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Method for preparing triuranium octoxide from selective solution slag

A technology of U3O8 and melting slag, which is applied in the field of preparation of U3O8, can solve the problems of certain difficulty in the clarity of the extraction liquid and difficult filtration, and achieve simplified extraction liquid system, complete separation of uranium and thorium, and high product quality Effect

Pending Publication Date: 2020-07-14
湖南中核金原新材料有限责任公司 +1
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

The solid-liquid separation form of this method is plate-and-frame filtration, which is difficult to filter and has certain difficulties in ensuring the clarity of the extraction solution, and this method is only applicable to the hydrochloric acid system, and the thorium content limit is not mentioned in the uranium products. , and the product form is diuranate

Method used

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  • Method for preparing triuranium octoxide from selective solution slag

Examples

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Effect test

example 1

[0071] In the sulfuric acid leaching slurry of an excellent slag, the uranium concentration is 1.05g / L, the thorium concentration is 21.1g / L, and the sulfuric acid concentration is 10.4g / L.

[0072] The leaching slurry is centrifuged by a decanter centrifuge with a rotating speed of 3000r / min and a residence time of 0.8min. The solid content of the leaching pulp is 4.1%. D231 resin was used to adsorb the leached pulp, and the uranium content on the obtained loaded resin was 45 mg / g dry resin, and the thorium content was 82 mg / g dry resin. Subsequently, 100g / L sulfuric acid solution was used to rinse the loaded resin, and the concentration of uranium in the qualified solution was 6.1g / L, and the concentration of thorium was 11.1g / L.

[0073] The eluting qualified liquid was extracted with 5% P204+2%TRPO+2%TBP+kerosene for 5-stage countercurrent extraction, the concentration of uranium in the loaded organic phase was 13.5g / L, and the concentration of thorium was 0.006g / L. The l...

example 2

[0075] In the sulfuric acid leaching slurry of an excellent slag, the uranium concentration is 0.51g / L, the thorium concentration is 10.2g / L, and the sulfuric acid concentration is 15.4g / L.

[0076] The leaching slurry is centrifuged by a decanter centrifuge with a rotating speed of 2800r / min and a residence time of 1min. The solid content of the leaching pulp is 2.1%. Using 201*7 resin to adsorb the leached pulp, the uranium content on the obtained loaded resin is 25mg / g dry resin, and the thorium content is 45mg / g dry resin. Then, 110g / L sulfuric acid solution was used to rinse the loaded resin, and the uranium concentration in the leaching qualified liquid was 3.3g / L, and the thorium concentration was 5.9g / L.

[0077] The eluting qualified solution was extracted with 2.5%P204+1.2%TRPO+2%TBP+kerosene for 6-stage countercurrent extraction, the concentration of uranium in the loaded organic phase was 8.5g / L, and the concentration of thorium was 0.008g / L. The load organic phas...

example 3

[0079] In the sulfuric acid leaching slurry of an excellent slag, the uranium concentration is 1.5g / L, the thorium concentration is 32g / L, and the sulfuric acid concentration is 20.4g / L.

[0080] The leaching slurry is centrifuged by a decanter centrifuge with a rotating speed of 3200r / min and a residence time of 0.9min. The solid content of the leaching pulp is 5.2%. D231 resin was used to adsorb the leached pulp, and the uranium content on the obtained loaded resin was 61 mg / g dry resin, and the thorium content was 98 mg / g dry resin. Subsequently, 120g / L sulfuric acid solution was used to rinse the loaded resin, and the uranium concentration in the leaching qualified solution was 8.2g / L, and the thorium concentration was 13.2g / L.

[0081] The eluting qualified solution was extracted with 7% P204 + 4% TRPO + 3% TBP + kerosene for four-stage countercurrent extraction, and the concentration of uranium in the loaded organic phase was 22.1g / L, and the concentration of thorium was...

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Abstract

The invention relates to the technical field of uranium extraction, and particularly discloses a method for preparing triuranium octoxide from selective solution slag, which comprises the following steps: step 1, leaching; step 2, centrifugal separation; step 3, adsorption; step 4, leaching; step 5, extraction; step 6, back extraction; 7, calcining. According to the method, centrifugal separationand slurry adsorption are combined, the problem of solid-liquid separation of the leached slurry is solved, industrialization is easy, and the method has the advantages of thorough uranium and thoriumseparation, high product quality and high practicability.

Description

technical field [0001] The invention belongs to the technical field of uranium extraction, and in particular relates to a method for preparing U3O8 from excellent molten slag. Background technique [0002] Excellent slag is the tailings rich in uranium and thorium left after the rare earth industry has extracted rare earths from monazite mines. Monazite is a valuable resource rich in rare earths, uranium and thorium. In my country, monazite has been mainly used to extract rare earth chloride for many years. When extracting rare earths, uranium and thorium resources are not recovered simultaneously but are left in the tailings, forming tens of thousands of tons of high-quality molten slag, which urgently needs comprehensive environmental protection utilization. The uranium content in the excellent slag is 0.4-1.0%, and the thorium content is 14-24%. Uranium has a certain recovery value. Although there is no industrial recovery example, it has been reported in some articles a...

Claims

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Application Information

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IPC IPC(8): C01G43/01
CPCC01G43/01C01P2006/80
Inventor 支梅峰舒祖骏王皓赵凤岐周志全牛玉清张永明常喜信
Owner 湖南中核金原新材料有限责任公司
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