Uranium-containing material extraction process control method

A process control and extraction technology, applied in the direction of program control, electrical program control, general control system, etc., can solve the problems of difficulty in guaranteeing the quality of extraction and stripping products, high labor intensity of workers, etc., and achieve stable acidity, purity and other indicators. Controllable, reduced uranium content, and improved stability
CN106929674AInactive Publication Date: 2017-07-07CNNC JIANZHONG NUCLEAR FUEL
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Patent Information

Authority / Receiving Office
CN Β· China
Current Assignee / Owner
CNNC JIANZHONG NUCLEAR FUEL
Publication Date
2017-07-07
Estimated Expiration
Not applicable Β· inactive patent

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Abstract

The invention relates to the technical field of treatment of uranium-containing waste materials during production of uranium dioxide powder and fuel pellets, in particular to a uranium-containing material extraction process control method. The method includes the steps of liquid level interlocking controlling over a liquid distribution tank and all liquid storing tanks, controlling over flows of all reaction media in the extraction process and the reextraction process, and controlling over the stirring speed of a mixer-settler. An electrical capacitance level meter is adopted for liquid level measurement; a putting-into-type liquid level meter is adopted for tributyl phosphate (TBP) liquid level measurement; a magnetic liquid level meter is adopted for nitric acid liquid level measurement; an electromagnetic flow meter is adopted for flow measurement of a uranyl nitrate solution; a mass flow meter is adopted for measurement of flow and density of a TBP extraction agent; and a metallic rotor flow meter is adopted for flow measurement of non-ionic water. The uranium-containing material extraction process control method is applied to production, the continuity, stability and the like of extraction production are greatly improved, the quality indexes including the uranium concentration, acidity, purity and other indexes of back water output to a precipitation station are stable and controllable, and the uranium content of waste water output to an adsorption station is greatly reduced.
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Description

technical field

[0001] The invention relates to the technical field of uranium-containing waste treatment in the production process of uranium dioxide powder and fuel pellets, in particular to a method for controlling the extraction process of uranium-containing materials. Background technique

[0002] In the production process of uranium dioxide powder and fuel pellets, various forms of uranium-containing wastes will be generated, and these uranium-containing wastes can be reused in the preparation of uranium dioxide powder and fuel pellets after recycling. Therefore, the recycling of uranium-containing waste can produce high economic benefits.

[0003] Extraction is an important process in the recycling process of uranium-containing waste. The uranyl nitrate solution from the dissolving post is firstly configured into a liquid with a certain uranium concentration and acidity (abbreviated as raw water) in the dosing tank. During the extraction process, a certain flow rate...

Claims

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