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Solution and method for extracting radionuclides from high-level radioactive vitreous bodies

A radionuclide and vitreous technology, applied in the field of radionuclide extraction solutions, can solve the problems of harsh conditions, easy formation of strong corrosive volatile gases, and high concentration of lye, achieve mild composition, promote final processing, and extraction capabilities strong effect

Pending Publication Date: 2021-06-15
XI AN JIAOTONG UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

However, this high-temperature alkali fusion method has harsh conditions, the concentration of the alkali solution used is extremely high, and it is highly corrosive, and it often needs to be carried out at high temperature.
In the hydrofluoric acid corrosion method, the hydrofluoric acid used is extremely corrosive, and it is easy to form highly corrosive volatile gases at high temperatures, requiring additional tail gas treatment processes
It can be seen that the existing two methods have harsh conditions and high risk, and are obviously not suitable for the future extraction process of vitrified nuclides. Strong method to extract nuclides in the vitreous

Method used

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  • Solution and method for extracting radionuclides from high-level radioactive vitreous bodies
  • Solution and method for extracting radionuclides from high-level radioactive vitreous bodies
  • Solution and method for extracting radionuclides from high-level radioactive vitreous bodies

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preparation example Construction

[0030] 1) Preparation of simulated high-radiation glass: using main glass forming reagents (including: SiO 2 , B 2 o 3 、Na 2 O, Al 2 o 3 , ZnO, CaO and Li 2 O) and various metal oxides (including: La 2 o 3 、Nd 2 o 3 , ZrO 2 、Cs 2 O, PdO, Rh 2 o 3 , RuO 2 and SeO 2 ). La, Pd, Ru, Rh, and Cs are respectively selected as representative nuclides of lanthanides, PGM, and alkaline earth elements. Please refer to Table 1 for detailed composition and dosage of each component. These reagents (purchased from Sinopharm Chemical Reagent Co., Ltd.) are non-radioactive and mixed uniformly. With the content of the ingredients listed in Table 1, mix the glass forming reagent and metal oxide powder in a 100mL alumina crucible, heat at 1450°C for 2h, then cool the glass melt to room temperature, and crush it to 100-300μm to obtain glass Solidified powder. The following examples and comparative examples of the present invention are implemented using the glass solidified body po...

Embodiment 1

[0042] The present embodiment extracts the method for radionuclide from the high-level glass solidified body, and its process is as follows:

[0043] The self-made vitrified body powder was added to the mixed solution of hydrogen peroxide / nitric acid with different content ratios, wherein the amount of hydrogen peroxide added was 1 mL, and the concentration of nitric acid was 1 mol / L. The liquid / solid ratio was 20 / 1 mL / g. Put the above-prepared solid-liquid mixture into an oven, heat it up to 90°C, keep it warm for 1 hour, and then cool it down to room temperature. After the impregnation experiment, the supernatant was collected by centrifugation and analyzed for element concentration by ICP-MS. Referring to Figure 2(a) and Figure 2(b), the leaching rates of Na and Cs are 97.69% and 98.37%, respectively.

Embodiment 2

[0045] The present embodiment extracts the method for radionuclide from the high-level glass solidified body, and its process is as follows:

[0046] The self-made vitrified body powder was added to the mixed solution of hydrogen peroxide / nitric acid with different content ratios, wherein the amount of hydrogen peroxide added was 1 mL, and the concentration of nitric acid was 1 mol / L. The liquid / solid ratio was 20 / 1 mL / g. Put the above-prepared solid-liquid mixture into an oven, heat up to 50°C, keep it warm for 1 hour, and then cool to room temperature. After the impregnation experiment, the supernatant was collected by centrifugation and analyzed for element concentration by ICP-MS. Referring to Figure 2(a) and Figure 2(b), the leaching rates of Na and Cs are 92% and 70%, respectively.

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Abstract

The invention belongs to the technical field of nuclear waste treatment, and discloses a solution and method for extracting radionuclides from high-level radioactive vitreous bodies. The solution comprises hydrogen peroxide and nitric acid, the concentration of the nitric acid is 0.5 mol / L-2 mol / L, and each liter of the solution contains 0.5 mL-2 mL of hydrogen peroxide. The method for extracting the radionuclides from the high-level radioactive vitreous bodies comprises the following steps of adding high-level radioactive vitreous body powder into the above solution, and leaching the radionuclides in the high-level radioactive vitreous body powder. Compared with traditional high-temperature alkali fusion and hydrofluoric acid corrosion, the method adopted is milder and higher in operability. The solution and method for extracting the radionuclides from the high-level radioactive vitreous bodies are expected to promote the final treatment of nuclear waste based on the advanced nuclear transmutation technology, and are expected to extract useful nuclides from vitrified waste for resource utilization. In addition, the solution and method for extracting the radionuclides from the high-level radioactive vitreous bodies can be expanded to extraction of specific elements in glass containing specific elements in other industrial fields.

Description

technical field [0001] The invention belongs to the technical field of nuclear waste treatment, and in particular relates to a solution and a method for extracting radionuclides from high-level vitreous bodies. Background technique [0002] Nuclear energy is considered to be an efficient and clean energy, which has brought huge economic and ecological benefits to mankind. However, the fission of nuclear fuel will inevitably produce radioactive spent fuel, and a large amount of high-level liquid waste will be generated in the subsequent spent fuel reprocessing process. These high-level waste liquids have intense and persistent radiotoxicity because they contain long-lived fission products (such as 135 Cs, 79 Se, 93 Zr, 107 Pd, half-life greater than 10 5 years) and minor actinides (Am, Cm, Np). Currently, high-level liquid waste is immobilized in a glass matrix to prevent it from migrating into the environment. Among the glass matrices, borosilicate glass is widely acc...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C22B7/00C22B60/00C22B26/10C22B26/20C22B30/02C01B19/02
CPCC22B7/007C22B60/00C22B26/10C22B26/20C22B30/02C01B19/02Y02P10/20
Inventor 许章炼高阳阳徐丽红张蒙张倩王盛王洁
Owner XI AN JIAOTONG UNIV
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