lye is controlled between the uranium ore that is soaked is 12:1, mixing speed is 300r/min, and alkali soak time is 1.5h, filter residue uses 70g/L sulfuric acid leaching, in sulfuric acid:The liquid-solid ratio of ore is 20:1, mixing speed 500r/min condition Lower leaching 1h, total leaching rate of uranium is 90.5%.
It is an object of the invention to provide a kind of method of the Leaching Uranium from low-grade uranium ore, step is first to be soaked using alkali, is broken Micropore is leached in gangue structure in bad uranium ore, manufacture, is tentatively realized the separation of uranium thing phase and gangue, is then recycled acidleach, To strengthen the leaching effect of uranium.
The technical scheme of soda acid process integration Leaching Uranium from low-grade uranium ore must be comprised the steps of, can be only achieved this The purpose of invention:
(1) first low-grade uranium ore is soaked using weak caustic solution, makes the gangue structure in uranium ore by partial destruction, reach To the purpose that uranium thing phase is separated with gangue is tentatively realized, weak-acid leaching is then used again, uranium is entered in solution, and the two order is not Can be reverse.
(2) species of alkali can be sodium hydroxide or sodium carbonate, and concentration must be controlled in 10~20g/L, and concentration is too low can not Gangue structure is destroyed, concentration is too high to cause gangue largely to dissolve, and the dissociation to follow-up uranium brings difficulty.
(3) liquid-solid ratio is controlled 10 during dipping by lye uranium ore:1~15:1, while using mixing slowly, stirring is fast Degree control is controlled in 1~1.5h in 200~300r/min, extraction time, and extraction time is oversize to cause a large amount of dissolvings of gangue, And colloidal magnesium salt material is formed, the dissociation of uranium during hindered acid leaching.
(4) soaking the alkali lye of uranium ore can recycle, and keep pH value between 10-12, when pH value is less than 10 Supplement sodium carbonate or sodium hydroxide solution.
(5) during dilute sulfuric acid leaching, sulfuric acid concentration is 50~80g/l, liquid-solid ratio 15~20:1, extraction time 0.5~1h, 400~600r/min of mixing speed.Sulfuric acid concentration is too high to cause leachate impurity content high, while can also make leaching The uranium gone out in liquid is adsorbed in leached mud again, causes the overall leaching rate of uranium to decline.
The present invention is the leaching ability of the damage capability and dilute sulfuric acid that make full use of alkali to gangue mineral to uranium, specific Extract technology under the conditions of, uranium in uranium ore is entered in solution, lack conditions above, it is impossible to reach the purpose of the present invention.Its Advantage is:(1) substantial amounts of silica gangue structure is contained in uranium ore, weak base can destroy silica gangue structure;(2) Weak caustic solution can be recycled;(3) corrosion of the weak-acid leaching process to equipment is small;(4) the overall leaching rate of uranium is more conventional leaches It is high.
The general principle of the present invention is as follows:
Uranium ore adds alkali to be soaked, and can destroy the gangue contents such as the silica in uranium ore, by controlling soaking technology Parameter, is partly dissolved the gangue content in uranium ore, surface corrosion is formed, so that then uranium can again be adopted with gangue initial gross separation With weak-acid leaching can by uranium from uranium ore high efficiency extraction comes out, its key point be to control the concentration of alkali, alkali soak time and Weak-acid leaching technological parameter, is otherwise easily caused alkali immersion treatment excessively, and substantial amounts of uranium is entered the damage for causing uranium in alkali lye Lose, or because the control of acidleach condition is improper, cause leachate impurity component high, the further separation to follow-up uranium causes difficulty.

Claims (1)

1. a kind of method of soda acid process integration Leaching Uranium from low-grade uranium ore, it is characterised in that following steps:
A. uranium ore after alkali leaching is obtained, the low-grade uranium ore is that uranium contains with the low-grade uranium ore of dipping by lye to destroy gangue content The uranium ore for 0.008-0.04% is measured, the granularity of the low-grade uranium ore is 75-400 μm, and the alkali lye is sodium carbonate or hydrogen Sodium hydroxide solution, concentration of lye is 10-20g/l, and the liquid-solid ratio between the alkali lye and the uranium ore soaked is 10:1-15: 1, while mixing slowly using 200-300r/min, soak time is 1-1.5h;
B. low-grade uranium ore leachate is obtained, the sulfuric acid concentration is to uranium ore leaching after step A alkali leaching with sulfuric acid 50-80g/l, sulfuric acid:The liquid-solid ratio of ore is 15-20:1, extraction time is 0.5-1h, mixing speed 400-600r/min.
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CN111499365B (en) * 2020-04-22 2022-05-20 宜宾学院 Method for whitening weathered sandstone through acid-base combined treatment
CN113265540B (en) * 2021-04-14 2023-10-03 东华理工大学 Method for extracting uranium from low-grade uranium ores through microwave activation roasting reinforcement
CN113477393B (en) * 2021-08-10 2022-10-28 南华大学 Method for leaching uranium from pyrite-containing carbonate type uranium ore

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4340252A (en) * 1979-05-07 1982-07-20 Mobil Oil Corporation Process for the in-situ leaching of uranium

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4340252A (en) * 1979-05-07 1982-07-20 Mobil Oil Corporation Process for the in-situ leaching of uranium

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
采用HF和HClO4从铀尾矿中浸出铀的试验研究;李密 等;《中国矿业大学学报》;20160531;第45卷(第3期);第639-645页 *
铀尾矿酸浸过程中的矿物学性质变化研究;李密 等;《南华大学学报(自然科学版)》;20160331;第30卷(第1期);第11-16页 *

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