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

Inactive Publication Date: 2017-07-07
CNNC JIANZHONG NUCLEAR FUEL
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Problems solved by technology

[0005] In view of the above-mentioned prior art, the present invention provides a method for controlling the extraction process of uranium-containing materials, which is used to solve the problem that th

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Embodiment Construction

[0023] The present invention will be described in detail below in conjunction with the accompanying drawings and specific embodiments.

[0024] Such as Figure 1 to Figure 3 Shown, a kind of uranium-containing material extraction process control method of the present invention comprises the following steps:

[0025] For liquid level measurement, capacitive liquid level gauge is used for uranyl nitrate solution and wastewater liquid level measurement with conductive characteristics, an input liquid level gauge is used for non-conductive TBP liquid level, and magnetic flap liquid level is used for highly corrosive nitric acid liquid level count.

[0026] For flow measurement, raw water with conductivity and unstable density uses electromagnetic flowmeters, mass flowmeters are used to measure the flow and density of TBP (mass flowmeters can measure flow and density at the same time), and non-ionized water uses cost-effective metal Rotameter.

[0027] Step 1. Automatic interloc...

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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.

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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Application Information

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IPC IPC(8): C22B3/26C22B60/02G05B19/05
CPCC22B60/026G05B19/05G05B2219/25268
Inventor 王建卫王来革周海涛鲁小兵王兴刚石磊王溯刘利星蒋斌
Owner CNNC JIANZHONG NUCLEAR FUEL
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