A method and system for separating strontium ions and calcium ions in high-level radioactive solution

Abstract

The present invention provides a method and system for separating strontium ions and calcium ions in a high-level radioactive solution, and relates to the field of spent fuel reprocessing. The method comprises: obtaining a first preset volume of an extractant; obtaining a second preset volume of a high-level radioactive solution containing strontium ions and calcium ions; adjusting the acidity of the high-level radioactive solution to a preset value to obtain a first solution; placing the extractant and the first solution in an extraction device, extracting the first solution with the extractant, and obtaining a target solution. The scheme of the present invention realizes the separation of strontium ions and calcium ions in a high-level radioactive solution.

Description

Technical Field

[0001] The invention relates to the field of spent fuel post-processing, and in particular to a method and system for separating strontium ions and calcium ions in a high-level radioactive solution. Background Art

[0002] In the spent fuel reprocessing process, high-level waste liquid is a waste liquid with high radioactivity and strong toxicity. It concentrates more than 95% of the radioactivity in spent fuel, posing a potential hazard to humans and the environment. Its treatment and disposal has become one of the key factors restricting the sustainable development of nuclear energy. 90Sr and its daughter 90Y are both pure beta emitters, and are ideal materials for making beta radiation sources and nuclear batteries. They have special applications in defense, environmental science, biomedicine and other fields, and have high practical value and economic significance. The calcium content of strontium in high-level waste liquid is relatively high and its properties are relatively similar. In order to obtain a 90Sr solution of a certain purity, the calcium ions in it need to be separated. Summary of the invention

[0003] The technical problem to be solved by the present invention is to provide a method and system for separating strontium ions and calcium ions in a high-level radioactive solution, thereby realizing the separation of strontium ions and calcium ions in a high-level radioactive solution.

[0004] In order to solve the above technical problems, the technical solution of the present invention is as follows:

[0005] An embodiment of the present invention provides a method for separating strontium ions and calcium ions in a high-level radioactive solution, comprising:

[0006] Obtaining a first preset volume of an extractant;

[0007] Obtaining a second preset volume of a high-radiation solution containing strontium ions and calcium ions;

[0008] The acidity of the high-acid solution is adjusted to a preset value to obtain a first solution, wherein the preset value ranges from 0.8 to 1.0 mol / L;

[0009] The extractant and the first solution are placed in an extraction device, and the first solution is extracted by the extractant to obtain a target solution.

[0010] Optionally, obtaining a first preset volume of the extractant includes:

[0011] Obtaining a third preset volume of TODGA solution and a fourth preset volume of TBP solution;

[0012] The TODGA solution and the TBP solution are mixed, and diluted with kerosene to obtain an extractant of a first preset volume;

[0013] Wherein, the TODGA is N,N,N′,N′-tetraoctyl-3-oxoglutaramide, the TBP is tributyl phosphate, and the extractant is a mixed solution of TODGA, TBP and kerosene.

[0014] Optional, by calculating a third preset volume of the TODGA solution;

[0015] Wherein, V1 is the third preset volume, V is the first preset volume, and C1 is the concentration of TODGA in the extractant.

[0016] Optional, by calculating a fourth preset volume of the TBP solution;

[0017] Wherein, V2 is the fourth preset volume, V is the first preset volume, and C2 is the concentration of TBP in the extractant.

[0018] Optionally, adjusting the acidity of the high-acid solution to a preset value to obtain a first solution comprises:

[0019] The initial acidity of the high-radiation solution is obtained, and a fifth preset volume of nitric acid solution is added to the high-radiation solution, and the acidity of the high-radiation solution is adjusted to a preset value by the nitric acid solution, wherein the preset value ranges from 0.8 to 1.0 mol / L, to obtain a first solution.

[0020] Optional, by calculating a fifth predetermined volume of the nitric acid solution;

[0021] Among them, V4 is the fifth preset volume, V3 is the second preset volume, C3 is the acidity of the high-level radioactive solution, b is the acidity of the first solution, and C4 is the concentration of nitric acid required to be added.

[0022] Optionally, placing the extractant and the first solution in an extraction device, and extracting the first solution with the extractant to obtain a target solution, comprises:

[0023] Fill the extraction equipment with the extraction agent;

[0024] The first solution is introduced into the extraction device, the two-phase flow ratio of the extractant and the first solution is set to 1:1, the two phases undergo extraction reaction in the extraction device, and the target solution is obtained after the reaction reaches equilibrium.

[0025] An embodiment of the present invention further provides a system for separating strontium ions and calcium ions in a high-level radioactive solution, comprising:

[0026] An acquisition module, used for acquiring a first preset volume of an extractant and a second preset volume of a high-radiation solution containing strontium ions and calcium ions;

[0027] A regulating module, used for adjusting the acidity of the high-acid solution to a preset value to obtain a first solution;

[0028] The processing module is used to place the extractant and the first solution into an extraction device, and extract the first solution with the extractant to obtain a target solution.

[0029] Optionally, when the acquisition module acquires the first preset volume of the extractant, it is specifically used to acquire a third preset volume of a TODGA solution and a fourth preset volume of a TBP solution; the TODGA solution and the TBP solution are mixed, and diluted and fixed with kerosene to obtain the extractant; wherein the TODGA is N,N,N′,N′-tetraoctyl-3-oxoglutaramide, the TBP is tributyl phosphate, and the extractant is a mixed solution of TODGA, TBP and kerosene.

[0030] The above solution of the present invention includes at least the following beneficial effects:

[0031] The method for separating strontium ions and calcium ions in a high-radiation solution of the present invention comprises: obtaining a first preset volume of an extractant; obtaining a second preset volume of a high-radiation solution containing strontium ions and calcium ions; adjusting the acidity of the high-radiation solution to a preset value to obtain a first solution; placing the extractant and the first solution in an extraction device, extracting the first solution with the extractant to obtain a target solution. The separation of strontium ions and calcium ions in the high-radiation solution is achieved. BRIEF DESCRIPTION OF THE DRAWINGS

[0032] Figure 1 The present invention is a schematic flow diagram of a method for separating strontium ions and calcium ions in a high-level radioactive solution. DETAILED DESCRIPTION

[0033] The exemplary embodiments of the present disclosure will be described in more detail below with reference to the accompanying drawings. Although the exemplary embodiments of the present disclosure are shown in the accompanying drawings, it should be understood that the present disclosure can be implemented in various forms and should not be limited by the embodiments set forth herein. On the contrary, these embodiments are provided to enable a more thorough understanding of the present disclosure and to fully convey the scope of the present disclosure to those skilled in the art.

[0034] like Figure 1 As shown, an embodiment of the present invention provides a method for separating strontium ions and calcium ions in a high-level radioactive solution, comprising:

[0035] Step 11, obtaining a first preset volume of an extractant;

[0036] Step 12, obtaining a second preset volume of a high-radiation solution containing strontium ions and calcium ions;

[0037] Step 13, adjusting the acidity of the high-acid solution to a preset value to obtain a first solution, wherein the preset value ranges from 0.8 to 1.0 mol / L;

[0038] Step 14: placing the extractant and the first solution into an extraction device, extracting the first solution with the extractant to obtain a target solution.

[0039] Obtaining a first preset volume of an extractant, comprising:

[0040] Obtaining a third preset volume of TODGA solution and a fourth preset volume of TBP solution;

[0041] The TODGA solution and the TBP solution are mixed, and diluted with kerosene to obtain an extractant of a first preset volume;

[0042] The TODGA is N,N,N′,N′-tetraoctyl-3-oxoglutaramide, the TBP is tributyl phosphate, and the extractant is a mixed solution of TODGA, TBP and kerosene.

[0043] In this embodiment, the acidity of the high-power solution is adjusted to a preset value, and then a mixed solution of TODGA, TBP and kerosene is used as an extractant. The strontium ions in the high-power solution are retained in the raffinate phase after extraction, and the calcium ions in the high-power solution enter the extraction phase. Then, the desired target solution is obtained by liquid separation, and the target solution is the raffinate phase solution.

[0044] In an optional embodiment of the present invention, by calculating a third preset volume of the TODGA solution;

[0045] Among them, V1 is the third preset volume, V is the first preset volume, C1 is the concentration of TODGA in the extractant, which is 0.1, in moles per liter, 580.97 is the relative molecular mass of TODGA, and 0.91 is the density of TODGA.

[0046] In an optional embodiment of the present invention, by calculating a fourth preset volume of the TBP solution;

[0047] Among them, V2 is the fourth preset volume, V is the first preset volume, C2 is the concentration of TBP in the extractant, which is 0.5, in moles per liter, 266.37 is the relative molecular mass of TBP, and 0.97 is the density of TBP.

[0048] In an optional embodiment of the present invention, the acidity of the high-acid solution is adjusted to a preset value to obtain a first solution, comprising:

[0049] The initial acidity of the high-radiation solution is obtained, and a fifth preset volume of nitric acid solution is added to the high-radiation solution, and the acidity of the high-radiation solution is adjusted to a preset value by the nitric acid solution to obtain a first solution.

[0050] In an optional embodiment of the present invention, by calculating a fifth predetermined volume of the nitric acid solution;

[0051] Among them, V4 is the fifth preset volume, V3 is the second preset volume, C3 is the acidity of the high-level radioactive solution, b is the acidity of the first solution, and C4 is the concentration of nitric acid required to be added.

[0052] In an optional embodiment of the present invention, the extractant and the first solution are both placed in an extraction device, and the first solution is extracted by the extractant to obtain a target solution, comprising:

[0053] Fill the extraction equipment with the extraction agent;

[0054] The first solution is introduced into the extraction device, the two-phase flow ratio of the extractant and the first solution is set to 1:1, the two phases undergo extraction reaction in the extraction device, and the target solution is obtained after the reaction reaches equilibrium.

[0055] The specific implementation process of the above method is described below. In one practicable example, the method for separating strontium ions and calcium ions in a high-level radioactive solution includes:

[0056] 1. Extraction agent preparation

[0057] The required volume of TODGA is calculated based on the required volume of extractant. The calculation formula is:

[0058] Wherein, V1 is the volume of TODGA in liters, V is the volume of the required extractant in liters, C1 is the concentration of TODGA in the extractant, which is 0.1, in moles per liter;

[0059] The required volume of TBP is calculated based on the required volume of extractant. The calculation formula is:

[0060] Wherein, V2 is the volume of TBP in liters, V is the volume of the required extractant in liters, C2 is the concentration of TBP in the extractant, which is 0.5, in moles per liter;

[0061] The required volume of TODGA and the required volume of TBP were measured and placed in a container, and then kerosene was added to the container to make up the volume, and a mixed solution of TODGA, TBP and kerosene was prepared as an extractant, wherein the concentration of TODGA in the extractant was 0.1 mol / L, and the concentration of TBP was 0.5 mol / L.

[0062] 2. Acidity adjustment of high-level radioactive solution

[0063] The initial acidity of the high-radiation solution is detected, and a certain volume of nitric acid solution is added to the high-radiation solution according to the detection result, and the acidity of the high-radiation solution is adjusted to 0.8-1.0 mol / L by the nitric acid solution, wherein the volume of the nitric acid solution to be added is calculated as follows: Wherein, V4 is the volume of nitric acid required to be added, in liters, V3 is the initial volume of the HLA solution, in liters, C3 is the initial acidity of the HLA solution, in moles per liter, b is the acidity of the HLA solution to be adjusted, ranging from 0.8 to 1.0, in moles per liter, and C4 is the concentration of nitric acid required to be added, in moles per liter.

[0064] 3. Extraction and separation

[0065] The extraction device is filled with the prepared extractant, and the high-radioactivity solution after acidification is introduced into the extraction device. The two-phase flow ratio of the extractant and the high-radioactivity solution after acidification is set to 1:1. The two phases undergo extraction reaction in the extraction device, and after the reaction reaches equilibrium, the target solution is obtained by liquid separation.

[0066] In the above embodiment of the present invention, a mixed solution of 0.1 mol / L TODGA, 0.5 mol / L TBP and kerosene is used as an extractant, and strontium ions and calcium ions in a high-radiation solution with an acidity of 0.8-1.0 mol / L can be separated by extraction, thereby removing the calcium ions in the high-radiation solution. When the extraction is performed by the method described in the present invention, the single-stage extraction separation coefficient of strontium ions to calcium ions is greater than 1.5.

[0067] An embodiment of the present invention further provides a system for separating strontium ions and calcium ions in a high-level radioactive solution, comprising:

[0068] An acquisition module, used for acquiring a first preset volume of an extractant and a second preset volume of a high-radiation solution containing strontium ions and calcium ions;

[0069] A regulating module, used for adjusting the acidity of the high-acid solution to a preset value to obtain a first solution, wherein the preset value ranges from 0.8 to 1.0 mol / L;

[0070] The processing module is used to place the extractant and the first solution into an extraction device, and extract the first solution with the extractant to obtain a target solution.

[0071] In an optional embodiment of the present invention, when the acquisition module acquires the first preset volume of the extractant, it is specifically used to acquire a third preset volume of a TODGA solution and a fourth preset volume of a TBP solution; the TODGA solution and the TBP solution are mixed, and diluted and fixed with kerosene to obtain the extractant; wherein the TODGA is N,N,N′,N′-tetraoctyl-3-oxoglutaramide, the TBP is tributyl phosphate, and the extractant is a mixed solution of TODGA, TBP and kerosene.

[0072] Optional, by calculating a third preset volume of the TODGA solution;

[0073] Wherein, V1 is the third preset volume, V is the first preset volume, and C1 is the concentration of TODGA in the extractant.

[0074] Optional, by calculating a fourth preset volume of the TBP solution;

[0075] Wherein, V2 is the fourth preset volume, V is the first preset volume, and C2 is the concentration of TBP in the extractant.

[0076] In an optional embodiment of the present invention, the acidity of the high-acid solution is adjusted to a preset value to obtain a first solution, comprising:

[0077] The initial acidity of the high-radiation solution is obtained, and a fifth preset volume of nitric acid solution is added to the high-radiation solution, and the acidity of the high-radiation solution is adjusted to a preset value by the nitric acid solution to obtain a first solution.

[0078] Optional, by calculating a fifth predetermined volume of the nitric acid solution;

[0079] Among them, V4 is the fifth preset volume, V3 is the second preset volume; C3 is the acidity of the high-level radioactive solution, b is the acidity of the first solution, and C4 is the concentration of nitric acid required to be added.

[0080] Optionally, placing the extractant and the first solution in an extraction device, and extracting the first solution with the extractant to obtain a target solution, comprises:

[0081] Fill the extraction equipment with the extraction agent;

[0082] The first solution is introduced into the extraction device, the two-phase flow ratio of the extractant and the first solution is set to 1:1, the two phases undergo extraction reaction in the extraction device, and the target solution is obtained after the reaction reaches equilibrium.

[0083] It should be noted that all implementation methods of the above method embodiments are applicable to the embodiments of the system and can achieve the same technical effects.

[0084] The above is a preferred embodiment of the present invention. It should be pointed out that for ordinary technicians in this technical field, several improvements and modifications can be made without departing from the principles of the present invention. These improvements and modifications should also be regarded as the scope of protection of the present invention.

Claims

1. A method for separating strontium ions and calcium ions in a high-level radioactive solution, characterized in that: include: Obtaining a first preset volume of an extractant; Obtaining a second preset volume of a high-radiation solution containing strontium ions and calcium ions; The acidity of the high-acid solution is adjusted to a preset value to obtain a first solution, wherein the preset value ranges from 0.8 to 1.0 mol / L; placing the extractant and the first solution into an extraction device, and extracting the first solution with the extractant to obtain a target solution; Obtaining a first preset volume of an extractant, comprising: Obtaining a third preset volume of TODGA solution and a fourth preset volume of TBP solution; The TODGA solution and the TBP solution are mixed, and diluted with kerosene to obtain an extractant of a first preset volume; Wherein, the TODGA is N,N,N′,N′-tetraoctyl-3-oxoglutaramide, the TBP is tributyl phosphate, and the extractant is a mixed solution of TODGA, TBP and kerosene; pass calculating a third preset volume of the TODGA solution; Wherein, V1 is the third preset volume, V is the first preset volume, and C1 is the concentration of TODGA in the extractant; pass calculating a fourth preset volume of the TBP solution; Wherein, V2 is the fourth preset volume, V is the first preset volume, and C2 is the concentration of TBP in the extractant; The acidity of the high-radiation solution is adjusted to a preset value to obtain a first solution, comprising: Obtaining the initial acidity of the high-radiation solution, and adding a fifth preset volume of nitric acid solution to the high-radiation solution, adjusting the acidity of the high-radiation solution to a preset value by the nitric acid solution, to obtain a first solution; pass calculating a fifth predetermined volume of the nitric acid solution; Wherein, V4 is the fifth preset volume, V3 is the second preset volume, C3 is the acidity of the high-level solution, b is the acidity of the first solution, and C4 is the concentration of nitric acid to be added; The extractant and the first solution are placed in an extraction device, and the first solution is extracted by the extractant to obtain a target solution, including: Fill the extraction equipment with the extraction agent; The first solution is introduced into an extraction device, the two-phase flow ratio of the extractant to the first solution is set to 1:1, the two phases undergo extraction reaction in the extraction device, and the target solution is obtained after the reaction reaches equilibrium; The concentration of TODGA in the extractant is 0.1 mol / L, and the concentration of TBP is 0.5 mol / L.

2. A system for separating strontium ions and calcium ions in a high-level radioactive solution, characterized in that: include: An acquisition module, used for acquiring a first preset volume of an extractant and a second preset volume of a high-radiation solution containing strontium ions and calcium ions; A regulating module, used for adjusting the acidity of the high-acid solution to a preset value to obtain a first solution, wherein the preset value ranges from 0.8 to 1.0 mol / L; A processing module, used for placing the extractant and the first solution into an extraction device, extracting the first solution with the extractant to obtain a target solution; Obtaining a first preset volume of an extractant, comprising: Obtaining a third preset volume of TODGA solution and a fourth preset volume of TBP solution; The TODGA solution and the TBP solution are mixed, and diluted with kerosene to obtain an extractant of a first preset volume; Wherein, the TODGA is N,N,N′,N′-tetraoctyl-3-oxoglutaramide, the TBP is tributyl phosphate, and the extractant is a mixed solution of TODGA, TBP and kerosene; pass calculating a third preset volume of the TODGA solution; Wherein, V1 is the third preset volume, V is the first preset volume, and C1 is the concentration of TODGA in the extractant; pass calculating a fourth preset volume of the TBP solution; Wherein, V2 is the fourth preset volume, V is the first preset volume, and C2 is the concentration of TBP in the extractant; The acidity of the high-radiation solution is adjusted to a preset value to obtain a first solution, comprising: Obtaining the initial acidity of the high-radiation solution, and adding a fifth preset volume of nitric acid solution to the high-radiation solution, adjusting the acidity of the high-radiation solution to a preset value by the nitric acid solution, to obtain a first solution; pass calculating a fifth predetermined volume of the nitric acid solution; Wherein, V4 is the fifth preset volume, V3 is the second preset volume, C3 is the acidity of the high-level solution, b is the acidity of the first solution, and C4 is the concentration of nitric acid to be added; The extractant and the first solution are placed in an extraction device, and the first solution is extracted by the extractant to obtain a target solution, including: Fill the extraction equipment with the extraction agent; The first solution is introduced into an extraction device, the two-phase flow ratio of the extractant to the first solution is set to 1:1, the two phases undergo extraction reaction in the extraction device, and the target solution is obtained after the reaction reaches equilibrium; The concentration of TODGA in the extractant is 0.1 mol / L, and the concentration of TBP is 0.5 mol / L.

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