The present disclosure provides systems and methods for fast molten salt reactor fuel-salt preparation. In one implementation, the method may comprise providing fuel assemblies having fuel pellets, removing the fuel pellets and spent fuel constituents from the fuel assemblies, granulating the removed fuel pellets or process feed to a chlorination process, processing the granular spent fuel salt into chloride salt by ultimate reduction and chlorination of the uranium and associated fuel constituents chloride salt solution, enriching the granular spent fuel salt, chlorinating the enriched granular spent fuel salt to yield molten chloride salt fuel, analyzing, adjusting, and certifying the molten chloride salt fuel for end use in a molten salt reactor, pumping the molten chloride salt fuel and cooling the molten chloride salt fuel, and milling the solidified molten chloride salt fuel to predetermined specifications.

A material (e.g., an alloy) comprises molybdenum, rhenium, and at least one element selected from the group consisting of tellurium, iodine, selenium, chromium, nickel, copper, titanium, zirconium, tungsten, vanadium, and niobium. Methods of forming the material (e.g., the alloy) comprise mixing molybdenum powder, rhenium powder, and a powder comprising at least one element selected from the group consisting of tellurium, iodine, selenium, chromium, nickel, copper, titanium, zirconium, tungsten, vanadium, and niobium. The mixed powders may be coalesced to form the material (e.g., the alloy).

A system and a method for the remote monitoring of an irradiated salt mass within a decay enclosure is provided. The system and the method determine a mass ratio of a first radioisotope relative to a second radioisotope, the second radioisotope having a significantly shorter half-life than the first radioisotope. In addition, the second radioisotope includes a shorter half-life than an effective half-life of the decay enclosure, and the first radioisotope includes a longer half-life than the effective half-life of the decay enclosure. The mass ratio quickly decreases outside of a target range after material diversion, while remaining below the target range for several years. As a consequence, the isotopic mass ratio presents a rapid and enduring indicator of inventory change, which is of extreme importance in detecting a diversion of the irradiated salt mass, which remains a potential proliferation target.

A system and a method for the remote monitoring of an irradiated salt mass within a decay enclosure is provided. The system and the method determine a mass ratio of a first radioisotope relative to a second radioisotope, the second radioisotope having a significantly shorter half-life than the first radioisotope. In addition, the second radioisotope includes a shorter half-life than an effective half-life of the decay enclosure, and the first radioisotope includes a longer half-life than the effective half-life of the decay enclosure. The mass ratio quickly decreases outside of a target range after material diversion, while remaining below the target range for several years. As a consequence, the isotopic mass ratio presents a rapid and enduring indicator of inventory change, which is of extreme importance in detecting a diversion of the irradiated salt mass, which remains a potential proliferation target.

A molten salt electrolysis tank, comprises: an anode feeder which is equipped with a mechanism for recovering deteriorated contact resistance that takes place between the metal fuel rod and the anode in the course of the anodic electrolysis; a cathode feeder which is controlled so as to have a potential in a range that causes U and/or Pu ions to be reduced to metal; a heating mechanism for locally heating the metal fuel rod and/or an excitation mechanism for bringing the metal fuel rod into a locally excited state; and a solenoid coil or a permanent magnet that is disposed between the anode feeder and the cathode feeder so as to improve separation efficiency of U and/or Pu ions by applying a combination of an electric field and a magnetic field.

A molten salt electrolysis tank, comprises: an anode feeder which is equipped with a mechanism for recovering deteriorated contact resistance that takes place between the metal fuel rod and the anode in the course of the anodic electrolysis; a cathode feeder which is controlled so as to have a potential in a range that causes U and/or Pu ions to be reduced to metal; a heating mechanism for locally heating the metal fuel rod and/or an excitation mechanism for bringing the metal fuel rod into a locally excited state; and a solenoid coil or a permanent magnet that is disposed between the anode feeder and the cathode feeder so as to improve separation efficiency of U and/or Pu ions by applying a combination of an electric field and a magnetic field.

A method of fabricating metallic fuel from surplus plutonium may include combining plutonium oxide powder and uranium oxide powder to obtain a mixed powder with reduced proliferation potential. The mixed powder may be electroreduced in a bath of molten salt so as to convert the mixed powder to a first alloy. The first alloy may be pressed to remove a majority of the molten salt adhered to the first alloy to form a pressed alloy-salt mixture. The first alloy may be isolated from the salt by melting the pressed alloy-salt mixture. The first alloy may be further processed to fabricate a fuel rod. Accordingly, the metallic fuel produced may be used in a fast reactor system, such as a Power Reactor Innovative Small Module (PRISM).

A method of making a nuclear fuel structure may include reducing a metal oxide in a cathode assembly so as to deposit a metal of the metal oxide on the cathode plate of the cathode assembly, and processing the cathode plate with the metal deposited thereon to fabricate the nuclear fuel structure. The cathode plate may include an upper blade including an electrically conductive material, a lower blade portion connected to the upper blade, and a connection structure configured to secure the lower blade portion to the upper blade while providing electrical continuity. The connection structure may be configured to be disconnected from the lower blade portion to detach the lower blade portion from the upper blade.

A method of making a nuclear fuel structure may include reducing a metal oxide in a cathode assembly so as to deposit a metal of the metal oxide on the cathode plate of the cathode assembly, and processing the cathode plate with the metal deposited thereon to fabricate the nuclear fuel structure. The cathode plate may include an upper blade including an electrically conductive material, a lower blade portion connected to the upper blade, and a connection structure configured to secure the lower blade portion to the upper blade while providing electrical continuity. The connection structure may be configured to be disconnected from the lower blade portion to detach the lower blade portion from the upper blade.

A method for processing a spent nuclear fuel is disclosed which includes a step for decontaminating uranium(VI) from one or more actinides(IV) and more specially from neptunium and/or plutonium, by complexing this (these) actinide(s)(IV). This method includes a step for decontaminating uranium (VI) from at least one actinide(IV), which decontaminating step comprises at least one operation for stripping the actinide(IV) from an organic phase, not miscible with water, and wherein uranium(VI) and the actinide(IV) are present, by putting the organic phase into contact with an aqueous phase comprising nitric acid and at least one complexing agent which more strongly complexes actinides(IV) than uranium(VI), and then separating the organic phase from the nitric aqueous phase, wherein the at least one complexing agent is a diglycolamide.