Patent · US Active

Method for the treatment of an aqueous nitric solution resulting from dissolving spent nuclear fuel, said method being performed in a single cycle and without requiring any operation involving reductive stripping of plutonium

US10249396B2 · kind B2 · utility

0Cited by

4References

15Claims

0Family size

Assignees

COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES · FR
ORANO CYCLE · FR

Inventors

Manuel Miguirditchian · Avignon, FR
Christian Sorel · Villeneuve-lès-Avignon, FR
Sylvain Costenoble · Bagnols-sur-Cèze, FR
Vincent Vanel · Les Angles, FR
Xavier Heres · Avignon, FR
Pascal Baron · Colomiers, FR
Michel Masson · Avignon, FR
Laurence Chareyre · Vernon, FR

Key dates

Filing date	Jul 28, 2016
Grant date	Apr 2, 2019
Priority date	—
Expiry date	Jul 28, 2036

Classification

Technology area (CPC Y)Emerging Cross-Sectional Technologies
CPC primaryY02W30/50
WIPO fieldMaterials, metallurgy
WIPO sectorChemistry

Abstract

A method for the treatment of an aqueous solution resulting from the dissolution of a spent nuclear fuel in nitric acid, allowing the uranium and plutonium contained in the solution to be extracted, separated and decontaminated in a single cycle, without requiring any operation involving a reductive stripping of plutonium. Applications for the method include the processing of uranium-based and/or plutonium-based spent nuclear fuels.

Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.