Device and method for rapid separation of activated product americium, uranium and gallium

An activated product and fast technology, which is applied in the preparation of measuring devices, analytical materials, and samples for testing, etc., can solve the problems of synchronous separation and purification technology and methods that are not mentioned, and achieve reduced exposure dose, clear function, and simple process. Effect

Active Publication Date: 2019-01-01
NORTHWEST INST OF NUCLEAR TECH
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

There is also no mention of the simultaneous separation and purification technology and method of the activation product of americium uranium and the activation product gallium

Method used

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  • Device and method for rapid separation of activated product americium, uranium and gallium
  • Device and method for rapid separation of activated product americium, uranium and gallium
  • Device and method for rapid separation of activated product americium, uranium and gallium

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0083] Dissolve the fissioned sample of nuclear fuel containing americium-uranium-gallium in 20mL 3mol / L HCl medium to form a solution containing americium-uranium-gallium. figure 2 shown.

[0084] Control the flow rate of the americium-uranium-gallium-containing solution at 1mL / min, so that the americium-uranium-gallium-containing solution passes through the first LN chromatographic adsorption column, the Al 2 o 3 The chromatographic adsorption column 13, the first TBP chromatographic adsorption column 14 and the DN chromatographic adsorption column 15 are separated, wherein the first LN chromatographic adsorption column is LN chromatography column, Al 2 o 3 The chromatographic adsorption column 13 is Al 2 o 3 Chromatography column, the first TBP chromatography adsorption column 14 is TBP extraction chromatographic column, DN chromatographic adsorption column 15 is The DN chromatographic column, in which the LN chromatographic column realizes the separation of Am...

Embodiment 2

[0095] Replace the first LN chromatographic adsorption column and the second LN chromatographic adsorption column with the first P204 chromatographic adsorption column and the second P204 chromatographic adsorption column in Example 1, repeat the separation process of Example 1, and obtain the activated product americium , uranium and gallium as gamma radioactive measurement sources, the recovery rates of americium, uranium and gallium are 78.6%, 91.4% and 96.9% respectively, and the decontamination factors for fission products are shown in Table 1, which shows that it is better than 10 4 , the process takes 180 minutes.

[0096] Table 1 The recovery rate and decontamination factor analysis of activation product americium uranium gallium

[0097]

[0098]

[0099] "*" indicates the lower limit of detection assigned for non-detection.

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PUM

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Abstract

The invention discloses a fast separation method of activation products of americium, uranium and gallium. The fast separation method comprises preparation before separation, chromatographic separation and process control. The separation method comprises making a radioactive solution of fission product-rich activation products of americium, uranium and gallium flow through a P204 or LN chromatographic column, an Al2O3 chromatographic column, a TBP chromatographic column and a DN chromatographic column at a certain flowing rate so that americium, uranium and gallium adsorption is realized, orderly making dilute acid and peracid solutions go through a DN chromatographic layer-P204 or LN chromatographic layer series column and a P204 or LN chromatographic layer-TBP chromatographic layer series column so that americium and uranium readsorption separation is realized and making a desorption solution go through chromatographic column groups corresponding to americium, uranium and gallium, wherein the eluants respectively are radioactivity measurement solutions of activation products of americium, uranium and gallium. The fast separation method has an americium recovery rate higher than 75%, a uranium and gallium recovery rate higher than 90%, a fission product decontamination factor higher than 104 and separation process time of 3h.

Description

technical field [0001] The invention belongs to the technical field of radiochemical separation of activation products, and specifically discloses a rapid separation device and method for activation products americium (Am) uranium (U) gallium (Ga). Background technique [0002] The neutron flux and neutron energy in the nuclear fission process can be determined indirectly by analyzing the content and type of activation products. Uranium and plutonium are the most commonly used fissile material nuclear fuel. In order to realize the multiplication of nuclear fission process and sustainable development of nuclear energy, the use of uranium and plutonium mixed fuel has become a new type of nuclear fuel (MOX fuel) construction direction (Gu Zhongmao. my country's advanced nuclear fuel cycle technology development Some thoughts on strategy. Nuclear Chemistry and Radiation Chemistry. 2006,28(1):1-9.). As a fissile material, uranium and plutonium fissile materials have a good homoge...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G01N1/34
CPCG01N1/34G01N1/405
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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