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Method for recovering technetium from post-treatment waste liquid of spent fuel

A technology for spent fuel and waste liquid, applied in the direction of improving process efficiency, etc., can solve the problems of high price, low extraction efficiency of TRPO, and difficulty in the synthesis of cup-crown reagents, etc., and achieve the effect of high extraction efficiency

Active Publication Date: 2020-08-04
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

The first four reagents can extract pertechnetate from nitric acid medium, but the extraction efficiency of TRPO is low, and trioctylamine and quaternary ammonium salts have serious three-phase problems
However, the calix crown reagents are difficult to synthesize and expensive, and are not suitable for the extraction of technetium under post-treatment conditions; pyridine reagents can only extract technetium under alkaline conditions, and are soluble in water under neutral and acidic conditions. Not suitable for technetium extraction

Method used

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  • Method for recovering technetium from post-treatment waste liquid of spent fuel
  • Method for recovering technetium from post-treatment waste liquid of spent fuel
  • Method for recovering technetium from post-treatment waste liquid of spent fuel

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Embodiment 1

[0043] For the process of this embodiment, see image 3 .

[0044] (1) Material liquid acid adjustment and technetium extraction (TcX): 0.1mol / L MIDOA is used as the extraction agent, kerosene is used as the diluent, 1AXXW is extracted after the acid adjustment to 0.5mol / L, after 6-stage extraction, technetium The recovery rate reaches above 99.99%.

[0045] (2) Technetium back-extraction (TcBX): use 0.2mol / L ethylenediamine to back-extract technetium from the extracted organic phase, and separate it from tetravalent impurity elements. After 6-stage back-extraction, the decontamination of Pu(IV) reaches 100 Above, the yield of technetium reaches 99%.

[0046] (3) An washing (ASX): wash the organic phase with 0.02mol / L ammonium carbonate solution, and the organic phase can be reused after washing.

[0047] Through the above process, the total yield of technetium reaches 99%, the decontamination of plutonium reaches more than 100%, and the decontamination of uranium reaches m...

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Abstract

The invention belongs to the technical field of extraction and recovery of nuclear materials, and relates to a method for recovering technetium from post-treatment waste liquid of a spent fuel. The method sequentially comprises the following steps of: (1) adjusting the acidity of the post-treatment waste liquid of the spent fuel to 0.1-1 mol / L, adding a MIDOA-kerosene solution for extracting, andcollecting an organic phase; (2) adding an acidified ethylenediamine solution into the organic phase for back extraction, and collecting technetium in a water phase; and (3) washing the organic phasesubjected to the back extraction with an alkaline solution, and collecting the washed organic phase. The method for recovering technetium from the post-treatment waste liquid of the spent fuel can efficiently extract and recover technetium from nitric acid waste liquid after nuclear fuel post-treatment, and prevent technetium from entering glass curing and geological disposal processes.

Description

technical field [0001] The invention belongs to the technical field of nuclear material extraction and recovery, and relates to a method for recovering technetium from spent fuel reprocessing waste liquid. Background technique [0002] 99 Tc is one of the main long-lived fission products in spent fuel, with a half-life of 2.11×10 5 a, Under thermal neutron irradiation 235 The fission yield of U is about 6%, and its content in spent fuel is about one-thousandth. 99 Tc is a nuclide that is difficult to handle in the disposal of nuclear fuel and radioactive waste. First, technetium is volatile during vitrification and leaks into the environment; second, technetium (mainly in the form of pertechnetate) has a certain Strong mobility, so its geological disposal will bring potential long-term radioactive hazard risks to the biosphere. Therefore, it is necessary to separate technetium from spent fuel reprocessing waste liquid for utilization or transmutation, so as to prevent it...

Claims

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Application Information

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IPC IPC(8): C22B61/00C22B7/00
CPCC22B7/006C22B61/00Y02P10/20
Inventor 王辉王均利申震晏太红郑卫芳
Owner CHINA INSTITUTE OF ATOMIC ENERGY