US 2024/0312656 A1Published application

Systems and methods for electrochemical extraction of reduced fission products from irradiated molten salt compositions

AssigneeAbilene Christian University

InventorsKim Pamplin, Diego Zometa

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Abstract

Fission of uranium-235 produces a wide range of fission products. Of particular importance is the production of molybdenum-99 due to its uses in the medical field. Fission products can be extracted from a molten salt reactor through electrochemical deposition by utilizing an electrode submerged in the flow of irradiated molten salt. However, this is likely to disrupt the redox of the irradiated molten fuel leading to harmful corrosion of the reactor. The present invention utilizes three electrode sets to capture fission products from irradiated molten salt of a molten salt reactor, monitor the redox behavior of the irradiated molten salt, and maintaining the balance of uranium ions to avoid harmful corrosion to the reactor's core.

Claims24

Dependent claims

A system for capture of fission products from irradiated fueled molten salt of a molten salt reactor system comprising:

a first electrode circuit comprising a first working electrode, the first electrode circuit operable to capture the fission products from the irradiated fueled molten salt by electrochemical deposition of the fission products onto the first working electrode;
a second electrode circuit comprising a second working electrode and a potentiostat, the second electrode circuit operable to adjust a ratio of uranium(IV) to uranium(III) of the irradiated fueled molten salt by oxidation of uranium(III) by the second working electrode;
a third electrode circuit comprising a meter electrically coupled with the potentiostat operable to measure an electric potential of the irradiated fueled molten salt;
wherein the potentiostat is operable to adjust an electric current provided to the second working electrode upon the meter reading that the electric potential of the irradiated fueled molten salt has reached a predetermined threshold;
and
wherein the first electrode circuit, second electrode circuit, and third electrode circuit are housed in a conduit of the molten salt reactor system.

3 more elements

A system comprising:

a fuel salt system configured to circulate an irradiated fueled molten salt through a molten salt loop, the molten salt loop including a reactor vessel;
and
an extraction system fluidly coupled to the reactor vessel along the molten salt loop, the extraction system, comprising
a first electrode circuit comprising a first working electrode, the first electrode circuit operable to capture the fission products from the irradiated fueled molten salt by electrochemical deposition of the fission products onto the first working electrode;
a second electrode circuit comprising a second working electrode and a potentiostat, the second electrode circuit operable to adjust a ratio of uranium(IV) to uranium(III) of the irradiated fueled molten salt by oxidation of uranium(III) by the second working electrode;
a third electrode circuit comprising a meter electrically coupled with the potentiostat operable to measure an electric potential of the irradiated fueled molten salt;
wherein the potentiostat is operable to adjust an electric current provided to the second working electrode upon the meter of the third electrode circuit reading that the electric potential of the irradiated fueled molten salt has reached a predetermined threshold;
and
wherein the first electrode circuit, second electrode circuit, and third electrode circuit are housed in a conduit of the molten salt loop.

6 more elements

Dependencies are inferred from the claim text.