阅读说明：本技术 熔融盐反应器中的电化学分离机构 (Electrochemical separation mechanism in molten salt reactor ) 是由 约翰·班森 马修·曼马特 于 2019-05-29 设计创作，主要内容包括：一些实施例包括用于熔融盐反应器的化学分离机构,其中,所述熔融盐可以包括裂变产物。在一些实施例中,所述化学分离机构包括：熔融盐容器,其具有部署在其内的熔融盐；溶剂容器,其具有部署在其内的溶剂；电极；和电极机构。在一些实施例中,所述电极机构用于：将所述电极沉浸到所述熔融盐容器中,以使得化学反应发生在所述电极与所述熔融盐中的所述裂变产物中的一个或多个之间。在一些实施例中,所述电极机构可以将所述电极沉浸到所述溶剂容器中,以使得化学反应发生,导致所述裂变产物中的一个或多个沉积到所述溶剂中。(Some embodiments include a chemical separation mechanism for a molten salt reactor, wherein the molten salt may include fission products. In some embodiments, the chemical separation mechanism comprises: a molten salt vessel having molten salt disposed therein; a solvent container having a solvent disposed therein; an electrode; and an electrode mechanism. In some embodiments, the electrode mechanism is for: immersing the electrode into the molten salt container such that a chemical reaction occurs between the electrode and one or more of the fission products in the molten salt. In some embodiments, the electrode mechanism may immerse the electrode in the solvent container to cause a chemical reaction to occur resulting in deposition of one or more of the fission products into the solvent.)

1. A chemical separation mechanism, comprising:

a molten salt vessel having a molten salt disposed therein, the molten salt comprising a fission product;

a solvent container having a solvent disposed therein;

an electrode; and

an electrode mechanism for immersing the electrode in the molten salt container to cause a chemical reaction to occur between the electrode and one or more of the fission products in the molten salt, and for immersing the electrode in the solvent container to cause a chemical reaction to occur resulting in deposition of one or more of the fission products into the solvent.

2. The chemical separation mechanism of claim 1, wherein the electrode mechanism comprises a lifting and rotating gantry.

3. The chemical separation mechanism of claim 1, wherein the electrode mechanism comprises a lift and slide electrode mechanism.

4. The chemical separation mechanism of claim 1, further comprising a power source for placing an electrical potential on the electrode.

5. The chemical separation mechanism of claim 1, wherein the molten salt comprises an actinide-containing salt, and wherein the electrode does not react with actinides within the actinide-containing salt.

6. The chemical separation mechanism of claim 1, wherein the molten salt comprises an actinide-containing salt.

7. The chemical separation mechanism of claim 1, wherein the electrode comprises uranium.

8. The chemical separation mechanism of claim 1, wherein the electrode comprises an actinide.

9. The chemical separation mechanism of claim 1, wherein the fission product plates on the electrode when the electrode is placed within the molten salt container.

10. A chemical separation mechanism as claimed in claim 1, wherein the molten salt comprises a fluoride or chloride salt.

11. The chemical separation mechanism of claim 1, further comprising a second electrode disposed within or in contact with the molten salt within the molten salt container.

12. The chemical separation mechanism of claim 1, further comprising a third electrode disposed within or in contact with the solvent within the solvent container.

13. The chemical separation mechanism of claim 1, wherein the chemical separation chamber encloses a noble gas.

14. The chemical separation mechanism of claim 1, further comprising a chemical separation chamber coupled to the molten salt vessel, the chemical separation chamber comprising a getter for collecting one or more gases.

15. A method, comprising:

exposing an electrode to molten salt comprising fission products such that a chemical reaction occurs between the electrode and one or more of the fission products in the molten salt;

removing the electrode from the molten salt; and

exposing the electrode to a solvent such that a chemical reaction occurs resulting in deposition of one or more of the fission products into the solvent.

16. The method of claim 15, further comprising: removing the electrode from the solvent.

17. The method of claim 15, wherein exposing the electrode to the molten salt comprises: operating a lift and rotate gantry or lift and slide electrode mechanism.

18. The method of claim 15, wherein the fission product plates on the electrode when the electrode is exposed to the molten salt.

19. The method of claim 15, wherein the molten salt comprises an actinide-containing salt, and wherein the electrode does not react with actinides within the actinide-containing salt.

20. The method of claim 15, wherein the electrode comprises uranium.

21. The method of claim 15, wherein the molten salt comprises an actinide-containing salt.

22. The method of claim 15, further comprising: providing an electrical potential to the electrode while the electrode is exposed to the molten salt or while the electrode is exposed to the solvent.

Background

Molten salt reactors are a type of nuclear fission reactor in which the primary nuclear reactor coolant or fuel is a molten salt mixture. In general, molten salt reactors operate at higher temperatures than water cooled reactors and therefore can produce higher thermodynamic efficiencies while staying at low vapor pressures. In addition, molten salt reactors can produce interesting and useful fission byproduct products.

Disclosure of Invention

Some embodiments of the invention include a chemical separation mechanism for molten salt reactors; the molten salt in the reactor may include some fission products. In some embodiments, the chemical separation mechanism may include: a molten salt vessel having molten salt disposed therein; a solvent container having a solvent disposed therein; an electrode; and an electrode mechanism. In some embodiments, the electrode mechanism may be configured to: immersing the electrode into the molten salt container such that a chemical reaction occurs between the electrode and one or more of the fission products in the molten salt. In some embodiments, the electrode mechanism may immerse the electrode in the solvent container to cause a chemical reaction to occur resulting in deposition of one or more of the fission products into the solvent.

In some embodiments, the electrode mechanism includes a lifting and rotating gantry. In some embodiments, the electrode mechanism comprises a lift and slide electrode mechanism.

In some embodiments, the chemical separation mechanism may include a power source configured to: an electrical potential is placed on the electrode.

In some embodiments, the molten salt comprises an actinide containing salt, and wherein the electrode does not react with actinides within the actinide containing salt. In some embodiments, the molten salt comprises an actinide-containing salt. In some embodiments, the molten salt comprises a fluoride or chloride salt.

In some embodiments, the fission product may plate on the electrode when the electrode is placed within the molten salt vessel.

In some embodiments, the electrode may comprise uranium. In some embodiments, the electrode may comprise an actinide.

In some embodiments, the chemical separation mechanism may comprise a second electrode disposed within or in contact with the molten salt within the molten salt container. In some embodiments, the second electrode may be disposed within or in contact with the solvent within the solvent container.

In some embodiments, the chemical separation chamber encloses a noble gas.

Some embodiments of the invention may include a method comprising: exposing an electrode to molten salt comprising fission products such that a chemical reaction occurs between the electrode and one or more of the fission products in the molten salt; removing the electrode to the molten salt; and exposing the electrode to a solvent such that a chemical reaction occurs resulting in deposition of one or more of the fission products into the solvent. The method may further comprise: removing the electrode from the solvent. In some embodiments, the method may comprise: providing an electrical potential to the electrode while the electrode is exposed to the molten salt. In some embodiments, the method may comprise: providing an electrical potential to the electrode while the electrode is exposed to the solvent.

In some embodiments, exposing the electrode to the molten salt comprises: the operation raises and rotates the gantry. In some embodiments, exposing the electrode to the molten salt comprises: the lift and slide electrode mechanism is operated.

In some embodiments, the molten salt comprises an actinide containing salt and the electrode does not react with actinides within the actinide containing salt. In some embodiments, the molten salt comprises an actinide-containing salt.

In some embodiments, the electrode may comprise uranium.

Drawings

These and other features, aspects, and advantages of the present disclosure will become better understood when the following detailed description is read with reference to the accompanying drawings.

Figure 1 is a diagram of a molten salt reactor system according to some embodiments.

FIG. 2 is a diagram of a chemical separation subsystem according to some embodiments.

FIG. 3 is a diagram of a chemical separation subsystem having electrodes in a raised position within a chemical separation chamber, according to some embodiments.

Fig. 4 is a diagram of a chemical separation subsystem having an electrode in a lowered position and disposed within a solvent bath, according to some embodiments.

FIG. 5 is a diagram of a chemical separation subsystem according to some embodiments.

FIG. 6 is another diagram of a chemical separation subsystem according to some embodiments.

Figure 7 is a flow diagram representing a process of using electrodes to remove fission products from a molten salt reactor, according to some embodiments.

Detailed Description

Some embodiments of the present disclosure include a chemical separation mechanism that includes a molten salt container and a solvent container. The molten salt vessel may comprise or contain molten salt with fission products. The solvent container may comprise or contain a solvent. The chemical separation mechanism may include: an electrode; and an electrode mechanism configured to: the electrode was immersed in a molten salt container and the electrode was immersed in a solvent container. The electrode mechanism may comprise any type of electromechanical electrode mechanism or electronics to move the electrodes from various positions. The electrodes may react with or bind to some fission products in the molten salt vessel. The electrode may react with or bind to a solvent in the solvent vessel such that fission products bound to the electrode may be deposited or released into the solvent.

The chemical separation mechanism may be utilized in any type of molten salt system or apparatus, including but not limited to thermal spectrum nuclear reactors, fast spectrum nuclear reactors, hyper thermal spectrum nuclear reactors, molten salt test loops, molten salt targets, molten salt neutron sources, and the like. In some embodiments, the solvent comprises a vinyl glycol. In some embodiments, the solvent comprises choline chloride.

In some embodiments, the chemical separation mechanism may include a lift and rotate gantry or a lift and slide electrode mechanism to move the electrodes from one location to another. Various other robots or electromechanical devices may be used.

Systems and methods for electrochemical separation in a molten salt chamber are disclosed. The molten salt reactor may be a nuclear fission reactor, where the primary nuclear reactor coolant or even the fuel itself is the molten salt mixture. In some embodiments, the molten salt reactor may be operated at a higher temperature than the water cooled reactor for higher thermodynamic efficiency while staying at a low vapor pressure. In some embodiments, the fuel in the molten salt reactor may include fluoride salts (e.g., lithium fluoride and beryllium fluoride (FLiBe)) with dissolved uranium (U-235 or U-233) fluoride (UF)₄) The molten mixture of (1). In some embodiments, the uranium may be low enriched uranium, un-enriched uranium, or enriched uranium.

Figure 1 is a diagram of a molten salt reactor system 100 according to some embodiments. Molten salt reactor system 100 may include reactor 102, a chemical separation subsystem (e.g., including chemical separation chamber 120), a safety system (e.g., including one or more emergency drain tanks 165), and turbine 145.

The reactor 102 may comprise any type of molten salt fission device or system, whether or not it comprises a reactor. The reactors 102 may include liquid salt ultra high temperature reactors, liquid thorium fluoride reactors, liquid thorium chloride reactors, liquid salt breeder reactors, liquid salt solid fuel reactors, high flux water reactors with high or low enriched uranium salt targets, and the like.

The molten salt reactor system 100 may employ, for example, one or more molten salts having fissile material. The molten salt may for example comprise fluorineAny salt of chlorine, lithium, sodium, potassium, beryllium, zirconium, rubidium, and the like, or any combination thereof. Some examples of molten salts may include LiF, LiF-BeF₂、2LiF-BeF₂、LiF-BeF₂-ZrF₄、NaF-BeF₂、LiF-NaF-BeF₂、LiF-ZrF₄、LiF-NaF-ZrF₄、KF-ZrF₄、RbF-ZrF₄、LiF-KF、LiF-RbF、LiF-NaF-KF、LiF-NaF-RbF、BeF₂-NaF、NaF-BeF₂And LiF-NaF-KF. In some embodiments, the molten salt may include sodium fluoride, potassium fluoride, aluminum fluoride, zirconium fluoride, lithium fluoride, beryllium fluoride, rubidium fluoride, magnesium fluoride, and/or calcium fluoride.

In some embodiments, the molten salt may comprise any of the following possible salt co-crystals. Many other co-crystals may be possible. The following list also includes the molar ratios and melting points of the example co-crystals. The molar ratios are merely examples. Various other co-crystals may be used.

·LiF-NaF(60-40mol％)652℃

·LiF-KF(50-50mol％)492℃

·LiF-NaF-KF(46.5-11.5-42mol％)454℃

·LiF-NaF-CaF₂(53-36-11mol％)616℃

·LiF-NaF-MgF2-CaF2(～50-～30-～10-～10mol％)～600℃

·LiF-MgF₂-CaF₂(～65-～12-～23mol％)650-725℃

·LiF-BeF₂(66.5-33.5mol％)454℃

·NaF-BeF₂(69-31mol％)570℃

·LiF-NaF-BeF₂(15-58-27)480℃

·LiF-NaF-ZrF₄(37-52-11)604℃

·LiF-ThF₄(71-29)565℃

·NaF-ThF₄(77.5-22.5)618℃

·NaF-ThF₄(63-37)690℃

·NaF-ThF₄(59-41)705℃

·LiF-UF4(73-27)490℃

·NaF-UF₄(78.5-21.5)618℃

·LiF-NaF-UF₄(24.3-43.5-32.2)445℃

The reactor 102 can include a reactor regeneration zone 105 surrounding a reactor core 110. A plurality of rods 115 may be disposed within the reactor core 110. The reactor core 110 may comprise, for example, a uranium rich molten salt (e.g., such as UF)₄-FLiBe). The reactor regeneration zone 105 can include a breeder fuel, which can produce uranium for the reactor core 110. Reactor regeneration zone 105 may include a thorium-rich fluoride salt. For example, reactor regeneration zone 105 may include thorium-232, which is turned to thorium-233 by neutron radiation. Thorium-233 has a half-life of 22 minutes and becomes protactinium-233 by beta decay. Then, the protactinium-233 having a half-life of 22.97 days becomes uranium-233, which is an additional fuel for the reactor core 110, by the second beta decay.

The rods 115 may include any material that may act as a neutron energy moderator (e.g., such as graphite, ZrH_xLight water, heavy water, beryllium, lithium-7, etc.). Neutron moderators may be selected or not used at all based on the need for thermal, epithermal, or fast spectrum neutrons within reactor core 110.

In some embodiments, the molten salt reactor system 100 may include a chemical separation subsystem. The chemical separation subsystem may include, for example, chemical separation chamber 120 and/or chemical separation loop 125. The chemical separation subsystem may be used, for example, to extract fission products (e.g., molybdenum, ruthenium) from molten salts and purify the fission products. The list of fission products can be found, for example, at https:// www-nds. iaea. org/with/fpyield. htm # T1 and/or https:// www-nds. iaea. org/with/fpyield. htm # T2. Other fission products may be included. For example, the chemical separation subsystem may remove fission products from the reactor core without removing actinides (e.g., uranium isotopes (e.g., such as uranium 233, 235), or plutonium isotopes (e.g., such as plutonium 239), or thorium isotopes, etc.). Fig. 2, 3, and 4 illustrate examples of chemical separation subsystems.

The safety subsystem may include an emergency drain line 170, an anti-freeze plug 160, or one or more emergency drain tanks 165. The emergency drain tank 165 is connected to the reactor core 110 via an emergency drain pipe 170. The freeze plug 160 may be an active element that retains fissionable materials within the reactor core 110 unless an emergency condition exists. For example, if the freeze plug 160 is de-energized or otherwise triggered, the drain line is opened and the material in the reactor core 110 is drained into the emergency drain tank 165. The emergency drain tank 165 may include, for example, materials such as energy decelerating materials. For example, emergency drain tank 165 may be placed in any location where the reaction may be controlled. For example, emergency drain tank 165 may be sized to exclude the possibility of a persistent reaction.

Figure 2 is a diagram of a chemical separation subsystem 200 of a molten salt reactor according to some embodiments. The chemical separation subsystem 200 includes a molten salt chemical separation channel 205 that can direct molten salt from a molten salt chamber (e.g., the reactor core 110). The molten salt chemical separation channel 205 may be connected to a molten salt circuit conduit 220, and the molten conduit 220 may guide the molten salt from the molten salt chamber to the molten salt chemical separation channel 205. The molten salt chemical separation channel 205 may feed molten salt into the molten salt reservoirs 210, 215. The molten salt reservoirs 210, 215 may be filled or partially filled with molten salt via a molten salt chemical separation channel 205. In some embodiments, bismuth or other chemical species may be constrained, placed, or deployed by a membrane or mesh within the molten salt reservoir 210, 215, e.g., to chemically remove additional fission products. Molten salt may flow through the molten salt reservoirs 210, 215 and return to the molten salt chamber via molten salt return conduit 245.

In some embodiments, the molten salt surface 225 within the molten salt chemical separation channel 205 may separate the molten salt chemical separation channel 205 from the chemical separation chamber 260. In some embodiments, the chemical separation chamber 260 may be filled with an inert gas or vacuum, which may, for example, prevent exposure of the molten salt surface 225 to undesired reactions or oxidation.

In some embodiments, the electrode 230 may be soaked within the molten salt chemical separation channel 205. The electrode 230 may include an actinide (e.g., such as uranium). The electrodes may be coupled to a lift and rotate frame 235. The elevation and rotation frame 235 may be a mechanical electrode mechanism that elevates the electrode 230 (see fig. 3), rotates the electrode 230, and lowers the electrode 230 (see fig. 4) into the solvent 241 within the solvent container 240. The solvent container 240 may include a solvent 241. In some embodiments, the solvent may include any solvent (including ethylene glycol). In some embodiments, the solvent may be maintained at or near about room temperature. The lift and rotate frame 235 may include one or more of motors, actuators, gears, pulleys, solenoids, cables, etc., that may effectuate movement of the electrodes 230.

In some embodiments, an electrical potential may be placed on the electrode 230 while the electrode is in contact with the molten salt (e.g., actinide-containing salt). In some embodiments, no electrical potential may be required while the electrodes are in contact with the molten salt, and the electrodes 230 will only be conductors. In some embodiments, the potential may be a direct current or an alternating current potential. The second electrode may be in contact with the molten salt to complete (or ground) the electrical circuit. The second electrode may be an electrode coupled to any portion of chemical separation subsystem 200 or may be part of a vessel wall of chemical separation subsystem 200. For example, the second electrode may be part of the vessel wall of the molten salt chemical separation channel 205 and/or the vessel wall of the molten salt circuit conduit 220. The electrical potential between the electrode 230 and the second electrode may create or enhance an electrochemical reaction between the fission products within the molten salt and the electrode 230. In some embodiments, the electrochemical reaction may cause the fission products to plate on the electrode 230. In some embodiments, the potential between the electrodes may vary from as low as 0 volts to as high as 6 volts. The potential may be varied to select which elements are desired to be plated on the electrode 230.

In some embodiments, the magnitude of the electrical potential, the magnitude of the current applied to the electrical potential, the composition of the molten salt, the type and composition of fission products dissolved in the salt, and/or the material 230 of the electrode may determine the reactants that react with the electrode 230. Additionally or alternatively, in some embodiments, the frequency of the alternating potential, the frequency of the alternating current applied to the potential, the composition of the molten salt, and/or the material comprising the electrodes 230 may determine the reactants that react with the electrodes 230.

In some embodiments, the lift and rotate gantry 235 can be partially disposed within the chemical separation chamber 260. In some embodiments, one or more of motors, actuators, gears, pulleys, solenoids, cables, etc. may be coupled to and/or part of the lift and rotate frame 235. In some embodiments, one or more of motors, actuators, gears, pulleys, solenoids, cables, etc. may be disposed outside of chemical separation chamber 260, which causes lifting and rotating frame 235 to lift and/or rotate electrode 230.

In some embodiments, chemical separation chamber 260 can include getter 250, which can include a getter plug. A getter may be used to remove gases from within chemical separation chamber 260. Getter 250 may include, for example, magnesium carbonate, depleted uranium, silver, or copper, among others. In some embodiments, the getter may collect various chemical species, particularly gases (e.g., tritium, hydrogen, deuterium, iodine, krypton, xenon, zirconium, molybdenum, helium, etc.). In some embodiments, the getter 250 may use a pneumatic or mechanical system to remove and/or replace the (potentially saturated) getter to pull the chemical species from the chemical separation chamber 260.

In some embodiments, chemical separation chamber 260 may include gas release port 255. The gas release port 255 can collect a gas product (e.g., such as krypton, xenon, iodine, helium, molybdenum, zirconium, etc.) from the chemical separation chamber 260, for example.

Figure 3 is a diagram of a chemical separation subsystem 200 of a molten salt reactor with electrodes 230 in a raised position within a chemical separation chamber 260, according to some embodiments. In this figure, one or more of motors, actuators, gears, pulleys, solenoids, cables, etc. have been engaged to raise and rotate the frame 235 so that the electrodes 230 are not immersed in the molten salt and not in the solvent 241 in the solvent container 240.

Figure 4 is a diagram of a chemical separation subsystem 200 of a molten salt reactor with electrodes 230 in a lowered position and disposed within a solvent 241 in a solvent vessel 240, according to some embodiments. In some embodiments, when the electrode 230 is in the lowered position and is disposed, placed, or inserted into the solvent 241 within the solvent vessel 240, the potential between the electrode 230 and the second electrode may be reversed and an electrochemical reaction is generated between the fission product on the electrode and the solvent 241 of the solvent vessel 240. In some embodiments, when the electrode 230 is in the lowered position and disposed within the solvent vessel 240, the frequency or magnitude of the electrical potential between the electrode 230 and the second electrode may be changed to produce an electrochemical reaction between the fission product on the electrode and the solvent 241 within the solvent vessel 240. In some embodiments, the fission products may be released, dissolved, and/or deposited into the solvent.

In some embodiments, one of the first or second electrodes may comprise an anode, while the other electrode may comprise a cathode. In some embodiments, a third electrode may be included, which may be a reference electrode. In some embodiments, a third electrode may be included, which may be an additional anode or an additional cathode.

In some embodiments, solvent container 240 may be coupled with a solvent handling subsystem, such as via a conduit and/or solenoid that allows solvent 241 to flow from solvent container 240 to the solvent handling subsystem, for example. In some embodiments, the fission products may be separated from the solvent and/or further processed.

Figure 5 is a diagram of a chemical separation subsystem 200 with a molten salt reactor 270 (e.g., reactor 102) attached, according to some embodiments. Figure 6 is another illustration of a chemical separation subsystem 200 with a molten salt reactor 270 attached, according to some embodiments. In some embodiments, chemical separation subsystem 200 may be coupled with molten salt reactor 270 via molten salt return conduit 245 and/or molten salt loop conduit 220.

Figure 7 is a flow diagram representing a process 700 for using electrodes to remove fission products from a molten salt reactor, according to some embodiments. At block 705, the electrode may be exposed to a molten salt. The electrodes may include, for example, electrode 230. The molten salt may include, but is not limited to, any molten salt described in this document.

At block 710, a potential is provided to the electrode. For example, the electrical potential may vary in voltage and/or frequency depending on the type of molten salt, mixture of molten salts, and/or type of fission product desired to be extracted from the molten salt. For example, the electrical potential may be between an electrode and a second electrode disposed elsewhere in the molten salt. An electrical potential between the electrode and the second electrode may produce an electrochemical reaction between the fission products within the molten salt and the electrode. In some embodiments, the electrochemical reaction may cause the fission products to plate on the electrode.

At block 715, the electrodes may be removed from the molten salt. This may be done in any number of ways. For example, the electrode may be removed using a lifting and rotating gantry. As another example, the electrodes may be removed using one or more of a motor, actuator, gear, pulley, solenoid, or the like. As another example, the electrode may be removed from the molten salt by removing the molten salt.

At block 720, the electrode may be exposed to a solvent. For example, the electrode may be moved to a solvent container. As another example, the chamber in which the electrode is deployed may be filled with solvent after the molten salt has been removed.

At block 725, the electrodes may be exposed to an electrical potential. In some embodiments, the potential provided while the electrodes are disposed in the solvent may be reversed relative to the potential provided at block 710. In some embodiments, for example, the potential may vary in voltage and/or frequency depending on the solvent composition and/or the type of fission product. For example, the electrical potential may be between an electrode and a third electrode disposed elsewhere in the solvent. The electrical potential between the electrode and the third electrode may produce an electrochemical reaction between fission products plated on the electrode to cause the fission products to dissolve in the solvent.

At block 730, the electrode may be removed from the solvent.

Process 700 may be repeated any number of times. Process 700 may also include additional blocks or steps. Additionally or alternatively, any number of blocks of process 700 may be removed or deleted.

In some embodiments, the electrodes may remain stationary within the chemical separation subsystem. The molten salt and solvent may alternately flow into the chemical separation subsystem because the electrical potential on the electrodes is correspondingly reversed to collect fissile material from the molten salt and dissolve the fissile material in the solvent.

In some embodiments, more than one electrode may be used. In some embodiments, a power supply may be included that is configured to place an electrical potential on the electrodes. The electrical potential may produce an electrochemical reaction between the electrode and fission products within the molten salt or between the electrode and the solvent. In some embodiments, the fission products plate on the electrodes when the electrodes are placed or immersed within the molten salt container.

In some embodiments, the molten salt comprises an actinide-containing salt, and wherein the electrode comprises a material that does not react with actinides within the actinide-containing salt. In some embodiments, the molten salt comprises a fluoride salt or a chloride salt. In some embodiments, the electrode comprises an actinide.

In some embodiments, the chemical separation mechanism may further comprise a chemical separation chamber, wherein at least a portion of the electrode mechanism is disposed within the chemical separation chamber.

In some embodiments, the chemical separation chamber comprises a noble gas.

In some embodiments, the mesh is used to collect the deposited particles within the solvent container.

In some embodiments, the secondary chamber may be used to perform chemical cleaning of the salt.

Unless otherwise indicated, the term "substantially" means within 5% or 10% of the value referred to or within manufacturing tolerances. Unless otherwise specified, the term "about" means within 5% or 10% of the value referred to or within manufacturing tolerances.

Numerous specific details are set forth herein to provide a thorough understanding of claimed subject matter. However, it will be understood by those skilled in the art that claimed subject matter may be practiced without these specific details. In other instances, methods, devices, or systems that would be known by one of ordinary skill have not been described in detail so as not to obscure claimed subject matter.

The one or more systems discussed herein are not limited to any particular hardware architecture or configuration.

The use of "adapted to" or "configured to" herein is meant to not exclude open and inclusive languages of a device adapted to or configured to perform additional tasks or steps. Additionally, the use of "based on" is meant to be open and inclusive in that: a process, step, calculation, or other action that is "based on" one or more stated conditions or values may actually be based on additional conditions or values beyond those stated. Headings, lists, and numbers are included herein for ease of explanation only and are not meant to be limiting.

While the present subject matter has been described in detail with respect to specific embodiments thereof, it will be appreciated that those skilled in the art, upon attaining an understanding of the foregoing may readily produce alterations to, variations of, and equivalents to such embodiments. Accordingly, it is to be understood that the present disclosure has been presented for purposes of illustration and not limitation, and does not preclude inclusion of such modifications, variations and/or additions to the present subject matter as would be readily apparent to one of ordinary skill in the art.