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Method for directly dissolving uranium dioxide or spent fuel oxides with ionic liquid

An ionic liquid, iron-based ionic liquid technology, applied in reactor fuel elements, radioactive purification, reduction of greenhouse gases, etc., can solve the problems of high operating temperature, strict protection requirements, not meeting the requirements of green chemistry development, etc., and achieve good economy. , the effect of high dissolution efficiency

Active Publication Date: 2014-05-07
PEKING UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

Because these molten salts generally become liquid at high temperatures, there are some defects in the post-processing technology: high operating temperature, increased vapor pressure of radionuclides, strict protection requirements, serious corrosion of equipment, and the process needs to be carried out under the protection of an inert atmosphere. Can only be done in closed equipment
Although these two gaseous oxidants have the characteristics of fast dissolution rate and no introduction of impurities into the dissolved system, they are both toxic and do not meet the development requirements of green chemistry. Therefore, we hope to find a non-toxic or less oxidant in the ionic liquid system. Toxic oxidizing agent to dissolve uranium dioxide

Method used

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  • Method for directly dissolving uranium dioxide or spent fuel oxides with ionic liquid
  • Method for directly dissolving uranium dioxide or spent fuel oxides with ionic liquid
  • Method for directly dissolving uranium dioxide or spent fuel oxides with ionic liquid

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0028] Example 1[Bmim]FeCl 4 、[Bdmim]FeCl 4 and [Emim]FeCl 4 UO in ionic liquid 2 Dissolution studies of

[0029] [Bmim]FeCl 4 、[Bdmim]FeCl 4 and [Emim]FeCl 4 Pipette 1ml of the ionic liquid into the reaction bottle, and then add 40.3mg of UO 2 , Stir the reaction in an oil bath at 160°C. After reacting for 2 hours, the reaction system still had a black slurry, and after continuing to react for 8 hours, the reaction system still did not become clear. After fully shaking, draw a small amount of reaction solution into a 10ml plastic centrifuge tube, dilute with acetone and centrifuge to separate unreacted UO 2 , and then spin off acetone with HNO at a pH of about 2 3 After diluting to an appropriate concentration, perform ICP-AES test. When drawing the uranium calibration curve, it is necessary to add the same amount of iron-based ionic liquid as the test sample to offset the interference of the matrix. It is found that the uranium concentration in the uranium standard...

Embodiment 2

[0030] Example 2[Bmim]FeCl 4 、[Bdmim]FeCl 4 and [Emim]FeCl 4 Adding its corresponding imidazolium chloride salt to the ionic liquid on 2 Dissolution studies

[0031] In 1.0ml iron-based ionic liquid, add its corresponding imidazolium chloride salt in an equimolar amount, then add 50.2mg UO to the reaction bottle 2 ,, The reaction was carried out in an oil bath at 160°C. After reacting for 2 hours, the reaction system became clear without black insoluble matter. After that, add a certain amount of UO to the reaction bottle every 2h 2 , until the final reaction system has black insoluble matter. Then, the dissolved uranium content was analyzed by ICP-AES according to the same method as above, and the test results showed that after adding imidazolium chloride salt in an equimolar amount to the iron-based ionic liquid, 286 mg of UO could be dissolved in every milliliter of iron-based ionic liquid 2 .

Embodiment 3

[0032] Embodiment 3 Reaction temperature is to UO in the mixed ionic liquid 2 Effect of dissolution

[0033] In 1.0ml of iron-based ionic liquid, add its corresponding imidazolium chloride salt in an equimolar amount, and then add 25.3mg of UO 2 , three mixed ionic liquid systems were reacted in an oil bath at 40, 90, 120, 140 and 160 °C, respectively. Absorb a certain amount of reaction solution from the reaction system at regular intervals to analyze the dissolved uranium content within this time range. The results of the dissolved uranium with time at a reaction temperature of 140°C are shown in the appendix figure 1 ( figure 1 The three curves in the figure represent the mixed system of the iron-based ionic liquid and its corresponding imidazolium chloride salt respectively), and the effect of reaction temperature on the dissolution of uranium is characterized by fitting the apparent activation energy, see appendix figure 2 . The test results showed that [Bdmim]FeCl ...

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Abstract

The invention discloses a method for directly dissolving uranium dioxide or spent fuel oxides with ionic liquid. UO2 or spent fuel oxides are dissolved in iron (III)-containing ionic liquid directly, and no additional strong oxidants are needed to be added into the ionic liquid system. The method has advantages of high dissolution efficiency, good economical efficiency, green, environmental protection and the like. The method can be used for dissolution process of spent fuel reprocessing and also can be used for preparation and purification of uranium mine concentrates.

Description

technical field [0001] The invention relates to the technical field of spent fuel reprocessing, in particular to UO 2 Or a method in which spent fuel oxides are oxidized and dissolved in ionic liquids for separation and recovery. Background technique [0002] With the development of economy and society, human beings' demand for energy is increasing day by day, and energy development restricts economic construction. China has a large population and a relatively small amount of energy and minerals per capita. However, due to the widespread use of fossil energy, it is currently facing a severe energy crisis. Nuclear energy has many advantages. At present, the government's attitude towards the nuclear power industry has changed from "positive development" to "development as much as possible", which is of great significance to developing China. Due to the limited uranium resources, in order to maintain the sustainable development of nuclear power, it is necessary to reprocess s...

Claims

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Application Information

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IPC IPC(8): G21C19/44G21F9/28
CPCY02E30/30Y02W30/50
Inventor 褚泰伟姚爱宁
Owner PEKING UNIV
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