HYDROMETALLURGICAL PROCESS FOR THE TREATMENT AND RECYCLING OF SPENT FUEL SALT FROM A MOLTEN CHLORIDE NUCLEAR REACTOR

A hydrometallurgical process for recycling spent fuel salts from molten chloride nuclear reactors recovers actinides and chlorine through dissolution, precipitation, electrolysis, and liquid-liquid extraction, addressing the need for efficient recycling and waste reduction in nuclear fuel treatment.

FR3170694A1Pending Publication Date: 2026-06-26COMMISSARIAT A LENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES +1

Patent Information

Authority / Receiving Office
FR · FR
Patent Type
Applications
Current Assignee / Owner
COMMISSARIAT A LENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
Filing Date
2024-12-20
Publication Date
2026-06-26

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Abstract

The invention relates to a hydrometallurgical process for the treatment and recycling of spent fuel salt from a molten chloride nuclear reactor, comprising at least the steps of: a) precipitation of chloride ions present in the spent fuel salt by: - ​​dissolving the spent fuel salt in an aqueous solution of nitric acid comprising a nitrate of a metal M; or - dissolving the spent fuel salt in an aqueous solution of nitric acid and adding the nitrate of metal M to the resulting solution; thereby obtaining a two-phase medium consisting of a precipitate of chloride of metal M and an aqueous nitric phase comprising the metals of the spent fuel salt in the form of nitrates; b) separation of the precipitate of chloride of metal M from the aqueous nitric phase; c) dissociation of the precipitate of chloride of metal M obtained in step b) into chlorine and metal M, with recovery of the chlorine;d) selective recovery of at least one of the actinides present in the aqueous nitric phase obtained in step b) by implementing at least one liquid-liquid extraction-deextraction process; ete) use of the dichlorine recovered in step c) and of said at least one actinide recovered in step d) to produce a new fuel salt for a molten chloride nuclear reactor.;
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