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Rapid neptunium separating method

A fast, organic-phase technology used in chemistry to solve problems such as slow separation rates

Inactive Publication Date: 2018-11-13
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0013] The present invention is aimed at the problems existing in the prior art, especially for the problem that the method for separating neptunium from the organic phase using n-butyraldehyde has a slow separation rate. Method for rapid separation of neptunium in process 1AP (organic phase loaded with uranium, plutonium and neptunium)

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Embodiment 1

[0034] Schematic representation of fast separation of neptunium in the Purex flow process according to an embodiment of the present invention, such as figure 2 As shown, the neptunium is reductively stripped to the water phase by using a multi-stage countercurrent reduction stripping process, and the uranium and plutonium are retained in the organic phase to realize the separation and extraction of neptunium. The reducing agent methylhydrazine is added from the outlet of the organic phase, the outlet of the organic phase is the nth stage, n>2, the reducing agent is dissolving methylhydrazine in aqueous nitric acid solution, wherein the concentration of methylhydrazine is a, 0<a≤1.0 mol / L, the concentration of nitric acid is b, 0<b≤5.0mol / L, the flow ratio of adding reducing agent is: organic phase material solution containing uranium, neptunium and plutonium / reducing agent=1 / 10~1 / 0.1. The supplementary extraction agent is added from the outlet of the water phase, the outlet o...

Embodiment 2

[0036] According to another embodiment of the present invention, the same as embodiment 1, the difference is that the multistage countercurrent reduction and stripping is that the reducing agent methylhydrazine is added from the nth stage water phase inlet of the multistage centrifugal extractor, n >2, the supplementary extraction agent is added from the first-stage organic phase inlet of the multi-stage centrifugal extractor, and the organic phase feed solution containing uranium, neptunium and plutonium is added from the i-stage of the multi-stage centrifugal extractor, 1<i<n.

Embodiment 3

[0038] According to an embodiment of the present invention, a 12-stage centrifugal extractor is used with a mixing chamber of 0.7 mL; a syringe pump of model MSP1-C1 is used as the liquid flow delivery device. Concentrated nitric acid, tributyl phosphate (TBP), and sodium nitrite are all national medicines, analytically pure; kerosene is hydrogenated kerosene; uranyl nitrate is analytically pure. Np(Ⅵ) solution: Neptunium nitrate solution was electrolyzed at a constant current, using an H-shaped glass electrolytic cell with a diaphragm, a platinum mesh as an anode, and a titanium sheet as a cathode, and the current density was controlled at 30mA cm-2 for electrolytic oxidation to prepare Np(Ⅵ) ) solution, Np(Ⅵ) is generated when the anode solution is rose red. Carry out spectral scanning on the anolyte, when there is an absorption peak at 1225nm (Np(Ⅵ)), and there is no absorption peak at 980nm (Np(V)) and 960nm (Np(Ⅳ)), the solution in the anode chamber is collected as Np(Ⅵ ...

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Abstract

The invention discloses a rapid neptunium separating method. The method comprises the steps that neptunium is reduced and reextracted to a water phase through a multi-stage reverse flow reduction andreextraction process, uranium and plutonium are reserved in an organic phase, and neptunium separation and extraction are achieved. Rapid separation of neptunium from uranium and plutonium is achieved, the extraction technological time is shortened, the technological process of separating and extracting neptunium is simplified, and the difficulty of purifying neptunium from follow-up processes (neptunium purification cycle and plutonium purification cycle) is lowered.

Description

technical field [0001] The invention belongs to the field of chemistry, in particular to a method for rapidly separating neptunium. Background technique [0002] Power reactor spent fuel contains about 95% uranium, about 1% plutonium, about 4% fission products and minor actinides (Np, Am, Cm). in 237 The output of Np (neptunium) in spent fuel increases with the increase of burnup. In spent fuel with a burnup of 45GWd, 237 Np content is about 0.65kg / tHM. 237 Np is an alpha emitter with a half-life of 2.14×10 6 years, with high radiotoxicity. Studies have shown that if 99.9% of the uranium, plutonium and minor actinides (Np, Am, Cm) in the spent fuel are separated from the fragmentation products, they can be fissioned or transformed into short-lived or stable nuclei by neutron nuclear reactions. It can shorten the isolation time of radioactive waste from the biosphere to hundreds to thousands of years, which can greatly reduce the volume and radioactivity level of high-le...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C22B60/02
CPCC22B60/0295
Inventor 张虎刘占元王日腾杨贺宁勇智李传博刘协春
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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