Method for coextracting uranium, plutonium and neptunium

An extraction and neptunium co-extraction technology, applied in the field of co-extraction of plutonium, uranium and neptunium, can solve the problems of increasing the salt content of radioactive waste, increasing the difficulty and cost of nuclear waste disposal, and the low extraction rate of neptunium

Active Publication Date: 2012-11-14
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

In addition, because the above formula is a reversible reaction, there will still be some Np(V) that cannot be oxidized into Np(VI), making it difficult for the neptunium in the feed liquid to be completely extracted into the 1AP organic phase, and the extraction rate of neptunium is not high. For example, in The extraction rate of neptunium from the solution to the organic phase in the co-decontamination (1A) stage is about 82% in the French UP-3 factory, about 70% in the British Wenzkell factory, and about 88% in the Japane

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  • Method for coextracting uranium, plutonium and neptunium
  • Method for coextracting uranium, plutonium and neptunium

Examples

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Embodiment 1

[0035] A method of co-extraction of uranium, plutonium, and neptunium. This method is to co-extract neptunium with uranium and plutonium in the co-decontamination section to make it enter the organic phase 1AP. The key is to oxidize Np(V) into energy in the 1A extractor. Np(VI) extracted by the extractor.

[0036] figure 1 Schematic diagram of the co-decontamination separation cycle. The total decontamination section is divided into two parts, 1AX to 1AF are extraction sections, and 1AF to 1AS are washing sections.

[0037] 1AF is a nuclear fuel solution, which is an aqueous solution of nitric acid containing uranium, plutonium, neptunium, sub-actinium MA (neptunium, americium, curium), shard elements, etc., 1AF is fed from the middle of the extractor; 1AX is an extractant with the composition 30% TBP / kerosene, the extractant is fed from the outlet stage of the aqueous raffinate of the extractor; 1AS is the detergent, which is an aqueous solution of nitric acid, fed from the orga...

Embodiment 2

[0040] A method of co-extraction of uranium, plutonium, and neptunium. This method is to co-extract neptunium with uranium and plutonium in the co-decontamination section to make it enter the organic phase 1AP. The key is to oxidize Np(V) into energy in the 1A extractor. Np(VI) extracted by the extractor.

[0041] figure 1 It is a schematic diagram of the co-decontamination separation cycle, where the nitric acid concentration in 1AF is 3.50 mol / L, and the nitric acid concentration in 1AS is 3.0 mol / L. The concentration of nitrous acid in the water phase of the extraction section is 1×10 -4 mol / L. 1AX:1AS (organic phase: water phase) flow ratio range is 3: 1 uranium saturation is 60%, the operating temperature of extraction section and washing section are 50℃ and 20℃ respectively.

[0042] UV-UV-Visible spectrophotometer was used to analyze the uranium concentration and nitrous acid concentration in the sample, and the yield of uranium product was greater than 99.99%. The plutoni...

Embodiment 3

[0044] The method is the same as that used in Example 2, except for the process parameters. The nitric acid concentration in 1AF is 4.50 mol / L, and the nitric acid concentration in 1AS is 3.5 mol / L. The concentration of nitrous acid in the water phase of the extraction section is 8×10 -4 mol / L. The 1AX:1AS flow ratio range is 5:1. The uranium saturation is 65%, and the operating temperatures of the extraction section and the washing section are 40℃ and 25℃ respectively.

[0045] UV-UV-Visible spectrophotometer was used to analyze the uranium concentration and nitrous acid concentration in the sample, and the yield of uranium product was greater than 99.99%. The plutonium concentration and neptunium concentration in the sample were analyzed by α spectrum, and the yield of plutonium was greater than 99.9%. , The yield of neptunium is greater than 99%.

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Abstract

The invention belongs to the technical field of nuclear fuel cycles, and discloses a method for coextracting uranium, plutonium and neptunium. The method is implemented in a way that: neptunium is coextracted with uranium and plutonium at the co-decontamination section, so that the neptunium enters an organic phase 1AP. The key point is to oxidate Np (V) in an extraction apparatus 1A into Np (VI) which can be extracted by the extraction apparatus. The method implements high yields of uraniumm, plutonium and neptunium, does not increase the salt content in the after-treatment process, and can implement quantitative extraction of the uranium, plutonium and neptunium.

Description

Technical field [0001] The invention belongs to the technical field of nuclear fuel cycle, and specifically relates to a method for co-extraction of uranium, plutonium and neptunium. Background technique [0002] 237 Np is a transuranium element, a fissile nuclear material, and one of the by-products of the reprocessing plant, with a half-life of 2.14×10 6 year. In a typical light water reactor spent fuel, each ton of spent fuel contains about 500-700 grams 237 Np; in fast reactor spent fuel, there are approximately 200 grams per ton of spent fuel 237 Np. [0003] due to 237 Np is highly radioactive. In the nuclear fuel cycle, if it is used as nuclear waste for geological disposal after glass solidification, the disposal cost is high and it will have an incalculable impact on the ecological environment. And if it will be greater than 99% 237 Separating Np from spent fuel can greatly reduce the radioactive toxicity of nuclear waste and the cost of geological disposal. In addition,...

Claims

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Application Information

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IPC IPC(8): C22B3/26C22B60/02C22B60/04
CPCY02E30/30Y02W30/50
Inventor 张虎叶国安李丽
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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