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Process for reprocessing a spent nuclear fuel and of preparing a mixed uranium-plutonium oxide

a technology of uranium-plutonium oxide and reprocessing process, which is applied in the direction of uranium oxide/hydroxide, nuclear elements, greenhouse gas reduction, etc., can solve the problems of considerable overcost and achieve the effect of minimizing the risk of plutonium misappropriation

Inactive Publication Date: 2009-07-23
COMMISSARIAT A LENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Benefits of technology

This process effectively decontaminates uranium and plutonium from fission products, minimizes the risk of plutonium misappropriation, and produces a mixed uranium-plutonium oxide powder usable in both fast and light-water reactors, reducing the need for enhanced radiation protection and enabling direct use in MOX fuel manufacturing.

Problems solved by technology

Although the presence of radioactive fission products in non-negligible quantities in fresh nuclear fuels is not an obstacle to the use of these fuels in fast neutron reactors, this is not the case as regards their use in the current light-water reactors.
This is because such a use would make it necessary to develop a new type of fuel having a substantially increased content of fissile material because of the neutron-absorbing character of certain fission products and to carry out lengthy and expensive studies in order to obtain homologation of this fuel.
Implementation of this method on an industrial scale would therefore necessarily involve either substantial reinforcement of the radiological protection with which existing nuclear fuel reprocessing and production installations are provided, or the production of new installations especially designed for operating a highly radioactive processing chain, which in both cases would result in a very considerable overcost.

Method used

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  • Process for reprocessing a spent nuclear fuel and of preparing a mixed uranium-plutonium oxide
  • Process for reprocessing a spent nuclear fuel and of preparing a mixed uranium-plutonium oxide
  • Process for reprocessing a spent nuclear fuel and of preparing a mixed uranium-plutonium oxide

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first embodiment

[0094]The description firstly refers to FIG. 1, which shows a block diagram of a first embodiment mode of the process of the invention, designed to obtain a mixed uranium-plutonium oxide powder containing no neptunium and able to be used directly in the manufacture of an MOX nuclear fuel, from a dissolution liquor of a spent UO2 nuclear fuel that has been conventionally prepared, that is to say by dissolving this fuel in nitric acid and clarifying the resulting mixture.

[0095]Such a dissolution liquor typically contains 200 to 300 g / L of uranium per 2 to 3 g / L of plutonium, i.e. a U / Pu ratio of about 100 / 1, and has a content of fission products of around 50 to 70 Ci per gram of plutonium.

[0096]As mentioned previously, the process of the invention firstly comprises a step designed to separate the uranium and the plutonium from the fission products, the americium and the curium.

[0097]As may be seen in FIG. 1, this separation step comprises:[0098]an operation, labelled “U / Pu coextractio...

second embodiment

[0148]FIG. 5 illustrates schematically a second embodiment mode of the process of the invention which, unlike the previous ones, is designed to obtain a mixed uranium-plutonium oxide powder, which also contains neptunium, from a dissolution liquor of a spent UO2 nuclear fuel.

[0149]In this embodiment mode, the process takes place as in the mode of implementation illustrated in FIG. 3 except that it does not include the elimination of the neptunium during the “FP scrubbing” of the purification step.

[0150]The neptunium therefore accompanies the plutonium with which it was back-extracted during the “Pu / U back-extraction” throughout all the subsequent steps of the process until a mixed uranium-plutonium-neptunium oxide is obtained.

[0151]To give an example, a simulation was carried out using the PAREX Code of the Commissariat a L'Energie Atomique for the first embodiment mode of the process of the invention illustrated in FIG. 1.

[0152]The data of this simulation were the following:

Dissolu...

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Abstract

A process for reprocessing a spent nuclear fuel and for preparing a mixed uranium-plutonium oxide. The process: a) separates the uranium and plutonium from fission products, americium, and curium that are present in an aqueous nitric solution resulting from dissolution of the fuel in nitric acid, the separating including at least one operation of coextracting the uranium and plutonium from the solution by a solvent phase; b) partitions the coextracted uranium and plutonium to a first aqueous phase containing plutonium and uranium, and a second aqueous phase containing uranium but no plutonium; c) purifies the plutonium and uranium that are present in the first aqueous phase; and d) coconverts the plutonium and uranium to a mixed uranium / plutonium oxide.

Description

TECHNICAL FIELD[0001]The present invention relates to a novel process for reprocessing a spent nuclear fuel, based on uranium oxide or on mixed uranium-plutonium oxide, which makes it possible for the uranium and plutonium to be very effectively decontaminated from other chemical elements contained in this fuel without leaving, at any moment during this process, plutonium without uranium, so as to minimize the risk of misappropriating the plutonium for military purposes.[0002]The process of the invention also makes it possible to obtain, at the end of this decontamination, a mixed uranium-plutonium oxide powder that can be used directly in processes for manufacturing MOX (Mixed OXide Fuel) nuclear fuels, such as the MIMAS (MIcronized MASter Blend) process.PRIOR ART[0003]At the present time, all plants for reprocessing spent nuclear fuels use the PUREX (Plutonium Uranium Refining by EXtraction) process for recovering the uranium and plutonium that are present in these fuels.[0004]Thi...

Claims

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Application Information

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Patent Type & Authority Applications(United States)
IPC IPC(8): C09K11/04
CPCC01G43/003C01G43/01G21C19/46C01G56/001C01G56/00Y02W30/50Y02E30/30
Inventor BARON, PASCALDINH, BINHMASSON, MICHELDRAIN, FRANCOISEMIN, JEAN LUC
Owner COMMISSARIAT A LENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
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