A rapid separation device and method for activation products uranium and gallium

An activated product, fast technology, applied in the field of rapid separation of activated products uranium and gallium, can solve problems not mentioned, and achieve the effect of simple process, clear function, easy control and adjustment

Active Publication Date: 2018-01-19
NORTHWEST INST OF NUCLEAR TECH
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0007] Patent 1 (ZL201310214649.9, Fan Jinlong et al. A rapid separation method for activated product gallium in fission products) and patent 2 (ZL201310215354.3, Fan Jinlong et al. A separation device for radioactive solutions containing gallium) provide a The separation method and separation device for extracting the activated product gallium from the fission products have realized the effective separation of the activated product gallium from the fission products, but neither mentions the separation state of the activated product gallium when uranium exists

Method used

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  • A rapid separation device and method for activation products uranium and gallium
  • A rapid separation device and method for activation products uranium and gallium
  • A rapid separation device and method for activation products uranium and gallium

Examples

Experimental program
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Effect test

Embodiment 1

[0076] The fissioned sample of nuclear fuel containing uranium and gallium is dissolved in 20mL 3mol / L HCl medium to form a solution containing uranium and gallium, and the solution is placed in the gallium-containing uranium radioactive solution storage tank 1. like figure 2 shown.

[0077] Control the flow rate at 1mL / min, make the solution containing uranium and gallium pass through the P204 chromatographic adsorption column 91, Al 2 o 3 The chromatographic adsorption column 10 is separated from the first TBP chromatographic adsorption column 11, wherein the P204 chromatographic adsorption column 91 is a P 204 Chromatography column, Al 2 o 3 Chromatographic adsorption column 10 is Al of φ8×60mm 2 o 3 Chromatographic column, the first TBP chromatographic adsorption column 11 is a TBP extraction chromatographic column of φ8 × 60mm; wherein P 204 The chromatographic column realizes the separation of Ga from Mo, Zr, U, Al 2 o 3 The chromatographic column realizes the ...

Embodiment 2

[0085] P in Example 1 204 The chromatographic adsorption column 91 is replaced by the LN chromatographic adsorption column 92, and the separation process of Example 1 is repeated to obtain the gamma radioactivity measuring source of the activated product uranium and gallium, and the recovery rates of uranium and gallium are respectively 92.2% and 95.9%, which is very good for fission The decontamination factor of product is as shown in table 1, and it can be seen that it is better than 10 4 , the process takes 130 minutes.

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Abstract

The invention discloses a rapid separating device for uranium activation products and gallium activation products and a rapid separating method for the uranium activation products and the gallium activation products. The particular method comprises the following steps of enabling a sample to pass through a P204 chromato-graphic column or an LN chromato-graphic column, an Al2O3 chromato-graphic column and a TBP extraction chromato-graphic column at a certain flow rate, wherein uranium is adsorbed on the P204 chromato-graphic column or the LN chromato-graphic column and gallium is adsorbed on the TBP extraction chromato-graphic columns; conducting adsorption and separation on uranium again through the P204 chromato-graphic column or the LN chromato-graphic column and another TBP extraction chromato-graphic column with a high-acid solution after washing; and enabling the sample to pass through a series column of TBP chromato-graph and a TEVA+DA chromato-graph and a series column of the TBP chromato-graph and an Al2O3+ activated carbon chromato-graph at the same time with a dilute-acid solution after washing to obtain effluent liquids, wherein the effluent liquids are a radioactive measuring solution of the uranium activation products and a radioactive measuring solution of the gallium activation products respectively. The rapid separating method is used for separating the fission-product-enriched radioactive solutions of the uranium activation products and the gallium activation products, the recovery rate of uranium and gallium is better than 90%, the decontamination factors to the fission products is better than 10<4> and the separating process can be completed within 2.5 hours.

Description

technical field [0001] The invention belongs to the technical field of radiochemical separation of activation products, and specifically discloses a rapid separation method for activation products uranium (U) and gallium (Ga). Background technique [0002] Activation product analysis is one of the common methods of neutron spectrum analysis in nuclear fuel fission process. The neutron flux and neutron energy in the nuclear fission process can be determined indirectly by analyzing the content and type of activation products. Fissionable materials such as uranium and plutonium are the most commonly used nuclear fuels. In order to increase the processability of plutonium materials, metal gallium (Ga) usually needs to be added, and its content is about 1%. Because gallium and plutonium materials form a uniform mixture, it is the most favorable medium for neutron energy monitoring in the process of plutonium material fission, and can be applied to the analysis and determination ...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): C22B3/24C22B58/00C22B60/02
CPCC22B3/22C22B58/00C22B60/0265
Inventor 凡金龙卢嘉春杜丽丽师全林刘志超余功硕张丽莉
Owner NORTHWEST INST OF NUCLEAR TECH
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