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Selective extraction and separation method for trivalent actinides and lanthanides in spent fuel reprocessing

A separation method and technology for spent fuel, which are applied in the field of selective extraction and separation of trivalent actinides and lanthanides in spent fuel, can solve the problem that a multi-stage extraction and separation system has not been developed, the stability of the extractant is poor, and the extraction kinetics performance is poor. In order to achieve good extraction kinetic performance, simplify the composition of the extraction system, and improve the utilization rate of raw materials

Active Publication Date: 2020-12-08
SICHUAN UNIV
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Problems solved by technology

[0010] Although currently targeting An 3+ / Ln 3+ Separation has developed some multi-stage extraction process systems, but there are still many deficiencies in the process of practical application, such as: poor stability of extractant, poor extraction kinetics, low loading of organic phase, complex extraction system, etc.
Therefore, a kind of good An that is suitable for industrial scale application has not yet been developed. 3+ / Ln 3+ Multi-stage extraction separation system

Method used

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  • Selective extraction and separation method for trivalent actinides and lanthanides in spent fuel reprocessing
  • Selective extraction and separation method for trivalent actinides and lanthanides in spent fuel reprocessing
  • Selective extraction and separation method for trivalent actinides and lanthanides in spent fuel reprocessing

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Embodiment 1-6

[0044] The detergent TEE-BisDGA adopted is prepared by the following method:

[0045] (1) Diglycolic anhydride (2.9g, 0.025mol) was added to 40mL of tetrahydrofuran, and placed in an ice-water bath at 0°C, and diethylamine (1.8g, 0.025mol) was added dropwise while stirring. After the addition was complete, remove In an ice-water bath, react at 25°C for 3 hours under stirring conditions; then rotary steam the product obtained from the reaction to remove tetrahydrofuran, and then add dropwise an aqueous solution of hydrochloric acid with a volume concentration of 50% to the product obtained from the reaction of removing tetrahydrofuran, and white crystals are precipitated. Suction filtration, and recrystallization and purification using a mixed solvent of methanol / water with a volume ratio of 1:1 to obtain N,N-diethyl-3-oxoglutaric acid as a white flaky solid;

[0046] (2) Under stirring conditions, N,N-diethyl-3-oxoglutaric acid (4.7g, 0.025mol), ethylenediamine (0.7g, 0.010mol...

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Abstract

The invention discloses a method for selective extraction separation of trivalent actinides and lanthanides in fuel-short after-treatment. The method is implemented through the steps that NTAamide(n-Oct) serves as an extraction agent, kerosene serves as a diluting agent, a water-soluble ligand TEE-BisDGA serves as a detergent, a hydroxycarboxylic complexing agent or ammoniacarboxylic complexing agent or a nitric acid solution serves as a stripping agent, and a multi-stage extraction technology is utilized, firstly, a large number of actinide elements and part of lanthanide elements are extracted from feed liquid through the extraction agent, then the lanthanide elements in a loaded organic phase are removed through the detergent, finally the actinide elements are stripped from the organicphase through the stripping agent, thus selective extraction separation of the actinide elements and the lanthanide elements can be realized, the recovery rate of the actinide elements exceeds 99%, and the recovery purity can reach 99.9% or above.

Description

technical field [0001] The invention belongs to the technical field of nuclear fuel cycle and nuclear waste treatment, relates to a process system for separation of lanthanides / actinides, in particular to a method for selective extraction and separation of trivalent actinides and lanthanides in spent fuel based on a multi-stage extraction process. Background technique [0002] The effective handling and disposal of nuclear fuel is one of the key factors to ensure the sustainable development of nuclear energy. The "separation-transmutation" method is a nuclear fuel reprocessing method that is generally preferred in the world. Its main point is to selectively separate the small but highly toxic actinides from the high-level waste liquid by solvent extraction, and extract It transmutes into short-lived or stable nuclides (Gu Zhongmao et al., Atomic Energy Science and Technology, 2002, 36(2): 160-167). [0003] In actual extraction and separation, single-stage extraction often ...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): C22B7/00C22B59/00C22B60/02C22B3/26G21F9/12
CPCY02P10/20
Inventor 丁颂东王学羽王志鹏杨秀英宋莲君陈志力肖茜
Owner SICHUAN UNIV
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