Ruthenium purifying technology in plutonium purification cycle of Purex process

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

Active Publication Date: 2013-12-18
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

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Experimental program
Comparison scheme
Effect test

Embodiment 1

[0014] Under the condition of temperature of 20℃, add extractant 2AX and detergent 2AS in tank 2A ​​to remove a small amount of fission elements such as uranium and ruthenium in the 2AF feed liquid. The key is that the extractant 2AX used is 30% TBP / kerosene, Detergent 2AS is c(HNO 3 )=0.5mol / L aqueous solution, the flow ratio is 2AF:2AX:2AS=3.5:1:0.45, and the composition of the 2AF feed solution 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, the washing stage is 6, and the ratio of organic phase to water phase is 2:1.

[0015] During the experiment, the tank was filled with the feed solution without uranium and plutonium for two hours, and then the feed solution containing uranium and plutonium was added. After running for 5.0 hours, samples were taken every 2 hours. After running for 16 hours, the bath was stopped for analysis. .

[0016] Experimental results: the yield of urani...

Embodiment 2

[0018] The steps used in Example 1 are the same, except that the detergent 2AS is c(HNO 3 )=1mol / L aqueous solution, the selected flow ratio is 2AF:2AX:2AS=5:1:0.45, and 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 steps used in Example 1 are the same, except that the detergent 2AS is c(HNO 3 )=1.5mol / L aqueous solution, the selected flow ratio is 2AF:2AX:2AS=6:1:0.45, and 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 postprocessing, and discloses a ruthenium purifying technology in a plutonium purification cycle of a Purex process; according to the ruthenium purifying technology, extraction agent 2AX and detergent 2AS are added in 2A tank for removing a small amount of ruthenium element in 2AF material liquid, the used extraction agent 2AX comprises 30%TBP (Tri-Butyl-Phosphate) / kerosene, the detergent 2AS is an aqueous solution with C(HNO3) being 0.5-1.5 mol / L, the flow ratio of 2AF:2AX is 3.5-6, the extraction count is 8-10 grades and the washing grade is more than 6 grades. The ruthenium purifying technology can further purify the ruthenium, and can improve the quality of a 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 Applications(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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