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Method for extracting and separating trivalent lanthanum and trivalent actinium ion

A technology of actinides and lanthanides, applied in the field of nuclear fuel cycle and waste liquid treatment, can solve the problems of decreased extraction and separation capacity, deviation from the ideal range, unfavorable continuous extraction operation, etc., and achieve high-efficiency extraction and separation performance and good application prospects Effect

Active Publication Date: 2015-09-09
TSINGHUA UNIV +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

However, due to the high pH value required, when the metal ions in the aqueous phase are exchanged with the protons on the extractant in the organic phase during the extraction process or are disturbed by other factors (a small amount of decomposition of the extractant, dissolution of air carbon dioxide, etc.), it is easy to lead to the following conditions: The pH value of the aqueous phase adjusted by the above method obviously changes and deviates from the ideal range, thereby reducing the extraction and separation ability of the system to trivalent lanthanides and trivalent actinides (Chen, J. et al, Atalante 2012 International Conference on Nuclear Chemistry forSustainable Fuel Cycles, C. Poinssot, Editor. 2012.172-177)
At the same time, this traditional method of adjusting pH also greatly increases the complexity of the extraction process, which is not conducive to continuous extraction operations.

Method used

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  • Method for extracting and separating trivalent lanthanum and trivalent actinium ion

Examples

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Effect test

Embodiment 1

[0025] Example 1: Extraction and separation of Am(III) and Eu(III) / Nd(III) by HC301-n-dodecane. When performing extraction experiments, the aqueous phase contained trace amounts of 241 Am, tracer 151,152 Eu, 1.8mmol / L Eu(III), 14mmol / L Nd(III), the total concentration of formic acid-ammonium formate in the aqueous phase is 0.05mol / L, the pH of the aqueous phase is adjusted to 3.75, and the concentration of HC301 in the organic phase is 0.5 mol / L. After the two phases were mixed and stirred for 5 minutes, they were centrifuged, and the aqueous phase and the organic phase were taken for pH measurement, radioactive detection and ICP-MS measurement, and the extraction rate of Am(III) was determined to be 85%, and the extraction rate of Eu(III) was 0.03%, and the extraction rate of Nd(III) was 0.2%. The pH change of the aqueous phase before and after extraction is less than 0.02.

Embodiment 2

[0026] Example 2: HC301-kerosene extraction and separation of Am(III) and Eu(III) / Nd(III). When performing extraction experiments, the aqueous phase contained trace amounts of 241 Am, tracer 151,152Eu, 1.8mmol / L Eu(III), 14mmol / L Nd(III), the total concentration of formic acid-ammonium formate in the aqueous phase is 0.05mol / L, the pH of the aqueous phase is adjusted to 4.00, and the concentration of HC301 in the organic phase is 0.5 mol / L. After the two phases were mixed and stirred for 5 minutes, they were centrifuged, and the aqueous phase and the organic phase were taken for pH measurement, radioactivity detection and ICP-MS measurement respectively. It was determined that the extraction rate of Am(III) was 94%, and the extraction rate of Eu(III) was 0.1%, the extraction rate of Nd(III) was 0.7%. The pH change of the aqueous phase before and after extraction is less than 0.02.

Embodiment 3

[0027] Example 3: Extraction and separation of Am(III) and Eu(III) / Nd(III) by HC301-n-dodecane. When performing extraction experiments, the aqueous phase contained trace amounts of 241 Am, tracer 151,152 Eu, 1.8mmol / L Eu(III), 14mmol / L Nd(III), the total concentration of formic acid-sodium formate in the aqueous phase is 0.20mol / L, the pH of the aqueous phase is adjusted to 4.00, and the concentration of HC301 in the organic phase is 0.5mol / L. After the two phases were mixed and stirred for 5 minutes, they were centrifuged, and the aqueous phase and the organic phase were taken respectively for pH measurement, radioactive detection and ICP-MS measurement. It was determined that the extraction rate of Am(III) was 87%, and the extraction rate of Eu(III) was less than 0.1%. The pH change of the aqueous phase before and after extraction is less than 0.02.

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Abstract

The invention relates to a method for extracting and separating trivalent lanthanum and trivalent actinium ions and belongs to the technical field of nuclear fuel circulation and waste liquid treatment. The method uses bis(2,4,4-trimethylpentyl) dithiophosphinic acid as an extracting agent, uses long-chain alkane as a thinning agent and uses a weak acid buffer system to effectively stabilize the pH value of the water phase of an extraction system, pH regulation does not need to be performed to the system during extraction, trivalent actinium elements can be high-selectively extracted and separated out from the water phase, and most of trivalent lanthanum elements are remained in the water phase. The method for extracting and separating trivalent lanthanum and trivalent actinium ions has the advantages that the extraction and separation performance of trivalent lanthanum and trivalent actinium ions is high and stable and the prospect of application in the field of advanced nuclear circulation is better.

Description

technical field [0001] The invention relates to a method for extracting and separating trivalent lanthanide and trivalent actinide ions, and belongs to the technical field of nuclear fuel cycle and waste liquid treatment. Background technique [0002] A large amount of radioactive waste is generated during the nuclear fuel cycle. At present, whether it is the development of nuclear weapons or the application of civilian nuclear energy, a large amount of high-level liquid waste is left over, and its treatment and disposal has become the focus of attention all over the world. The "separation-transmutation" method is an advanced strategy for treating high-level waste liquid, that is, the chemical separation method is used to selectively separate the actinide elements, which account for a small proportion but are highly toxic, from the high-level waste liquid. Accelerators or reactors convert it into stable or short-lived nuclides, and the residual waste liquid becomes non-alph...

Claims

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Application Information

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IPC IPC(8): C22B3/26
CPCY02P10/20
Inventor 徐超孙涛祥陈靖秦芝
Owner TSINGHUA UNIV
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