Method for producing radioactive strontium-90 and caesium-137 simultaneously by adopting centrifugal extractor

A radioactive strontium extractor technology, applied in the field of radioactive wastewater treatment, can solve the problems of large two-phase retention, short residence time, and less compact structure, and achieve small two-phase retention, short residence time, and operating flow ratio wide range of effects

Active Publication Date: 2018-05-15
TSINGHUA UNIV
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Problems solved by technology

At present, the continuous solvent extraction equipment that can be used for high-level radioactive waste treatment includes mixing and settling tank, pulse extraction column and centrifugal extractor. defects such as too compact

Method used

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  • Method for producing radioactive strontium-90 and caesium-137 simultaneously by adopting centrifugal extractor
  • Method for producing radioactive strontium-90 and caesium-137 simultaneously by adopting centrifugal extractor
  • Method for producing radioactive strontium-90 and caesium-137 simultaneously by adopting centrifugal extractor

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Embodiment

[0037] 1) After acid adjustment, the original high-level radioactive waste liquid has an acidity of 1.25mol / L and a total α activity of 1.13×10 5 Beck / liter, 90 The radioactivity of Sr is 2.13×10 8 Beck / liter, 137 The radioactivity of Cs is 2.46×10 8 Beck / liter.

[0038] 2) in such as figure 2 In the solvent extraction process shown, 90 The extractant of Sr is dicyclohexyl 18-crown-6 (referred to as crown ether), the concentration is 0.1mol / L, the diluent is n-octanol, the detergent is 1mol / L nitric acid, and the stripping agent is 0.01mol / L nitric acid .

[0039] 3) in such as figure 1 The solvent extraction process flow shown 137 The extractant of Cs is 25,27-bis(2-propoxy)calix[4]arene-26,28-crown-6 (abbreviated as calix crown), the concentration is 0.025mol / L, and the diluent is n-octanol, The detergent is 0.1mol / L nitric acid, and the stripping agent is 0.001mol / L nitric acid.

[0040] 4) This production task requires extraction and stripping 90 Sr and 137 Cs...

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Abstract

The invention discloses a method for producing radioactive strontium-90 and caesium-137 simultaneously by adopting a centrifugal extractor and belongs to the technical field of radioactive wastewatertreatment. The method includes: adopting the centrifugal extractor, taking crown ether as an extraction agent of <90>Sr to extract radioactive <90>Sr in high-level liquid waste after acid adjustment,adopting nitrite acid solutions of different concentrations as washing agents and back extracting agents, and sequentially washing and back extracting extraction agents loaded with impurities and <90>Sr elements to obtain radioisotope <90>Sr products; taking crown as an extraction agent of <137>Cs, extracting radioactive <137>Cs from high-level liquid waste after <90>Sr is extracted, adopting nitrite acid solutions of different concentrates in the centrifugal extractor as washing agents and back extracting agents, sequentially washing and back extracting extraction agents loaded with impurities and <137>Cs to obtain radioisotope <137>Cs products. The method has the advantages of good transferring effect, high selectivity of <90>Sr and <137>Cs and radioactive decontamination factor and thelike, continuous production can be realized, and two kinds of high-purity radioisotope<90>Sr and <137> Cs products with important applications are obtained efficiently.

Description

technical field [0001] The invention relates to a method for simultaneous production of radioactivity using a centrifugal extractor 90 Sr and 137 The Cs method belongs to the technical field of radioactive wastewater treatment. Background technique [0002] Strontium-90( 90 Sr) and cesium-137 ( 137 Cs) are two radioactive isotopes that have important uses in many fields. 90 Sr can be used industrially for X-ray fluorescence analyzers, thickness gauges, material level gauges, static eliminators, cigarette density measuring instruments and other radioactive detectors and radiation sources in control instruments; medically, it can be used to treat corneal ulcers, melanin Cancer, skin cancer and neurodermatitis and other diseases; it can also be used to make radionuclide batteries for military, scientific research, luminous instrument manufacturing and medical fields. 137 Cs can be used industrially as the radiation source in radioactive detectors and control instruments fo...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): B01D59/24B01D59/20
CPCB01D59/20B01D59/24
Inventor 段五华陈靖王建晨王树威冯孝贵叶钢徐超徐世平
Owner TSINGHUA UNIV
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