CN115985542A - Method for separating strontium ions and barium ions in high-level radioactive waste liquid - Google Patents
Method for separating strontium ions and barium ions in high-level radioactive waste liquid Download PDFInfo
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- CN115985542A CN115985542A CN202211400151.7A CN202211400151A CN115985542A CN 115985542 A CN115985542 A CN 115985542A CN 202211400151 A CN202211400151 A CN 202211400151A CN 115985542 A CN115985542 A CN 115985542A
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Abstract
The invention relates to a method for separating strontium ions and barium ions in high-level radioactive waste liquid, which comprises the following steps: preparing an extracting agent: mixing N, N, N ', N' -tetraoctyl-3-oxoglutaramide, tributyl phosphate and a diluent to form an extracting agent; acid regulation of high-level radioactive waste liquid: adding acid liquor into the high-level waste liquid to adjust the acidity; extraction and separation: and mixing the extracting agent with the acid-adjusted high-level radioactive waste liquid, carrying out extraction reaction, and completing the separation of strontium ions and barium ions in the high-level radioactive waste liquid after the balance is achieved. Compared with the prior art, the method can separate strontium ions from barium ions in the high-level liquid waste, and the single-stage extraction separation coefficient of strontium to barium ions is larger than 10.
Description
Technical Field
The invention relates to the field of spent fuel post-treatment, in particular to a method for separating strontium ions and barium ions in high-level radioactive waste liquid.
Background
After-treatment of spent fuelIn the process flow, the high-level radioactive waste liquid is high in radioactivity level and extremely strong in toxicity, more than 95% of radioactivity in the spent fuel is concentrated, potential harm is caused to human and the environment, and the problem of treatment and disposal of the high-level radioactive waste liquid becomes one of key factors restricting the sustainable development of nuclear energy. 90 Sr and its daughter 90 Y is a pure beta emitter, is an ideal material for manufacturing a beta radiation source and a nuclear battery, has special application in the fields of national defense, environmental science, biomedicine and the like, and has high practical value and economic significance.
The high-level radioactive waste liquid strontium has high content of barium of the same group element and similar properties, and is prepared to have certain purity 90 Sr solution, needs to be separated from barium ions in the Sr solution.
Disclosure of Invention
The invention aims to overcome at least one of the defects of the prior art and provide a method for separating strontium ions and barium ions in high-level radioactive waste liquid.
The purpose of the invention can be realized by the following technical scheme:
a method for separating strontium ions and barium ions in high-level radioactive waste liquid comprises the following steps:
preparing an extracting agent: mixing N, N, N ', N' -tetraoctyl-3-oxoglutaramide (TODGA), tributyl phosphate (TBP) and a diluent to form an extractant;
extraction and separation: and mixing the extractant with the high-level radioactive waste liquid, carrying out extraction reaction, and completing the separation of strontium ions and barium ions in the high-level radioactive waste liquid after the balance is achieved.
Further, the diluent comprises kerosene (OK).
Furthermore, in the extracting agent, the concentration of N, N, N ', N' -tetraoctyl-3-oxoglutaramide (TODGA) is 0.2-0.3mol/L.
Furthermore, the concentration of tributyl phosphate (TBP) in the extractant is 0.4-0.6mol/L.
Furthermore, the concentration of tributyl phosphate (TBP) in the extracting agent is 0.5mol/L.
Further, before extraction and separation, acid liquor is added into the high-level waste liquid to adjust acidity.
Further, the acid solution comprises nitric acid.
Further, after the acid adjustment, the acidity of the high level radioactive waste liquid is 2.5-3mol/L.
Furthermore, the volume ratio of the extracting agent to the high-level radioactive waste liquid is (0.8-1.2): 1 during extraction.
Further, during extraction, the volume ratio of the extracting agent to the high-level radioactive waste liquid is 1:1.
Further, after the extraction reaction, the single-stage extraction separation coefficient of strontium to barium ions is more than 10.
Compared with the prior art:
(1) In the invention, the single-stage extraction separation coefficient of strontium to barium ions is more than 10 and even can reach 1000;
(2) In the invention, a special TODGA extractant is used, so that the extraction effect is greatly improved.
Detailed Description
The following examples are given for the detailed implementation and the specific operation procedures, but the scope of the present invention is not limited to the following examples.
A method for separating strontium ions from barium ions in high-level radioactive waste liquid comprises the following specific operation steps:
(1) Preparation of extractant
Measuring a certain volume of TODGA according to formula (1) and placing the TODGA into a container
Wherein V1 is TODGA volume in liters (L); v is the volume of the required prepared extractant, and the unit is liter (L); c is the concentration of TODGA in the required prepared extractant, and takes 0.2 to 0.3, and the unit is mol per liter (mol/L).
TBP with a certain volume is measured according to the formula (2) and put into a constant volume container, OK is added for constant volume, and TBP-OK with the concentration of 0.2-0.3mol/L TODGA-0.5mol/L is prepared to be used as an extracting agent.
Wherein V2 is TBP volume, and V is the volume of the extractant TODGA-TBP-OK to be prepared, and the unit is liter (L).
(2) Acidity regulation of high level radioactive waste liquid
Sampling the high-level radioactive waste liquid for analyzing acidity, and calculating HNO required to be added according to the formula (3) according to the analysis result of the high-level radioactive waste liquid 3 Volume, adjusting the acidity of the high level radioactive waste liquid to 2.5-3mol/L
Wherein V4 is the volume of the required nitric acid added and the unit is liter (L); v3 is the initial volume of the high-level radioactive waste liquid, and the unit is liter (L); c3 is initial acidity of the high level radioactive waste liquid, and the unit is mol per liter (mol/L); b is the acidity of the material liquid after seasoning, and the unit is mol per liter (mol/L) from 2.5 to 3; c4 is the desired nitric acid concentration added in moles per liter (mol/L).
(3) Extraction separation
Filling extraction equipment with a prepared extractant TODGA-TBP-OK, introducing the material liquid with adjusted acidity into the extraction equipment, and setting the two-phase flow ratio to be 1:1; the extraction reaction is carried out in two phases in an extraction device.
(1) Analysis of samples
After the extraction reaction reaches the equilibrium, sampling analysis is carried out, and the separation coefficient of strontium to barium ions is calculated according to the formula (4)
Wherein, the first and the second end of the pipe are connected with each other, β A/B is the separation coefficient of B to A; is a direct change A A distribution coefficient of A, oc B The partition coefficient is B.
Example 1
In the embodiment, the concentration of Sr in the high-level radioactive waste liquid is 2g/L, the concentration of barium is 2g/L, the acidity is 2.5mol/L, after 0.2mol/L TODGA-0.5mol/L TBP-OK extraction, the extraction is finished, the concentration of Sr in the raffinate is 0.004g/L, the concentration of barium is 1.998g/L, through calculation,
the separation factor was 1000.
Example 2
In the embodiment, the concentration of Sr in the high-level radioactive waste liquid is 2g/L, the concentration of barium is 2g/L, the acidity is 3mol/L, after 0.2mol/L TODGA-0.5mol/L TBP-OK extraction, the extraction is finished, the concentration of Sr in the raffinate is 0.003g/L, the concentration of barium is 1.90g/L, through calculation,
the separation factor was 20.
The foregoing is directed to preferred embodiments of the present invention, other and further embodiments of the invention may be devised without departing from the basic scope thereof, and the scope thereof is determined by the claims that follow. However, any simple modification, equivalent change and modification of the above embodiments according to the technical essence of the present invention are within the protection scope of the technical solution of the present invention.
Claims (10)
1. A method for separating strontium ions and barium ions in high-level radioactive waste liquid is characterized by comprising the following steps:
preparing an extracting agent: mixing N, N, N ', N' -tetraoctyl-3-oxoglutaramide, tributyl phosphate and a diluent to form an extracting agent;
extraction and separation: and mixing an extracting agent with the high-level radioactive waste liquid, carrying out extraction reaction, and completing the separation of strontium ions and barium ions in the high-level radioactive waste liquid after the balance is achieved.
2. The method for separating strontium ions from barium ions in high level radioactive waste liquid according to claim 1, wherein said diluent comprises kerosene.
3. The method for separating strontium ions from barium ions in high level radioactive waste liquid according to claim 1, wherein the concentration of N, N, N ', N' -tetraoctyl-3-oxoglutaramide in the extractant is 0.2-0.3mol/L.
4. The method for separating strontium ions from barium ions in high level radioactive waste liquid according to claim 1, wherein the concentration of tributyl phosphate in the extractant is 0.4-0.6mol/L, preferably 0.5mol/L.
5. The method for separating strontium ions and barium ions in high level radioactive waste liquid according to claim 1, wherein before extraction and separation, acid solution is added into the high level radioactive waste liquid to adjust acidity.
6. The method for separating strontium ions from barium ions in high level radioactive waste liquid according to claim 5, wherein the acid solution comprises nitric acid.
7. The method for separating strontium ions and barium ions in high level radioactive waste liquid according to claim 5, wherein the acidity of the high level radioactive waste liquid is 2.5-3mol/L after the acidity is adjusted.
8. The method for separating strontium ions from barium ions in high-level radioactive waste liquid according to claim 1, wherein the volume ratio of the extracting agent to the high-level radioactive waste liquid is (0.8-1.2): 1 during extraction.
9. The method for separating strontium ions and barium ions in high level radioactive waste liquid according to claim 1, wherein the volume ratio of the extracting agent to the high level radioactive waste liquid is 1:1.
10. The method for separating strontium ions from barium ions in high-level radioactive waste liquid according to claim 1, wherein after the extraction reaction, the single-stage extraction separation coefficient of strontium to barium ions is greater than 10.
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| CN202211400151.7A CN115985542A (en) | 2022-11-09 | 2022-11-09 | Method for separating strontium ions and barium ions in high-level radioactive waste liquid |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN116555568A (en) * | 2023-05-17 | 2023-08-08 | 四川长晏科技有限公司 | Method for extracting metal ions in strong acid system |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN116555568A (en) * | 2023-05-17 | 2023-08-08 | 四川长晏科技有限公司 | Method for extracting metal ions in strong acid system |
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