SEPARATION OF FISSION PRODUCTS IN A MOLTEN SALT REACTOR VIA ADSORBENT FRAMEWORKS
20250111957 ยท 2025-04-03
Inventors
- Kim Pamplin (Abilene, TX, US)
- Diego Zometa (Abilene, TX, US)
- Victoriano Cooper (Abilene, TX, US)
- Thomas Hamilton (Abilene, TX, US)
Cpc classification
International classification
Abstract
An extraction system includes an absorbent framework configured to withstand the harsh environment of a molten salt reactor system and capture fission products found in the molten salt of such systems. The extraction system further includes means for removing the absorbent framework from the flow of molten salt, such that the absorbent framework may be processed to harvest the fission products. The absorbent framework may include a temperature resistant cartridge configured to house an absorbent composition. The present invention contemplates multiple absorbent compositions including metal-organic frameworks with unique structures to provide thermal stability, carbon nanotubes, and absorbent microspheres. The metal-organic frameworks may be synthesized by a variety of techniques to impart particular characteristics advantageous for use in a molten salt reactor system.
Claims
1. A system comprising: a molten salt reactor system comprising a molten salt, a reactor core, and an extraction system; the extraction system coupled to the molten salt reactor system and configured to receive a flow of molten salt comprising fission products produced in the reactor core; an absorbent framework extending from the extraction system into the molten salt by an attachment rod; wherein the attachment rod is configured to facilitate removal of the absorbent framework from the molten salt; and wherein the absorbent framework comprises a temperature resistant cartridge configured to house an absorbent composition and enable flow of the molten salt therethrough; wherein the absorbent composition is configured to capture fission products from the molten salt by binding to the fission products via intermolecular force interaction between the absorbent composition and the fission products.
2. The system of claim 1, wherein the absorbent composition is a metal-organic framework.
3. The system of claim 2, wherein the intermolecular forces comprise one or more force interactions between the metal-organic framework and the fission products comprising ion-ion interaction, Van der Waals forces, dipole-dipole forces, ion-dipole interactions, and/or hydrogen bonding.
4. The system of claim 1, wherein the absorbent composition comprises carbon-nanotubes comprising binding sites with an affinity to fission products.
5. The system of claim 1, wherein the absorbent composition comprises microspheres formed or coated with a material having an affinity to fission products.
6. The system of claim 2, wherein the metal-organic framework compound is a porous structure with a plurality of pores of a size to allow the fission products to penetrate the metal-organic framework compound; and wherein the metal-organic framework compound is configured to have an affinity to the fission products by having an electrostatic charge opposite to that of the fission products.
7. The system of claim 2, wherein the metal-organic framework is temperature and corrosion resistant.
8. The system of claim 2, wherein the metal-organic framework compound comprises UiO-66, ZIF-4, or ZIF-8.
9. The system of claim 8, wherein the metal-organic framework is UiO-66 configured to be resistant to temperatures of at least 600 C.
10. The system of claim 8, wherein the UiO-66 has a crystal structure and is synthesized using thermal solvolysis.
11. The system of claim 8, wherein the UiO-66 has an amorphous glass structure and is synthesized using vapor diffusion.
12. The system of claim 9, wherein the UiO-66 has an amorphous powder structure and is synthesized using sonication.
13. The system of claim 2, wherein the metal-organic framework is bound to a temperature resistant substrate via sonication.
14. The system of claim 13, wherein the temperature resistant substrate is selected from a group consisting of a metal mesh wire frame, graphene, copper wire, nickel sponge, and graphite.
15. The system of claim 1, wherein the molten salt is LiFBeF.sub.2UF.sub.4 and the fission products comprise molybdenum-99.
16. The system of claim 1, wherein the extraction system is a bypass coupled to a molten salt loop including a bypass valve operable to selectively facilitate flow of the molten salt to the extraction system.
17. The system of claim 16, wherein the molten salt loop is configured to facilitate circulation of the molten salt comprising fissile material through the reactor core of the molten salt reactor system; and wherein the reactor core is operable to facilitate fission reaction of the fissile material thereby producing fission products within the molten salt.
18. An extraction system comprising: a pipe coupled to a molten salt loop of a molten salt reactor system; the pipe housing an attachment rod coupled to a cartridge and configured to submerge the cartridge into a flow of molten salt of the molten salt loop; and the cartridge configured to house an absorbent composition operable to capture fission products from the flow of molten salt.
19. The extraction system of claim 18, wherein the cartridge includes an outer wall and an inner wall with a mesh structure therebetween configured to enable the flow of molten salt to pass through the mesh structure and contact the absorbent composition.
20. The extraction system of claim 19, wherein the mesh structure defines an inner opening to reduce impedance on the flow of molten salt.
21. The extraction system of claim 18, wherein the pipe comprises a lower assembly having an in-line portion configured to receive the flow of molten salt, and a lower assembly pipe portion extending traverse from the in-line portion and defining a lower channel therethrough; an upper assembly fluidically coupled with the lower assembly and having an upper assembly pipe portion defining an upper channel therethrough and cooperating with the lower channel to define an attachment rod channel of the pipe; the attachment rod disposed fully within the attachment rod channel; the cartridge attached to a lower portion of the attachment rod; and an actuation mechanism operatively coupled to the attachment rod and configured to move the attachment rod axially within the attachment rod channel and configured to move the cartridge into and out of the flow of molten salt.
22. The extraction system of claim 18, wherein the attachment rod includes a stop feature proximal to the lower portion of the attachment rod; the stop feature configured to define a maximum extent to which the absorbent framework in the flow of molten salt.
23. The system of claim 18, wherein the absorbent composition comprises a metal-organic framework; wherein the metal-organic framework compound is a porous structure with a plurality of pores of a size to allow the fission products to penetrate the metal-organic framework compound; and wherein the absorbent composition is configured to capture fission products from the molten salt by binding to the fission products via intermolecular force interaction between the absorbent composition and the fission products; wherein the intermolecular force interactions comprises ion-ion interaction, Van der Waals forces, dipole-dipole forces, ion-dipole interactions, and/or hydrogen bonding.
24. The system of claim 18, wherein the absorbent composition comprises carbon-nanotubes comprising binding sites with an affinity to fission products.
25. The system of claim 18, wherein the absorbent composition comprises microspheres formed or coated with a material having an affinity to fission products.
26. The system of claim 23, wherein the metal-organic framework is resistant to temperatures of at least 600 C. and corrosion resistant.
27. The system of claim 23, wherein the metal-organic framework is UiO-66 with a crystal structure synthesized by thermal solvolysis; UiO-66 with an amorphous glass structure synthesized by vapor diffusion; or UiO-66 with an amorphous powder structure synthesized by sonication.
28. A method for synthesizing a temperature resistant metal-organic framework comprising: preparing a first solution by combining an organic ligand source and a metal source; conducting a synthesis technique on the first solution selected from a group comprising thermal solvolysis, sonication, and vapor diffusion; vacuum filtering the mixture; and drying the mixture to produce a precipitate comprising the temperature resistant metal-organic framework.
29. The method of claim 28, wherein the organic ligand source comprises a solution of 2-aminoterephthalic acid and dimethylformamide; and wherein the metal source comprises zinc nitrate.
30. The method of claim 29, wherein thermal solvolysis comprises heating the mixture within an autoclave at a first temperature for a first length of time and subsequently heating the mixture at a second temperature for a second length of time; and cooling the mixture.
31. The method of claim 30, wherein the second length of time is at least twice the first length of time and wherein the first temperature is less than the second temperature.
32. The method of claim 31, wherein the temperature resistant metal-organic framework is UiO-66; and the UiO-66 is a crystal structure operable to withstand temperatures up to 600 C.
33. The method of claim 29, wherein vapor diffusion comprises placing the mixture in an uncovered vessel and placing the mixture in a larger vessel; adding triethylamine to the larger vessel; and allowing the uncovered vessel to rest undisturbed for a length of time.
34. The method of claim 33, wherein the temperature resistant metal-organic framework is UiO-66; and wherein the UiO-66 is an amorphous glass structure operable to withstand temperatures up to 600 C.
35. The method of claim 29, further comprising adhering the temperature resistant metal-organic framework to a temperature resistant substrate via sonication of the mixture with the temperature resistant substrate.
Description
BRIEF DESCRIPTION OF THE DRAWINGS
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DETAILED DESCRIPTION
[0075] The description that follows includes sample systems, methods, and apparatuses that embody various elements of the present disclosure. However, it should be understood that the described disclosure may be practiced in a variety of forms in addition to those described herein.
[0076] The following disclosure relates generally to molten salt reactor systems, such as those that produce fission products, and systems and methods for removing such fission products out of the molten salt reactor system. A molten salt reactor system may broadly include a collection of components configured to circulate a molten fuel salt along a fuel salt loop. For example, a molten salt reactor system may operate by circulating a molten fuel salt between a reactor vessel (within which fission occurs) and a heat exchanger (for the removal of heat from the fuel salt). However, in some examples, the molten salt reactor is a pool-type reactor with the molten salt disposed within a main reactor vessel, including other components such as the reactor core.
[0077] Fissile nuclides, e.g., uranium-235, uranium-233, and plutonium-239, in the molten fuel salt undergo fission in the reactor vessel of a molten salt reactor to yield fission products, some of which may subsequently decay or otherwise be used to yield useful radionuclides. Non-limiting examples of radioactive elements that may be produced in a molten salt reactor include molybdenum-99, actinium-225, iodine-131, xenon-133, hydrogen-3, nitrogen-13, carbon-14, oxygen-15, fluorine-18, gallium-67, gallium-68, selenium-75, krypton-81m, strontium-89, yttrium-90, technetium-99m, indium-111, iodine-123, iodine-125, samarium-153, erbium-169, and radium-223, which are thereafter present in the irradiated molten fuel salt. The molten salt loop (or the main reactor vessel) carries the irradiated molten fuel salt from the reactor vessel to the heat exchanger, and the fuel salt loop may include one or more other components, such as, but not limited to, a reactor access vessel, a fuel pump, and a drain tank. The amount of fission products in the molten fuel salt increases over time, and as such, it may be necessary to remove one or more of the fission products from the molten fuel salt to decrease the amount of fission products in the molten fuel salt. Additionally, at least some of the fission products, once removed from the molten salt reactor system, may be used in various applications.
[0078] Conventional liquid-fueled molten salt reactors allow for the buildup of fission products in the molten fuel salt until the molten fuel salt is removed from the molten salt reactor system. The buildup of fission products in the molten fuel salt can inhibit the fission rate of the molten fuel salt through processes such as neutron capture, necessitating an earlier removal of the molten fuel salt and hindering the efficiency of the conventional molten salt reactor system.
[0079] To mitigate these and other challenges, the molten salt reactor system of the present disclosure includes an online extraction system to extract the fission products from the molten fuel salt in the molten salt reactor system, such that any fission product buildup issues are lessened or eliminated. The various extraction systems disclosed herein may utilize a variety of absorbent and adsorbent compositions housed within a temperature resistant cartridge (often collectively referred to as an absorbent framework or simply framework) to capture fission product atoms and molecules dissolved, suspended, or otherwise present in the molten fuel salt. As described herein, the various absorbent compositions may also have adsorbent properties, such that they are operable to absorb fission products, adsorb fission products, and/or both adsorb and absorb fission products. For clarity, this functionality is contemplated even if, for conciseness, only absorption is specifically described. The absorbent compositions may include metal-organic frameworks, such as UiO-66, ZIF-4, or ZIF8. The absorbent compositions may also include carbon nanotubes or absorbent microspheres. Further, the absorbent frameworks may include a cartridge configured to house the absorbent composition in a manner to allow the molten fuel salt to flow through the cartridge and consequently the absorbent composition, which capture the fission products from the molten fuel salt. Further, the extraction system may include one or more mechanisms for facilitating inclusion of the absorbent framework into the molten salt and remove of the absorbent framework from the molten salt, thereby enabling fission product removal. Following extraction, the fission products may be separated and collected from the absorbent composition utilizing known methods. Thus, the extraction system both lessens the burden fission products have on the molten salt reactor system and provide for the collection of valuable fission products (e.g., molybdenum-99).
[0080] Additionally, the example extraction system may also include one or more pipes off of the main molten salt reactor loop (i.e., the reactor-reactor access vessel-reactor pump-heat exchanger-reactor vessel loop) or bypasses. A valve may selectively control flow of molten salt to the extraction system, and, if multiple pipes in the extraction system, additional valves may be utilized to control flow through each individual pipe. Also, where the extraction system has more than one pipe, the multiple pipes may run in parallel to one another. Further, as shown in
[0081] In many embodiments, the absorbent material may be metal-organic frameworks (sometimes abbreviated as MOFs) configured to capture the fission products. Metal-organic frameworks are an organic-inorganic porous extended structures that have sub-units arranged in a pattern, and may be one-dimensional, two-dimensional, or three-dimensional. Metal-organic frameworks include pores that can hold fission products, and certain metal-organic frameworks can be synthesized so that they have an affinity for certain fission products and include binding sites so the fission product binds to the metal-organic frameworks. For example, in one embodiment, a certain metal-organic framework structure may have an affinity for molybdenum-99 (Mo-99), such that the Mo-99 atoms may be captured in the pores of the metal-organic framework, which removes Mo-99 from the molten salt. If desired, various other strategies may be used to increase the capture efficiency of the Mo-99 from the molten salt. For example, the metal-organic framework structure may be impregnated with a chemical species that preferentially binds to Mo-99, such that the chemical species resides within the pores of the metal-organic framework. Alternatively, the surface of the metal-organic framework may be decorated with a chemical species that preferentially bind with molybdenum, such that the rate of Mo-99 capture at the surface of the metal-organic framework structure is enhanced. Additionally, the metal-organic frameworks may be synthesized utilizing rational selection of appropriate synthesis conditions with nodes and linkers, it is possible to produce MOFs of desired surface area, pore size, functionality, and topology. Of course, the present invention contemplates combinations of these strategies as well.
[0082] Notably, while metal-organic frameworks may be well known and understood by those of ordinary skill in the art, known metal-organic frameworks may not be fit for inclusion in a molten salt reactor system. More specifically, in order for a metal-organic framework (or any absorbent material) to be capable of capturing fission products from a flow of molten salt of a molten salt reactor system, it must be able to withstand high temperatures (e.g., about 600 C.), be corrosion resistant to survive attacks from fluorine anions, and have an affinity for a particular radioisotope. Such desired characteristics may be accomplished by synthesizing known metal-organic frameworks with novel techniques to produce unique structures granting such desired characteristics. For example, a metal-organic framework may be synthesized utilizing thermal solvolysis under time and temperature conditions to produce a crystal structure with increased temperature resistant properties.
[0083] In certain non-limiting embodiments, the metal-organic frameworks contemplated by the invention may be doped with either sulfur or tungsten in order to enhance capture of the Mo-99. When the dopant is sulfur, for example, the sulfur may be present at a concentration of about 5%, about 10%, about 15%, about 20% or even about 25%, with the understanding that pairs of these percentage values can be used as endpoints that define a range that is expressly contemplated by the invention. In certain embodiments, one atom of sulfur is present per unit cell of the metal-organic framework. Generally, the sulfur may be introduced into the metal-organic framework using a precursor compound that contains sulfur, provided that the precursor compounds have sufficiently small molecular sizes to be able to penetrate the pore structure of the metal-organic frameworks. For instance, in certain embodiments, the sulfur precursor compound may be an alkyl thiol, sulfide, disulfide, thioester, or sulfoxide. In other embodiments, the sulfur precursor compound may be a sulfur-containing amino acid, such as 1-cysteine. Of course, combinations of such sulfur precursors are also expressly contemplated by the invention. It should be noted, however, that in certain embodiments, it is advantageous to use sulfur precursor compounds that do not include oxygen atoms or only one oxygen atom at most, in order to minimize the undesirable generation of oxygen in the molten salt. For this reason, in certain embodiments, sulfites and sulfates are not used as sulfur precursor compounds.
[0084] In addition to or instead of sulfur, the metal-organic frameworks may be doped with tungsten. In certain preferred embodiments, the tungsten is present as nanoparticles of metallic tungsten that are introduced into the metal-organic framework using a liquid phase infusion process. Tungsten nanoparticles may be commercially obtained from Cospheric LLC in Goleta, CA. Alternatively, the tungsten may be introduced into the pores of a metal-organic framework by dissolving a tungsten salt into an aqueous medium and then contacting the metal-organic framework with the aqueous medium. Non-limiting examples of soluble tungsten salts contemplated by the invention include tungsten (II) chloride and sodium tungstate. In other embodiments, the tungsten may be evaporated onto the surface of the metal-organic framework using techniques such as e-beam evaporation, thermal evaporation, sputter deposition, and the like.
[0085] For other radioactive isotopes of interest, the same or analogous doping strategies may be used to enhance capture of the radioactive isotopes by the metal-organic frameworks. For example, the capture efficiency of gallium-67 may be enhanced by using sulfur-doped metal-organic frameworks as discussed herein. However, this invention also expressly contemplates using other types of dopants analogously to enhance capture other radioactive isotopes.
[0086] Useful metal-organic frameworks (MOFs) contemplated by the invention include UiO-66 and zeolitic imidazolate frameworks (ZIFs), which are a class of metal-organic frameworks that are topologically isomorphic with zeolites. Currently, there are over 100 ZIF compounds reported in the literature. In general, suitable metal-organic frameworks include those that (1) have a pore size that permits capture of the Mo or other radioactive isotope of interest in the molten salt reactor; and (2) can withstand the high temperature, reactive conditions found in a molten salt reactor. For example, some of the Mo-99 produced in a molten salt reactor system may exists as molybdenum hexafluoride. Thus, in certain preferred embodiments, the MOFs have pore sizes that permit MoF.sub.6 to diffuse into the metal-organic framework. Useful MOFs of the invention include those that have a melting point of at least 650 C., 700 C., 750 C. or 800 C. Particularly useful ZIF compounds include ZIF-4 and ZIF-8.
[0087] The metal-organic frameworks utilized in a molten salt reactor system may include certain additional properties, such as being heat resistant (up to 800 degrees Celsius) and corrosion resistant. Further, the metal-organic frameworks may be built or added on top of another metal (e.g., stainless steel), to provide structure in the molten salt reactor system. For instance, the metal-organic frameworks may be sintered onto a high-surface-area metal support that is subsequently immersed into the molten salt to capture Mo-99 or another radioactive isotope of interest in the molten salt. In other embodiments, the metal-organic frameworks may be packed into a cartridge so that the metal-organic frameworks are prevented from passing through the cartridge but the molten fuel salt can flow through the cartridge to facilitate fission product capture. When the metal-organic frameworks are ZIFs, the Mo-99 or other radioactive isotope of interest may be recovered from the ZIFs by dissolving the ZIFs under acidic or alkaline conditions.
[0088] The absorbent compositions of the present invention may also include carbon nanotubes configured to capture fission products. Certain carbon nanotube structures may include large pores that can hold fission products, and certain carbon nanotubes may have, or can be made to have, an affinity for certain fission products and include binding sites so the fission product binds to the carbon nanotube structure. For example, in one embodiment, a certain carbon nanotube structure containing tungsten or sulfur at the binding site may have an affinity for Mo-99, such that the Mo-99 atoms may bind to the binding site in the pore of the carbon nanotube structure, which removes Mo-99 from the molten salt.
[0089] The absorbent composition of the present invention may also include microspheres formed or coated with materials having an affinity to fission products. For example, the various MOF compositions described herein may be grown onto or otherwise adhered to a surface of the microspheres. The microsphere structures may be one or more microspheres clustered together within a single porous structure configured to enable the microspheres to contact the molten salt while preventing them from escaping the porous structure. In this example, fission products may adsorb or absorb onto the microspheres via chemical interaction with the MOF composition. In some embodiments, the microspheres are made with a material that has an affinity for certain fission products, or may be coated with a second material that has an affinity for certain fission products. The fission products adsorb onto the microsphere structure surface. For example, in one embodiment, a certain microsphere structure may be made of a material that facilitates Mo-99 adsorption, such that the Mo-99 atoms may adsorb onto the surface of the microsphere structure, which removes Mo-99 from the molten salt. As another example, in one embodiment, a cluster of microspheres may have MOFs with an affinity to Mo-99 grown or otherwise adhered to the surface of the microspheres, such that the Mo-99 atoms may adsorb onto the surface of the microsphere structure, which removes Mo-99 from the molten salt.
[0090] Turning to the drawings, for purposes of illustration,
[0091] In various embodiments, a molten salt reactor system 100 utilizes fuel salt enriched with uranium (e.g., high-assay low-enriched uranium) to create thermal power via nuclear fission reactions. In at least one embodiment, the composition of the fuel salt may be LiFBeF.sub.2UF.sub.4, though other compositions of fuel salts may be utilized as fuel salts within the reactor system 100 (e.g., LiFBeF.sub.2UF.sub.4). The fuel salt within the system 100 is heated to high temperatures (about 600-700 C.) and melts as the system 100 is heated. In several embodiments, the molten salt reactor system 100 includes a reactor vessel 102 including a reactor core where the nuclear fission reactions occur within the molten fuel salt, a fuel salt pump 104 that pumps the molten fuel salt to a heat exchanger 106, such that the molten fuel salt re-enters the reactor vessel 102 after flowing through the heat exchanger 106, and piping in between each component. The molten salt reactor system 100 may also include additional components, such as, but not limited to, a drain tank 108, a reactor access vessel 110, an inert gas system 113, and an equalization system 120. The drain tank 108 may be configured to store the fuel salt once the fuel salt is in the reactor system 100 but in a subcritical state, and also acts as storage for the fuel salt if power is lost in the system 100. The reactor access vessel 110 may be configured to allow for introduction of small pellets of uranium fluoride (UF.sub.4) and/or beryllium (Be) to the system 100 as necessary to bring the reactor to a critical state, compensate for depletion of fissile material, and/or manage fuel salt chemistry.
[0092] In several examples, the molten salt reactor system 100 may include an inert gas system 113 to provide inert gas to a head space of the drain tank 108, among other functions. The inert gas system 113 may further relieve inert gas from the head space of the drain tank 108 as needed. The inert gas system 113 is therefore operable to maintain pressurized inert gas in the head space of the drain tank 108 that is sufficient to substantially prevent the flow of molten fuel salt into the drain tank during normal operations. For example, with the head space of the drain tank 108 pressurized by the inert gas system 113, molten salt may generally circulate between the reactor vessel 102 and the heat exchanger 106 without substantially draining into the drain tank 108. As described herein, the inert gas system 113 may be configured to supply inert gas to the head space of various other components of the molten salt reactor system 100, such as to the head space of the reactor access vessel 110, to the seal of reactor pump 104, among other components. Upon the occurrence of a shutdown event, the inert gas system 113 may cease providing inert gas to the head space of the drain tank 108, and other components to which the system 113 supplies inert gas.
[0093] The molten salt reactor system 100 may further include an equalization system 120 that is operable to equalize the pressure between the head space of the drain tank 108 and the reactor vessel 102 upon the occurrence of a shutdown event. For example, during normal operation a pressure differential exists between the head space of the drain tank 108 and the reactor vessel 102. Such pressure differential prevents or impedes the draining of the fuel salt into the drain tank 108. In this regard, the equalization system 120 may be operable to fluidically couple (via opening one or more valves) the head space of the drain tank 108 and the reactor vessel 102 to reduce or eliminate the pressure differential, thereby allowing the fuel salt to readily flow into the drain tank upon the shutdown event. The equalization system 120 may include numerous redundances and/or bypasses in order to facilitate a fail-safe or walk-away safe operation with respect to depressurization of the system 100.
[0094] Additionally, the system 100 may include an extraction system 112 and a filtration valve 114 that extend off of the main loop (i.e., the reactor vessel 102reactor access vessel 110reactor pump 104heat exchanger 106reactor vessel 102 loop) and return to the main loop at a point downstream. In several embodiments, the extraction system 112 is a bypass off the molten salt loop of the molten salt reactor system 100 and is provided selective flow of molten salt comprising fission products by the filtration valve 114. Although
[0095] Turning now to
[0096] In several embodiments, with reference to
[0097] In multiple embodiments, the capture system valve 212a, 212b, 212c, when in the open position, may have an area or volume large enough to pass the absorbent framework 204a, 204b, 204c and attachment rod 206a, 206b, 206c through the capture system valve 212a, 212b, 212c. In some embodiments, the capture system valve 212a, 212b, 212c may be a ball valve or any other type of valve that allows the absorbent framework 204a, 204b, 204c to access the pipe 201. The capture system valve 212a, 212b, 212c cannot close while the absorbent framework 204a, 204b, 204c is in the pipe 201. Once the extraction system 202a, 202b, 202c is removed from the pipe 201, capture system valve 212a, 212b, 212c, and capture system pipe 210a, 210b, 210c, the capture system valve 212a, 212b, 212c is closed to prevent molten fuel salt and fission products 203 from leaving the system 112 via capture system pipe 210.
[0098] In several embodiments, the absorbent framework 204a, 204b, 204c includes a temperature resistant cartridge 205a, 205b, 205c configured to house the absorbent composition 207a, 207b, 207c. The cartridge 205a, 205b, 205c is configured to enable passage of molten salt therethrough, such that the absorbent composition 207a, 2076, 207c may contact fission products 203 and be captured therein. Fission product capture may be facilitated by absorption or adsorption of fission products onto and/or in the absorbent composition 207a, 2076, 207c. In several embodiments, cartridges 205a, 205b, 205c are temperature and corrosion resistant. For example, cartridges 205a, 205b, 205c may be able to withstand temperatures of about 700 C. and may be able to withstand attack from fluorine ions. I several embodiments, cartridges 205a, 205b, 205c are configured to withstand temperatures between 550 C. and 750 C. However, one of ordinary skill in the art will appreciate that, depending on the material selected, the cartridges 205a, 205b, 205c may be configured to resist temperatures greater than 750 C. The absorbent composition may be a metal-organic framework, carbon nanotube, absorbent microsphere, or any combination thereof. The temperature resistant cartridge and the absorbent composition may be collectively referred to as the absorbent framework 204. In some embodiments, the temperature resistant cartridge is primarily made of the absorbent composition (see
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[0101] Turning now to
[0102] The present invention may include a rod-driven extraction system to facilitate extraction of fission products. The rod-driven extraction system may be attached to the absorbent framework and facilitate its submersion into the flow of molten salt. For clarity, the rod-driven extraction system may be referred to as a coupon sampler. Such a rod-driven extraction system may be that of the systems, apparatuses, and methods described in U.S. Nonprovisional patent application Ser. No. 18/778,349, which is hereby incorporated by reference in its entirety.
[0103] For example, the rod-driven extraction system may be integrated with a run of pipe or segment between one or more of the reactor vessels 102, the reactor access vessel 110, the pump 104, the heat exchanger 106, and/or the drain tank 108. Additionally or alternatively, the rod-driven extraction system may be integrated with a side run or by-pass pipe along the pipe of the main loop in order facilitate removal. In several embodiments, the rod-driven extraction system is extraction system 112 of
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[0105] The rod-driven extraction system 410 is shown in
[0106] To facilitate the foregoing, the rod-driven extraction system 410 may be operatively coupled with or include or otherwise be associated with the actuation mechanism 404. The actuation mechanism 404 may include a variety of components that are used to move, such as raising or lowering, the attachment rod 420 within the rod-driven extraction system 410. The actuation mechanism 404 may be configured to actuate the attachment rod 420 via an operative connection 405 using one or more of a magnetic coupling, a robotic coupler, a cable, a pressure differential and/or other mechanism, including hand operation. For example, the actuation mechanism 404 may include one or more magnetic drives that is configured to magnetically couple with a corresponding magnetic element of the attachment rod 420 such that movement of the magnetic drive of the actuation mechanism 404 causes a corresponding movement of the attachment rod 420 within the rod-driven extraction system 410. In another example, the actuation mechanism 404 may include one or more robotic grabbers, such as one or more articulable linkages or other mechanical elements, that are configured to enter the rod-driven extraction system 410 and physically engage a structure of the attachment rod 420. In turn, the robotic grabber may be moved, such as being moved up and down, in order to cause a corresponding movement of the attachment rod 420, and subsequently the absorbent framework, within the rod-driven extraction system 410. In another example, the actuation mechanism 404 may include one or more cables that are configured to enter the rod-driven extraction system 410 and physically engage a structure of the attachment rod 420. In turn, the cable may be moved, such as being moved up and down, in order to cause a corresponding movement of the attachment rod 420 within the rod-driven extraction system 410. In another example, the actuation mechanism 404 may include one or more valves, seals, and insert gas lines that are configured to induce a pressure differential across the attachment rod 420 within the rod-driven extraction system 410. Such pressure differential may be operative to move the attachment rod 420 therein. In other examples, other actuation mechanisms 404 are contemplated herein.
[0107] The rod-driven extraction system 410 may be configured to maintain the attachment rod 420 fully within an inert environment prior to, during, and subsequent to the placement of the attachment rod 420 within the flow of molten salt and consequently the absorbent framework. In this regard, the inert gas system 402 is shown in
[0108] In one implementation, the inert gas system 402 may deliver inert gas directly to the upper assembly 440 of the rod-driven extraction system 410. In other examples, such as that shown in
[0109] In this regard, in the example shown in
[0110] With reference to
[0111] To facilitate the foregoing, the attachment rod 420 may be a monolithic structure of a stainless-steel material. The attachment rod 420 may be formed via machining. Additionally or alternatively, the attachment rod 420 may be formed via segments, in particular for more precision and exotic absorbent framework geometry (See
[0112] In the monolithic structure shown in
[0113] The stop feature 430 is shown in
[0114] The engagement feature 435 may be any appropriate component integrated with the elongated structure 422 for operable coupling of the attachment rod 420 with the actuation mechanism 402, other actuation mechanism. For example, the engagement feature 435, as shown in
[0115] Turning now to
[0116] Turning to
[0117] In many embodiments, the temperature resistant cartridges 600a, 600b, and 700 may be made of materials that are heat resistant and corrosion resistant, such as stainless steel. In some embodiments, the temperature resistant cartridges 600a, 600b, and 700 may be formed from a material having an affinity for at least one of the fission products (such as, but not limited to, stainless steel, Hastelloy N, titanium, or any other materials that can withstand such harsh conditions within the system 100). Additionally, the cartridges 600a, 600b, and 700, and specifically, the respective mesh structures 602, 610, 702 may be designed so that the mesh structures 602, 610, 702 do not interrupt molten fuel salt flow in the system 100 but allow the molten salt to flow therethrough and contact the absorbent composition. The mesh structures 602, 610, 702 may be configured such that the absorbent composition cannot escape through the mesh. Though a circle and rectangular mesh structures are shown in
[0118] In several embodiments, the absorbent framework (e.g., a metal-organic framework) may be built or placed onto the mesh structures 602, 610, 702 so that when certain fission products make contact with the absorbent composition, the certain fission product are captured by the absorbent composition via a variety of mechanism. Fission product capture may be generally facilitate through absorption and/or adsorption. For example, and with reference to
[0119] After a certain period of time, or after other parameters are hit, the absorbent framework 204, 304, 426, (including cartridge 600a, 600b, 700) may be pulled out of the fission product removal system 112, and the absorbent composition may be processed to single out the one or more fission products. Such processing may include washing said absorbent composition with a solvent configured to unbind the fission products from the absorbent composition. Such processing may include known methods for removing fission products from the absorbent framework. Such processes may be followed by known methods for isolating certain fission products from others. For example, the present invention may utilize the system and methods described in U.S. Nonprovisional application Ser. No. 18/771,047 filed Jul. 12, 2024, which is hereby incorporated by reference in its entirety.
[0120] In several embodiments, the absorbent composition is a metal-organic framework (MOF). Turning now to
[0121] However, while UiO-66 may have high thermal stability, certain variables may be needed to increase its thermal stability to allow UiO-66 to survive temperatures of a molten salt reactor system (e.g., MSR system 100 of
[0122] Turning now to
[0123]
[0124] At step 1010, the mixture may then be subject to thermal solvolysis. Thermal solvolysis may be facilitated by placing the mixture into an autoclave, heating the autoclave to a first temperature for a first length of time and subsequently raising the temperature to a second temperature and maintaining that second temperature for a second length of time. For example, the autoclave may be heated to 80 C. for five hours and then the autoclave may be heated to 120 C. and maintained for 72 hours. Additionally, or alternatively, the first temperature may be 60 C. and may be maintained for 96 hours. In several embodiments, the first temperature is less than the second temperature, but the second length of time may be at least twice as long as the first length of time. Stated otherwise, thermal solvolysis may be facilitated by placing the mixture into an autoclave and heating the autoclave to an initial temperature, maintaining that temperature for a time, raising the temperature, and then maintaining the new temperature for an extended period of time. Following thermal solvolysis and at step 1016a, the resulting solution may be allowed to cool to room temperature and is then vacuum filtered. Vacuum filtering may isolate a precipitate containing the MOF from the remaining solution. Following step 1016a, the precipitate may be collected at step 1018a. The resulting precipitate may be an MOF with a crystal structure (See
[0125]
[0126]
[0127] Such MOFs synthesized utilizing the various synthesis schemes of
[0128] Turning now to
[0129] Initially, at step 1104, MOF reagents may be added to a solution. At step 1106 an appropriate solvent, such as DMF may be added to the solution. MOF reagents 1104 may include a zinc source (e.g., zinc nitrate), a zirconium source (e.g., zirconyl chloride), and an organic ligand source (e.g., 2-aminoterephthalic acid or imidazole). Then, a substrate may be oxidized using known methods. The substrate may be any temperature resistant material such as, metal mesh wire frame, copper ribbons, graphene, a nickel sponge, graphite, carbon nanotubes, absorbent microspheres, or any combination thereof. In some embodiments, based on the substrate used, oxidation may not be required. For example, substrates naturally containing oxides, such as nickel sponges, graphite, and/or graphene oxide, may not require oxidation. At step 1102, the oxidized substrate may be included in the solution or vessel along with the MOF reagents and DMF. These constituents may then be subject to sonication at step 1108. Sonication may be facilitated by a bath sonicator or a probe sonicator submerged in the vessel of the solution. Sonication may be performed for a variable amount of time, based on the need. For example, the oxidized substrate, MOF reagents, and DMF may be sonicated for twenty minutes. Following step 1108, the resulting solution may include the substrate coated in a metal-organic framework, such as ZIF-4, ZIF-8, or UiO-66. At step 1110, the coated substrate may then be rinsed, for example with ultra-pure water and acetone. At step 112, the coated substrate may then be dried. Drying may occur by use of an air valve or by simply leaving the coated substrate and vessel uncovered for a period of time. The resulting coated substrate may be washed and subsequently dried repeatedly. Stated otherwise, the rinsing step 1110 and drying step 1112 may occur more than once. Following the drying step 1112, a temperature resistant coated with a MOF is acquired.
[0130] Such coated substrates formed utilizing the method of
[0131] Turning now to
[0132] Turning now to
[0133] In several embodiments, the absorbent composition 207a, 207b, 207c may include the carbon nanotube structures 1506, 1508 within the cartridge 600, 700. Additionally, or alternatively, the cartridge 600, 700 may be primarily made of the carbon nanotube structures 1506, 1508, and may be some mesh shape (see, e.g.,
[0134] The absorbent compositions of the present invention may also include carbon nanotubes configured to capture fission products (e.g., carbon nanotubes 1506, 1508). The carbon nanotubes structures 1506, 1508 may include large pores (e.g., passages 1507, 1509a, 1509b, 1509c) that can hold fission products, and certain carbon nanotubes may have, or can be made to have, an affinity for certain fission products and include binding sites so the fission product binds to the carbon nanotube structure. For example, in one embodiment, the carbon nanotubes structures 1506, 1508 contains tungsten or sulfur at the binding site may have an affinity for Mo-99, such that the Mo-99 atoms may bind to the binding site in the pore of the carbon nanotube structure, which removes Mo-99 from the molten salt.
[0135] In many embodiments, the carbon nanotubes 1506, 1508 may be placed within cartridges 600a, 600b, 700a, 700b and be configured to capture fission products within the flow of molten salt. In several embodiments, the carbon nanotube structures may be built or placed onto the mesh structures 602 and 610, so that when certain fission products pass near the carbon nanotube structures 1506, 1508, the certain fission product is captured within the passages 1507, 1509a, 1509b, 1509c of the carbon nanotube structure 1506, 1508. As stated above, the carbon nanotube structures 1506, 1508 should be resistant to high heats, corrosion resistant, and have any affinity for at least one of the fission products so that the fission product can fit into the pore of the carbon nanotube structure. In some embodiments where the cartridges 600a, 600b, 700a, 700b are formed from the carbon nanotubes 1506, 1508, the absorbent composition may be the various MOFs described herein. Advantageously, these embodiments provide multiple, distinct mechanisms for capturing fission products, that is, through the carbon nanotubes and the MOFs contained therein.
[0136] In many embodiments, the carbon nanotubes 1506, 1508 are the temperature resistant structure used to anchor the various MOFs described herein. Stated otherwise, the oxidized substrate 1102 of
[0137] Turning now to
[0138] In some embodiments, the microspheres 1602 are absorbent microspheres configured to capture fission products from the flow of molten salt. The absorbent microspheres may be made with a material that has an affinity for certain fission products, or may be coated with a material that has an affinity for certain fission products. For example, in one embodiment, a certain microsphere structure may be made of a material that facilitates Mo-99 adsorption, such that the Mo-99 atoms may adsorb onto the surface of the microsphere structure, which removes Mo-99 from the molten salt.
[0139] The absorbent compositions of the present invention may also include absorbent microspheres configured to capture fission products (e.g., microspheres 1602). The microspheres 1602 may have, or can be made to have, an affinity for certain fission products and include binding sites on the surface of the microspheres 1602.
[0140] In many embodiments, the cluster of microspheres 1600 may be placed within cartridges 600a, 600b, 700a, 700b and be configured to capture fission products within the flow of molten salt. In several embodiments, the microspheres 1602 may be built or placed onto the mesh structures 602 and 610, so that when certain fission products pass near the microsphere cluster 1600, the certain fission products are captured by the binding sights of the microspheres 1602. As stated above, the microspheres 1600 should be resistant to high heats, corrosion resistant, and have any affinity for at least one of the fission products so that the fission product can bind to the microspheres 1602. In some embodiments where the cartridges 600a, 600b, 700a, 700b are coated with or partially formed from the microspheres 1602, the absorbent composition may be the various MOFs described herein. Advantageously, these embodiments provide multiple, distinct mechanisms for capturing fission products, that is, through the absorbent microspheres and the MOFs contained therein.
[0141] In some embodiments, the absorbent composition includes a metal-organic framework and hierarchical nanoporous carbon structure inside metallic foams, referred to as a composite absorbent composition. Such a structure is configured to capture fission products from the flow of molten salt. In these embodiments, the absorbent composition is a composite between a metallic foam and a reticular nanoporous framework. The composite absorbent composition combines a metallic foam (e.g., nickel foam) with various MOFs described herein. For example, the composite absorbent composition may combine metallic foam with ZIF-4 and/or UiO-66. While the various examples that follow describe a nickel foam, one of ordinary skill in the art will appreciate that any type of metallic foam may be used, such as aluminium, copper, steel, Inconel, tin, gold, silver, and others known in the art. The nickel foam forms the substrate to which the MOFs adhere or are grown onto. Advantageously, this composite absorbent composition may be operable to be temperature and corrosion resistant to withstand the environment of an MSR. Furthermore, this composite absorbent composition may be operable to capture certain fission products from the flow of molten salt. For example, Mo-99, I-131, and Sr-89.
[0142] Turning now to
[0143] The resulting composite absorbent composition may be capable of absorbing, and subsequently extracting using the various extraction systems described herein, a variety of fission products. The particular fission products captured may depend on the type of MOF grown or adhered to the nickel foam. Additionally or alternatively, the composite absorbent composition may be synthesized utilizing the synthesis techniques described in reference to
[0144] The present invention further contemplates a method for filtering fission products with an example fission product removal system on an example molten salt reactor, according to one embodiment of the present disclosure. At the start of this example method, a nuclear reactor, such as molten salt reactor system 100, is needed so that the fission products can be produced.
[0145] In several embodiments, metal ion fission products are created in the molten salt reactor through fission reaction of fissile material (e.g., UF.sub.4). As described herein, the fission of the uranium atoms in the molten salt results in various fission products that stay in the molten fuel salt and circulate through the molten salt reactor system.
[0146] In many embodiments, one or more fission products capture system (e.g., capture system 202) may be inserted into the fission product removal system 204. The one or more absorbent frameworks 204 may be extended though the capture system pipe 210 and into the pipe 201.
[0147] In some embodiments, filtration valve 114 is opened so that molten salt 203 may flow into and through the fission product removal system 112 to capture the fission products.
[0148] In several embodiments, the suspended fission products within the molten fuel salt may be captured within the pores of the metal-organic frameworks within the one or more absorbent frameworks 204.
[0149] In one or more embodiments, molten fuel salt flow is halted in the fission product removal system 112 by closing the filtration valve 114.
[0150] In some embodiments, the one or more absorbent frameworks 204 containing the captured fission products are removed from the fission product removal system 112 by pulling the attachment rod 206 up through the capture system pipe 210 so that the one or more cartridges 204 are pulled out of the pipe 201 and through the capture system valve 212. Additionally, each of the one or more capture system valves 212 are closed once the one or more cartridges are removed from the fission product removal system 112.
[0151] Though Mo-99 is generally used as an example fission product within the disclosure, the systems and methods as described herein may be utilized to extract and process any fission product created in a molten salt reactor system. The table below shows a non-exhaustive list of potential fission products that may be extracted and processed using the disclosed systems and methods:
TABLE-US-00001 Isotope Medical Applications Radiation Half-life Hydrogen-3 Many Beta 12.32 years Nitrogen-13 Myocardial blood flow PET 9.965 imaging minutes Carbon-14 studying abnormalities Beta/Gamma 5700 years that underline diabetes, gout, anemia and acromegaly; insufflation gas for procedures like endoscopies; and more Oxygen-15 Blood flow imaging PET 122.24 seconds Fluorine-18 Used to diagnose cancer, PET (positron) 109.77 heart disease, and minutes epilepsy Gallium-67 Imaging of tumors and Gamma 3.2617 days infections Gallium-68 Imaging of tumors and Positron 68 minutes infections Selenium-75 Many Gamma 119.78 days Krypton-81m Pulmonary imaging Gamma 13.1 seconds Strontium-89 Bone metastases Beta 50.563 days Yttrium-90 Treatment of arthritis Beta 64.053 hours Technetium-99m Many Gamma 6.0067 hours Molybdenum-99 Multiple Beta 65.976 hours Indium-111 Many Gamma 2.8047 days Iodine-123 Many Gamma 13.22 hours Iodine-125 Clot imaging Gamma 59.5 days Iodine-131 Many Beta/Gamma 8.025 days Xenon-133 Many Gamma 2.198 days Samarium-153 Bone metastases Beta/Gamma 46.284 hours Erbium-169 Treatment of arthritis Beta 9.392 days Radium-223 Bond cancer therapy Alpha 11.43 days
EXAMPLES
Example 1: Synthesis of MOFs
[0152] In general, this invention contemplates the use of metal-organic frameworks (MOFs) that are (1) capable of surviving the extreme heat and corrosive environment of a molten salt reactor; and (2) are capable of capturing a radionuclide of interest in the molten salt. This invention recognizes at least four approaches for capturing the desired radionuclide. First, the MOF may have pores that are large enough to allow the desired radionuclide or compound thereof (e.g., molybdenum fluoride) to penetrate the network structure of the MOF and become captured therein. Second, the MOF may be electrostatically charged with an opposite charge of the radionuclide species of interest. For instance, some forms of Mo in FLiNaK/FLiBe (fluorine salts commonly used in molten salt reactors) exist in the molten salt reactor as anionic species, and a cationic MOF present in the molten salt electrostatically attracts and captures such anionic species. Third, the MOF may be functionalized with chemical species that capture the radionuclide of interest. When the radionuclide is Mo, for example, the MOF may be functionalized by incorporating lead, tungsten, oxygen, or sulfur into the framework to capture Mo fluorides or other Mo species present in the molten salt. Fourth, the invention expressly contemplates using a combination or sub-combination of these three approaches.
[0153] The MOFs contemplated by the invention may be made using any method known in the art. For example, MOFs may be formed by using the approach outlined by Rahmidar, L. et al. A facile approach for preparing Zr-BDC and Zr-BDC-NH2 MOFs using solvothermal method J. Phys. Conf. Ser. 2243, (2022) 012055. Other methods are described by O. Abuzalat et al., Sonochemical fabrication of Cu(II) and Zn(II) metal-organic framework films on metal substrates, Ultrasonics-Sonochemistry 45 (2018) 180-188; M. Tanhaei, et al., Energy efficient sonochemical approach for the preparation of nanohybrid composites from graphene oxide and metal-organic framework, Inorganic Chemistry Communications 102 (2019) 185-191; C. Vaitsis et al., Metal Organic Frameworks (MOFs) and ultrasound: A review, Ultrasonics-Sonochemistry 52 (2019) 106-119; and Wharmby et al., Extreme Flexibility in a Zeolitic Imidazolate Framework: Porous to Dense Phase Transition in Desolvated ZIF-4, Angewandte Chemie. All of these references are incorporated by reference in their entirety, as if they were set forth herein.
[0154] Generally speaking, in the synthesis of ZIF-4 and ZIF-8, zinc nitrate is combined with imidazole (for ZIF-4) and with methyl imidazole (for ZIF-8). The MOF UiO-66 may be synthesized by combining zirconyl chloride with terephthalic acid.
[0155] By way of example, the synthesis of ZIF-4 will now be described. Zinc nitrate and imidazole are reacted under conditions that cause the zinc to form a bridge between neighboring imidazoles, as illustrated schematically in the following:
##STR00001##
In this way, an extended framework can be formed by combining these building blocks. In certain preferred embodiments, the mole ratio between the zinc nitrate and imidazole is at least 1:3. The reaction to form ZIF-4 may be carried out in any suitable solvent, non-limiting examples of which including dimethyl formamide (DMF), water, or a combination of methanol/ethanol. Optionally, a mineralizing agent such as HF or carbonate may be used. The ZIF-4 may be synthesized using either a solvothermal method or a sonication method. In the solvothermal method, an autoclave is used to heat the reagents and solvent under high temperatures for extended periods of time to allow the MOF to form. For example, when the solvent is DMF, the reactants and solvent may be heated in the autoclave for 72 hours at 140 C. Generally, solvothermal synthesis of MOFs can yield amorphous and/or crystalline forms. When the ZIF-4 is made using sonication, the reagents and solvents are put into a sonicator, where the sonic waves causes cavitation in which tiny air bubbles implode. Without wishing to be limited by theory, it is believed that the energy released by cavitation is absorbed by the reactants to drive the chemical reactions that form ZIF-4. In contrast to synthesis using solvothermal methods, where crystalline MOFs may be obtained, synthesis using sonication typically produces amorphous MOFs.
[0156] Either the imidazole groups in the framework of ZIF-4 or the Zn metal that bridges the imidazole groups may be substituted to form other MOFs under similar conditions. For example, to form ZIF-8, the imidazole is replaced by methyl imidazole. For UiO-66, the source of the zirconium bridging metal in the MOF structure is zirconyl chloride and the organic portion of the framework is formed using terephthalic acid.
Example 2: MOF Composites
[0157] This example describes some non-limiting embodiments of the MOF composites that are contemplated by the invention. In general, the MOF composites are formed in order to improve ease of handling of a MOF and to make it more convenient to introduce the MOF into a molten salt reactor.
[0158] For example, the following provides a protocol for the formation of a ZIF-4 MOF composite that has graphene oxide (GO), graphene, graphoil or carbon nanotubes as support.
Protocol (for Graphene Oxide, Graphene, Graphoil, or Carbon Nanotubes);
[0159] Measure enough zinc nitrate and support so that they match a predetermined mass % ratio. e.g., 25% Zn in graphene oxide. Combine to form a mixture. [0160] Sonicate the mixture for 15 mins with dimethylformamide as a solvent. [0161] After rinsing and drying, combine the resulting material with imidazole and sonicate in DMF for 60 minutes. [0162] Rinse and dry the MOF composite.
An exemplary reaction scheme is shown in
[0163] As another example, this invention expressly contemplates metal-MOF composites in which a metal is used as a support. In general, any metal with a sufficiently high melting point (e.g., 700 C.) may be used. The following provides a protocol for synthesizing ZIF-4 on cobalt.
Protocol (for ZIF-4 Grown on Cobalt);
[0164] Oxidize the surface of a cobalt strip with 10 M NaOH and persulfates. Optionally, use SEM to confirm whether nanostrands are present at the surface of the metal. [0165] Combine the metal with a solution of imidazole in DMF and sonicate. Optionally, zinc nitrate may be added to form a cobalt-imidazole-zinc composite. [0166] Rinse and dry the composite.
[0167] Other examples and implementations are within the scope and spirit of the disclosure and appended claims. For example, features implementing functions may also be physically located at various positions, including being distributed such that portions of functions are implemented at different physical locations. The foregoing description, for purposes of explanation, uses specific nomenclature to provide a thorough understanding of the described examples. However, it will be apparent to one skilled in the art that the specific details are not required in order to practice the described examples. Thus, the foregoing descriptions of the specific examples described herein are presented for purposes of illustration and description. They are not targeted to be exhaustive or to limit the examples to the precise forms disclosed. It will be apparent to one of ordinary skill in the art that many modifications and variations are possible in view of the above teachings.