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Spent fuel post-processing method based on uranium cluster compound

A technology for clustering and spent fuel, applied in reactor fuel elements, recycling technology, reducing greenhouse gases, etc., can solve the problems of reducing separation efficiency, uranium and plutonium purification coefficient, etc., and achieve good economic benefits, simple process, and low corrosiveness. Effect

Pending Publication Date: 2022-06-28
XI AN JIAOTONG UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

These products have a certain ability to complex the fission products, which will reduce the separation efficiency and the purification coefficient of uranium and plutonium, and often require multiple separation cycles to obtain qualified uranium and plutonium products
In addition, the PUREX process will separate the plutonium separately, which will lead to the risk of nuclear proliferation

Method used

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  • Spent fuel post-processing method based on uranium cluster compound
  • Spent fuel post-processing method based on uranium cluster compound
  • Spent fuel post-processing method based on uranium cluster compound

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0043] A method for reprocessing spent fuel based on uranium clusters, comprising the following steps:

[0044] S1. Dismantling the spent fuel assembly and cutting it into small fuel rods;

[0045] S2. Use hydrogen peroxide and ammonia water to dissolve spent fuel; the solution is hydrogen peroxide with a mass concentration of 30%, and the concentration of ammonia water is 4mol / L. The two are mixed at a volume ratio of 1:1, and hydrogen peroxide can be in excess; add the treated spent fuel Fuel, UO in spent fuel 2 Under the oxidation of hydrogen peroxide, it dissolves into uranyl ions. Ensure that the concentration of uranyl ions after dissolution is controlled at 0.5mol / L; uranyl ions are coordinated with peroxides and hydroxides to form uranyl peroxide clusters in the form of giant anions; Pu, some minor actinides and fission products dissolve After the alkaline solution, with Pu 4+ 、Cs + 、MoO 4 2- In the form of simple inorganic cations or anions, insoluble actinide p...

Embodiment 2

[0050] A method for reprocessing spent fuel based on uranium clusters, comprising the following steps:

[0051] S1. Dismantling the spent fuel assembly and cutting it into small fuel rods;

[0052] S2, using hydrogen peroxide and Na 2 CO 3 To dissolve spent fuel, the solution is hydrogen peroxide with a concentration of 30%, Na 2 CO 3 The concentration of the solution is 3mol / L, and the two are mixed at a volume ratio of 1:1, and the hydrogen peroxide can be appropriately excessive; the treated spent fuel is added, and the UO in the spent fuel 2 Under the oxidation of hydrogen peroxide, it dissolves into uranyl ions, ensuring that the concentration of uranyl ions after dissolution is controlled at 2mol / L; uranyl ions are coordinated with peroxide and hydroxide to form uranyl peroxide clusters in the form of giant anions ; After Pu, some minor actinides and fission products are dissolved in the alkaline solution, the Pu 4+ 、Cs + 、MoO 2- It exists in the form of simple in...

Embodiment 3

[0057] A method for reprocessing spent fuel based on uranium clusters, comprising the following steps:

[0058] S1. Dismantling the spent fuel assembly and cutting it into small fuel rods;

[0059] S2. Use hydrogen peroxide and NaOH to dissolve spent fuel. The solution is hydrogen peroxide with a concentration of 30%, and the concentration of NaOH solution is 2.5mol / L. Add treated spent fuel, UO in spent fuel 2 Under the oxidation of hydrogen peroxide, it dissolves into uranyl ions, ensuring that the concentration of uranyl ions after dissolution is controlled at 1mol / L; uranyl ions are coordinated with peroxide and hydroxide to form uranyl peroxide clusters in the form of giant anions , after Pu, some minor actinides and fission products are dissolved in the alkaline solution, the Pu 4+ 、Cs + 、MoO 2- In the form of simple inorganic cations or anions, insoluble actinide products and fission products are properly stored as high-level solid waste;

[0060] S3. Using the dif...

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Abstract

The invention belongs to the technical field of spent fuel post-treatment, and particularly relates to a spent fuel post-treatment method based on a uranium cluster compound, which comprises the following steps: S1, disassembling and shearing a spent fuel assembly into small fuel rods; s2, dissolving the spent fuel by using hydrogen peroxide and an alkaline solution, and filtering to obtain a precipitate and a filtrate; s3, treating the filtrate obtained in the step S2 by utilizing gel electrophoresis, and separating to obtain a uranium cluster compound and a solution containing Pu, minor actinides and fission products; and S4, dilute nitric acid and hydrogen peroxide are added into the uranium cluster compound obtained in the step S3, uranium peroxide clusters are converted into hematite sediment, filtering is carried out, sediment is obtained, and separation of the uranium element is achieved. The spent fuel post-treatment process based on the uranium cluster compound has the advantages of being simple in process, small in corrosivity and the like, the risk of nuclear diffusion does not exist, and compared with a PUREX process, the spent fuel post-treatment process based on the uranium cluster compound has better economic benefits.

Description

technical field [0001] The invention belongs to the technical field of spent fuel reprocessing, and in particular relates to a spent fuel reprocessing method based on uranium clusters. Background technique [0002] As a safe, clean and efficient energy source, nuclear power plays a very important role in meeting people's increasing energy demand and improving the ecological environment. However, with the development of nuclear power, spent fuel with strong radioactivity is also increasing. According to the development of nuclear power in my country, it is estimated that the total amount of spent fuel will reach 18500tU by 2025. If the spent fuel is not properly disposed of, it will pose a great threat to human health and the living environment. On the other hand, the utilization rate of nuclear fuel is now very low (less than 1%), so that more than 95% of the mass of spent fuel is unreacted uranium. If the unreacted uranium can be separated and recycled, the amount of spe...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C19/44G21C19/46
CPCG21C19/44G21C19/46Y02E30/30Y02W30/50
Inventor 邱杰李桥希韩哲
Owner XI AN JIAOTONG UNIV
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