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Ruthenium purifying technology in plutonium purification cycle of Purex process

A purification process, plutonium purification technology, applied in the field of ruthenium purification process in the Purex process plutonium purification cycle, to achieve the effect of improving purity, high plutonium yield, and reducing ruthenium content

Active Publication Date: 2015-03-11
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

There is no report on the purification of ruthenium in the plutonium purification cycle in the open literature at home and abroad

Method used

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  • Ruthenium purifying technology in plutonium purification cycle of Purex process

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0014] At a temperature of 20°C, add extractant 2AX and detergent 2AS to the 2A tank to remove a small amount of fission elements such as uranium and ruthenium in the 2AF feed liquid. The key point is that the extractant 2AX used is 30%TBP / kerosene, Detergent 2AS is c(HNO 3 )=0.5mol / L aqueous solution, the flow ratio 2AF:2AX:2AS=3.5:1:0.45, the composition of the 2AF feed liquid used is: c(Pu 4+ )=6.8g / L, c(UO 2 2+ )=0.74g / L, c(HNO 3 )=3.5mol / L, c(Ru)=0.3108mg / L aqueous solution, the selected extraction stage is 8 stages, the washing stage is 6 stages, and the ratio of the organic phase to the aqueous phase is 2:1.

[0015] During the experiment, the tank was first filled with uranium and plutonium-free feed solution for two hours, and then the feed solution containing uranium and plutonium was added. After running for 5.0 hours, an instant sample was taken every 2 hours. After running for 16 hours, the tank was stopped for analysis .

[0016] Experimental results: the yi...

Embodiment 2

[0018] The same procedure as that used in Example 1, except that the detergent 2AS is c(HNO 3 )=1mol / L aqueous solution, the selected flow ratio 2AF:2AX:2AS=5:1:0.45, the composition of 2AF is c(Pu 4+ )=2.75g / L, c(UO 2 2+ )=1.2g / L, c(HNO 3 )=3.5mol / L, c(Ru)=0.054mg / L aqueous solution, the number of extraction stages is 9, the number of washing stages is 8, and the temperature is 30°C. The obtained experimental results are: the yield of plutonium is 99.97%, Purification factor DF of Ru Ru =3590.

Embodiment 3

[0020] The same procedure as that used in Example 1, except that the detergent 2AS is c(HNO 3 )=1.5mol / L aqueous solution, the selected flow ratio 2AF:2AX:2AS=6:1:0.45, the composition of 2AF is c(Pu 4+ )=2.75g / L, c(UO 2 2+ )=1.2g / L, c(HNO 3 )=3.5mol / L, c(Ru)=0.054mg / L aqueous solution, the number of extraction stages is 10, the number of washing stages is 10, and the temperature is 30°C. The obtained experimental results are: the yield of plutonium is 99.98%, Purification factor DF of Ru Ru =3120.

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Abstract

The invention belongs to the technical field of nuclear fuel reprocessing, and discloses a purification process for ruthenium in the plutonium purification cycle of the Purex process. The process is to add an extractant 2AX and a detergent 2AS in the 2A tank to remove a small amount of ruthenium in the 2AF feed liquid. The composition of extractant 2AX is 30%TBP / kerosene, detergent 2AS is c(HNO3)=0.5~1.5mol / L aqueous solution, flow ratio 2AF:2AX=3.5~6, extraction count is 8~10, washing grade The number is greater than 6 grades. The process further purifies the ruthenium and improves the quality of the final plutonium product of the Purex process.

Description

technical field [0001] The invention belongs to the technical field of nuclear fuel reprocessing, and in particular relates to a purification process for ruthenium in the plutonium purification cycle of the Purex process. Background technique [0002] The Purex process includes a co-decontamination separation cycle, a plutonium purification cycle and a uranium purification cycle. One of the main purposes of the decontamination and separation cycle is to achieve the maximum separation between uranium, plutonium and fissile elements, and the uranium purification cycle and plutonium purification cycle are to obtain high-purity uranium and plutonium products. Ruthenium is one of the fission products to be removed in reprocessing. It is a strong γ-radioactive nuclide. Its amount in uranium and plutonium products directly determines the personnel protection standards for reprocessing operations. An important test item. [0003] In the co-decontamination separation cycle, by addi...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): C22B3/40C22B60/04
Inventor 肖松涛刘协春罗方祥杨贺兰天孟照凯
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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