Improvement of the purex method and uses thereof

A solvent phase and extraction technology, applied in the direction of reactors, recycling technology, reactor fuel elements, etc.

Active Publication Date: 2007-12-12
ORANO RECYCLAGE
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  • Abstract
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  • Claims
  • Application Information

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Problems solved by technology

[0027] The inventors have further set themselves the object that it should be possible to obtain a separation of uranium from neptunium without the need for a powerful neptunium chelating agent which will undoubtedly carry neptunium into an aqueous fluid different from uranium, However, the chelating agent itself or the products of its decomposition will tend to form unwanted products in the aqueous effluent, which will inevitably lead to the need for additional special treatment of these effluents.

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  • Improvement of the purex method and uses thereof
  • Improvement of the purex method and uses thereof
  • Improvement of the purex method and uses thereof

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Embodiment Construction

[0067] Reference is first made to FIG. 3 which shows a block diagram of a first exemplary embodiment of the method of the present invention, designed to allow stripping of neptunium(IV) during uranium / plutonium separation.

[0068] In this example, like the first purification cycle of the plutonium Rex process illustrated in Figure 1, the process of the present invention includes the following operations:

[0069] Co-extraction of uranium, plutonium and neptunium with oxidation state (VI), (IV) and (VI) respectively from the solution, the solution adopts the solvent composed of TBP in TPH with a concentration of 30% (v / v), The co-extracted solvent phase is then washed with aqueous nitric acid in order to complete the purification of uranium, plutonium and neptunium from fission products (“extraction-washing”);

[0070] ● Uranium / plutonium separation, which includes:

[0071] - reverse extraction of plutonium in oxidation state (III) from a solvent loaded with uranium, plutoni...

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Abstract

The procedure consists of separating the uranium, plutonium, other actinides and fission products from the spent fuel in a nitric acid solution, separating the uranium from the plutonium in two separate flows by extracting the plutonium from the solvant phase in a nitric acid aqueous solution with a reducing agent, and then concentrating the solution containing the uranium (III). Part of the concentrated solution is used to extract the actinides (IV) present in the oxidated state, the actinides (IV) being neptunium (IV), thorium (IV) and/or plutonium (IV).

Description

technical field [0001] The present invention relates to an improvement of the method for the reprocessing of spent nuclear fuel known under the name PUREX method. [0002] In particular, the particular method according to the invention makes it possible to separate uranium from other actinides (plutonium, neptunium, thorium, . . . ) in a single purification cycle. [0003] Like the plutonium-rex method, this method can be used for the reprocessing of spent nuclear fuel based on uranium oxide, mixed oxides of uranium and plutonium, or mixed oxides of uranium and thorium. Background technique [0004] All current industrial installations for the reprocessing of spent nuclear fuel use the Plutonium Uranium Refining by Extraction method in order to recover the uranium and plutonium present in these fuels. [0005] The method is carried out through multiple purification cycles using liquid-liquid extraction. [0006] The purpose of the first purification cycle is basically the ...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C19/46
CPCG21C19/46Y02E30/30Y02W30/50
Inventor J·莫林
Owner ORANO RECYCLAGE
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