Patent Application
20210057122
The present invention relates generally to the disposing of depleted uranium products and more particularly, the invention relates to (a) the disposal of munitions like depleted uranium penetrators and (b) the disposal of depleted uranium products like depleted uranium oxides and their derivatives.
A portion of the disclosure of this patent application may contain material that is subject to copyright protection. The owner has no objection to the facsimile reproduction by anyone of the patent document or the patent disclosure, as it appears in the Patent and Trademark Office patent file or records, but otherwise reserves all copyrights whatsoever.
Certain marks referenced herein may be common law or registered trademarks of third parties affiliated or unaffiliated with the applicant or the assignee. Use of these marks is by way of example and should not be construed as descriptive or to limit the scope of this invention to material associated only with such marks.
Depleted uranium is formed as a byproduct in many industrial and military processes including; nuclear fuel manufacture operations, military weapons testing, and miscellaneous civilian, industrial, and military operations. For example, five to ten kilograms of depleted uranium are formed for every kilogram of low-enriched uranium that is produced for nuclear fuel systems. Depleted uranium material is a dangerous radioactive material that needs to be safely stored and/or disposed of.
The term depleted uranium penetrators refers to military munitions that may be referred to herein as “DUP.” The term “DUF” refers to the specific products of depleted uranium hexafluoride and/or their derivatives. The term “DUM” is a generic term herein referring to depleted uranium material in forms different from the depleted uranium penetrators (DUPs).
Today (circa 2019) there is a massive quantity of depleted uranium materials and waste products accumulating across the world. In the U.S. alone there are more than 70,000 metric tons (MT) of DUPs being stored in warehouses and in the open on the surface of the earth. Such surface operations are very costly, typically costing hundreds of millions of dollars annually. The DUPs consist of thousands of rounds of munitions which have been removed from operations by the military across the world.
In addition, there is a significant amount of dangerous radioactive uranium hexafluoride UF6 which is a byproduct of the uranium enrichment industry. This DUF is accumulating in rusting steel cylinders across the U.S. and around the world. The current U.S. inventory is in excess of 700,000 MT of the material (NRC data). The world inventory is in excess of 1,200,000 MT. There is a significant need for new mechanisms and processes to safely get rid of (or minimize) the current surface storage operations of this dangerous radioactive waste and to sequester the DUP and/or DUF waste in a safe manner.
Regardless of the management alternatives used to safeguard the DUM at this time there is no clear answer as to the benefits of long-term surface storage or even storage in shallow pits or mined tunnels of the DUM. Currently, the only safe and scientifically valid approach is to remove the DUM from the surface or near surface disposal operations and sequester it in deep geological systems far from the ecosphere.
There are problems associated with prior art and their operations regarding storage and/or disposal of DUP and/or DUF.
In the case of DUP, the current systems and methods for disposal of the DUP on or near the surface pose serious environmental and technical problems which must be successfully addressed. The following issues which have been raised in public hearings and environmental discussions must be analyzed, addressed, and contingencies made to provide for safety to the environment and humankind:
In the case of the DUF there are also numerous problems which have yet to be overcome successfully before disposal of DUF can be considered safe and routine. DUF is very toxic. DUF can be a crystalline solid like rock salt. In storage cylinders the DUF may exist as solid salt at the bottom of the storage cylinder and a DUF gas above the solid phase at less than atmospheric pressure. DUF can react exothermically with air and moisture. To date, the problems to be resolved occur because the DUF is stored in surface or near surface facilities in tanks. The DUF treatment alternatives used today are:
The similarity of DU to transuranic waste has recently been noted in a National Research Council (NRC) report, both regarding their radiological characteristics as well in regard to the difficulties that are associated with their disposal. See Table 1 below:
Table 1 shows that DU cannot (should not) be considered analogous to a naturally occurring uranium ore. DU is more analogous to a transuranic waste and this NRC report states: “If disposal [of depleted uranium oxide] is necessary, it is not likely to be simple. The alpha activity of DU is 200 to 300 nanocuries per gram. Geological disposal is required for transuranic waste with alpha activity above 100 nanocuries per gram.” (US National Research Council report.)
Regardless of the management alternatives used to safeguard the DUM at this time there is no clear answer as to the benefits of long-term surface storage or even storage in shallow pits or mined tunnels for the DUM. The only safe and scientifically valid approach is to remove the DUM from the surface or near surface disposal operations and sequester it in deep geological systems far from the ecosphere.
There is also a public safety and social issue problem, that is, the long-term stewardship of DUPs, DUF, and DUM wastes, including financial liability over a matter of decades or even centuries. Limiting this liability for future generations requires a means of disposal that is intergenerational as well as extremely long-term in its efficacy and reliability.
Based on the inherent shortcomings of the prior art, there exists a critical need for an effective, economical method for developing and utilizing an acceptable nuclear waste process for the depleted uranium nuclear waste products (such as DUPs, DUF, and/or DUM).
To solve the above-described problems, the present invention provides systems and/or methods to dispose of the depleted uranium products (such as DUPs, DUF, and/or DUM) currently accumulating on the earth's surface (and/or near surface) as a result of the activities stated above.
There is a long felt, but currently unmet, need for means, systems, and/or mechanisms that would allow the DU nuclear waste which exists in a variety of physical forms to be packaged and disposed of very deep within the earth's crust and in substantial quantities.
It is a requirement of this invention that the DU waste is sequestered in large enough volumes and at a considerable enough distance below the surface of the earth to maintain the highest level of safety as possible.
A need, therefore, exists for a new method for to safely dispose of DU wastes in a controlled manner and then depositing these wastes in a system that is designed to meet the requirements of public acceptance along with regulatory guidelines.
There is a need in the art for systems and methods that dispose of and/or store depleted uranium products (such as DUPs, DUF, and/or DUM) within deep geological formations significantly below the earth's surface.
The novel and non-obvious approaches as taught in this subject patent application provide systems and methodologies wherein (a) the DUP are disposed of after packaging and/or (b) the DUM disposal operations go either directly to the deep geological systems without conversion or after a conversion cycle the final DUM products are then disposed safely in the deep geological systems.
It is to these ends that the present invention has been developed.
To minimize the limitations in the prior art, and to minimize other limitations that will be apparent upon reading and understanding the present specification, various embodiments of the present invention may describe and define systems and methods for the long-term (over thousands of years) disposal/storage of DUP, DUF, and/or DUM: (a) in wellbores; (b) in well casing; (c) in capsules in well casings; (d) in capsules in well casings in wellbores; (e) in human-made caverns; (f) in capsules in human-made caverns—and wherein all such storage final disposal/storage locations are located within deep geological rock formations.
The present invention is concerned with disposing of nuclear waste and, more specifically, to methods and systems of disposing of depleted uranium products such as DUP, DUF, and/or DUM in deep underground rock formations using: (a) multilateral horizontal boreholes connected to the earth's surface by a vertical wellbore, and/or also, (b) the present invention also relates generally to the containment of hazardous DUP, DUF, and/or DUM wastes disposed within large human-made, subterranean cavities (caverns) in deep geologic formations.
The present invention relates generally to disposing of DUP, DUF, and/or DUM waste and more particularly, to: (a) the operations of DU waste disposal; and/or (b) utilization of lateral wellbores and specialized human-made caverns wherein the DU waste may be sequestered in caverns implemented in deep geologic formations, such that in both cases, the nuclear waste is disposed of safely, efficiently, economically and in addition, if required, may be retrieved for technical or operational reasons.
In some embodiments, this invention may comprise three interrelated and connected systems: (a) a nuclear waste capsule/container; (b) a specially designed wellbore; and/or (c) a deep geological cavern (which may be human made).
Methods of disposing nuclear waste (such as DUP, DUF, and/or DUM) in underground rock formations is disclosed by the present invention. In some embodiments, such a method may comprise a step of selecting an area of land having a rock formation positioned therebelow. The rock formation must be of a depth able to prevent radioactive material placed therein from reaching the surface over geologic times and must be at least a predetermined distance from active water sources for human activity. In some embodiments, such a method may further comprise drilling a vertical wellbore from 5,000 feet to 30,000 feet deep from the earth's surface of the selected area which extends into the given underground rock formation. In some embodiments, a diameter of the vertical wellbore may be between 10 inches and 48 inches.
The selected geologic formations should also be structurally closed and comprise sufficient distinct geologic layers of specific petrophysical properties such that the repository is stratigraphically impermeable to fluid migration out of the zone. This rock property may limit radionuclide migration away from the given underground storage area or zone.
In some embodiments, at least one primary horizontal lateral wellbore of length varying from 500 feet to 20,000 feet, may be drilled out from the (primary) vertical wellbore whereby the surface of the horizontal lateral is defined by the underground rock formation. In some embodiments, a diameter of the lateral wellbores may be from 5 in to 30 inches (in). In some embodiments, secondary lateral wellbores may be drilled off the initial primary lateral wellbore as needed to increase the total volumetric capacity of the disposal system. In some embodiments, a steel (or steel like) casing may be placed within the horizontal lateral wellbore(s) and cemented in place by circulating cement in the annular space between the steel casing and the wall of the given wellbore.
In some embodiments, DU nuclear waste may be stored in a container or capsule and the encapsulated nuclear waste may be positioned within the horizontal lateral wellbore(s) as described herein. In some embodiments, the capsules/containers (with the DU) may then be sealed in place with appropriate means.
In some embodiments, DU nuclear waste may be stored in a deep human-made caverns. In some embodiments, the human-made cavern may be located within a deep geological rock structure/formation. By enlarging a pilot wellbore by under-reaming (or the like) to a significant and predetermined diameter and continuing to drill-out the cavity/cavern from 500 feet up to 10,000 feet, this operation may produce a permanent human-made cavity/cavern for waste disposal. A geologic human-made cavern of this size can provide more than 1,500,000 gallons of liquid waste storage or about 200,000 cubic feet of volumetric storage.
Briefly, one aspect of the disposal method in accordance with this invention achieves the intended objectives by including the steps of: drilling a pilot well which intersects a deep geologic rock formation. The creation of a human-made cavern/cavity, by under-reaming processes from a vertical and/or lateral wellbore, can be designed to allow the geometry and location of the human-made cavern/cavity to be controlled so that the life of the human-made cavern/cavity is a safe repository for nuclear waste.
In some embodiments, methods of the present invention may provide an operational method for fabricating at least one DU waste capsule/container. In this operational method, the tasks involved provide a more efficient methodology to allow safer, more economical, and long-lasting disposal of the DU waste in the deep underground repositories.
The eventual degradation of the physical integrity of well bore system components should be considered and addressed with respect long-term nuclear waste disposal and/or storage. Some mechanisms and/or means are needed to minimize, reduce, and/or mitigate such degradation. A long-lived technology system may be required to guarantee within technical certainty that DUP, DUF, and/or DUM may be safely contained within and/or adjacent to the given geological repository zone.
Means may be utilized that provide for very long-lived protection from degradation and migration of material away from the nuclear waste material. Stratigraphic and current structural geological analysis of underground oil formations which have historically produced heavy oil and other hydrocarbons indicate that tar-like deposits have existed for millions of years and have remained essentially unchanged and intact over such long time periods. In many cases such tar-like deposits actually formed an impermeable seal that prevented fluid flow across a rock matrix due to physical and chemical changes in the rock media.
Bitumen-like products and some petroleum-based products possess the qualities that make them capable of being utilized for low temperature sealing situations in the disposal of nuclear wastes. Other higher temperature resistant chemical products may be needed for higher temperature situations.
In many oil reservoirs, geologists have defined so-called “marker” beds of tar or high viscosity bitumen which are millions of years old. This geologic phenomenon illustrates the chemical stability of the hydrocarbon-based material over very long time periods, often of millions of years. This chemical stability of the tar-like material allows a selection of natural or similar synthetic hydrocarbons or hydrocarbon derivatives-based materials as the long-lived high-temperature resistant layer used to surround DU waste materials inside waste receiving capsules/containers. This patent application may provide for the use of such a protective medium in the protection of the DU material, protection of the nuclear waste components, and/or in the protection of the environment from the DU material.
The current invention may teach an improved engineered barrier system implemented with a longest duration barrier, the protective medium, at the inner-most layer of protection. In a naturally occurring degradation process, the degradation beginning at the outermost layer in contact with the earth (rock formation) continues inwards into the central core of the nuclear waste disposal system. The outer protective layers, outer cement, outer casing pipe (e.g., of steel), inner cement, inner pipe (e.g., of steel), all may degrade over varying time periods. The inner-most tar-like protective medium has been historically demonstrated in the geological record, to be an effective fluid and migration barrier for millions of years. In numerical terms the cement and steel (or steel like compositions) may degrade in 2,000 to 10,000 years, however the tar or tar like protective medium encasing a central core may protect the core for hundreds of thousands of years or more.
This invention specifically addresses the following technical consideration: the waste capsule/container may provide short-term protection, such as, up to 10,000 years. Long-term protection of the nuclear waste forms from the ecosphere may depend in part on the physical properties of the deep geological repository.
An object of the present invention may be to provide a method and/or a system of disposing of nuclear waste in the form of DUP, DUF, and/or DUM in deep underground rock formations.
An additional object of the present invention may be to provide a method and/or a system of disposing of nuclear waste (such as, DUP, DUF, and/or DUM) in deep underground rock formations which may in turn provide protection in case of rupturing or leaking of the nuclear waste containing capsules/containers.
An additional object of the present invention may be to provide a method of disposing of DU nuclear waste in capsules/containers which would minimize the physical and chemical degradation of the waste material for a sufficiently long period of time in the geological environment.
An additional object of the present invention may be to provide a method and/or a system wherein the nuclear waste containing capsules/container may be easily placed, located, dispersed, or “landed” in the wellbores or caverns (including human-made caverns) as a linear string of connected elements (e.g., a linear string of connected capsules/containers).
An additional object of the present invention may be to provide a method and/or a system wherein the nuclear waste containing capsules/containers may be rapidly landed or deployed in the wellbore laterals or caverns (including human-made caverns) without a need for a major operation at the wellsite.
An additional object of the present invention may be to provide a method and/or a system of disposing of DU nuclear waste in deep underground rock formations which may provide for retrieval at some future date less than 100 years.
It is another object of the invention to provide a method and/or a system of the type described wherein a human-made cavern of substantial strength and durability, with sufficiently protective walls and volumetric capacity can be formed in a deep geologic formation being several thousand feet below the earth's surface and wherein the human-made cavern can be several thousand feet in vertical extent with a large diameter ranging from two feet to as much as ten feet.
It is yet another objective of the present invention to utilize a tar, tar-like, bitumen, bitumen-like material as a protective medium surrounding the DU waste material.
These and other advantages and features of the present invention are described herein with specificity so as to make the present invention understandable to one of ordinary skill in the art, both with respect to how to practice the present invention and how to make the present invention.
Elements in the figures have not necessarily been drawn to scale in order to enhance their clarity and improve understanding of these various elements and embodiments of the invention. Furthermore, elements that are known to be common and well understood to those in the industry are not depicted in order to provide a clear view of the various embodiments of the invention.
In the following discussion that addresses a number of embodiments and applications of the present invention, reference is made to the accompanying drawings that form a part thereof, where depictions are made, by way of illustration, of specific embodiments in which the invention may be practiced. It is to be understood that other embodiments may be utilized and changes may be made without departing from the scope of the invention.
The novel and non-obvious features which are considered characteristic for embodiments of the present invention are set forth in the appended claims. Embodiments of the present invention itself, however, both as to construction and methods of operation, together with additional objects and advantages thereof, will be best understood from the following description of the specific embodiments when read and understood in connection with the accompanying drawings. Attention is called to the fact, however, that the drawings are illustrative only, and that changes may be made in the specific construction illustrated and described within the scope of the appended claims.
Notes on some terminology used herein: The term depleted uranium penetrators refers to military munitions that may be referred to herein as “DUP.” The term “DUF” refers to the specific products of depleted uranium hexafluoride and their derivatives. The term “DUM” is a generic term herein referring to “depleted uranium material” in forms different from the depleted uranium penetrators (DUPs). And the term “DU” may refer to depleted uranium. In this patent application the words “capsule” and “container” may be used interchangeably with the same meaning.
In this patent application the terms nuclear waste and radioactive waste describing high-level nuclear waste may also be used interchangeably herein. In addition, the term waste generally means nuclear or radioactive waste in general, and DU waste in particular, or waste derived from DU.
In this patent application the terms “well” and “wellbore” may be used interchangeably and refer to cylindrical elements implemented in design and/or installation processes of some embodiments of the present invention. In addition, the term “ream” and “under-ream” may be used interchangeably to mean the enlarging of a wellbore or hole in a rock medium, that may then result in the formation of a human-made cavern.
In this patent application the terms “cavern,” and “cavity” may be used interchangeably with the same meaning.
In addition, “matrix rock” and “host rock” may be used interchangeably.
Note, unless an explicit reference of “vertical wellbore” or “lateral wellbore” (i.e., “horizontal wellbore”) accompanies “wellbore,” use of “wellbore” herein without such explicit reference may refer to vertical wellbores or lateral wellbores, or both vertical and lateral wellbores. “Laterals” may refer to lateral wellbores.
In some embodiments, a method may provide an operational process for long-term disposal/storage of DUP, DUF, and/or DUM. Such methods may provide for more efficient methodology to allow safer, more economical, and long-lasting disposal/storage of DUP, DUF, and/or DUM waste in deep underground lateral wellbores and/or human-made caverns.
In some embodiments, at least one capsule 16 may be configured for receiving DU within the at least one capsule 16; wherein the at least one capsule 16 may be sealable.
In some embodiments, the at least one capsule 16 may be a substantially cylindrical member of a length and of a diameter that are both fixed (non-variable) and finite (predetermined); wherein the at least one capsule 16 may be comprised of a side-wall and opposing terminal ends that form the substantially cylindrical member; wherein the opposing terminal ends seal the at least one capsule 16. See e.g.,
In some embodiments, the at least one capsule 16 may comprise an exterior that may be substantially constructed of one or more of: a metal, a plastic, a composite, or a ceramic. In some embodiments, the metal may be selected from one or more of: steel, copper, or lead.
In some embodiments, DU kinetic elements 12 may be “circle packed” inside capsule 16. In some embodiments, DU kinetic elements 12 may be disposed in capsule 16 and may be separated and held in place by supports 17. In some embodiments, supports 17 may be known as dividers 17, and/or may function as a divider or dividers, separating one DU kinetic elements 12 from another DU kinetic element 12 within a given capsule 16. In some embodiments, supports 17 may be structural members.
In some embodiments, when the at least one divider 17 may be inserted into the at least one capsule 16, the at least one divider 17 may subdivide an internal volume of the at least one capsule 16 into a predetermined quantity of two or more sub-internal volumes of the at least one capsule 16; wherein each sub-internal volume of the at least one capsule 16 may be configured to receive at least some DU. In some embodiments, the at least one divider 17 may facilitate various “circle packing” schemes, see e.g.,
In some embodiments, a protective medium 18 may be placed inside capsule 16 walls and may fill void space and surround the DU kinetic elements 12. In some embodiments, protective medium 18 may be used in a variety of forms, ranging from semi-solid, moderately viscous substances, to slurries to liquids or even in some cases powders. In some embodiments, protective medium 18 may be selected from one or more of the following: tar, tar-like, bitumen, bitumen-like, asphalt, asphalt-like, heavy hydrocarbons, heavy oils, synthetic compounds, bentonite clays, vermiculite clays, modified clay nanotube compounds or their derivatives, combinations thereof, and/or similar hydrocarbon system. Protective medium 18 may afford long term protection as in the case of tars and their derivatives. Protective medium 18 may also include biocides. Protective medium 18 may also include anti-corrosion products/agents. Protective medium 18 may also include clay material like treated bentonites, treated vermiculites, and/or combinations thereof.
In some embodiments, protective medium 18 may be configured for minimizing degradation of the at least one capsule 16 from radiation emitted by the DU.
In some embodiments, protective medium 18 may be heated from about 80 degrees Celsius to about 195 degrees Celsius before inclusion in capsule 16 to destroy or “pasteurize” protective medium 18 by destroying or killing microbes and fungi that may be present in protective medium 18. The destruction or killing microbes and fungi may prevent future microbial degradation of protective medium 18 by microorganisms that may be naturally or inadvertently present in protective medium 18. In some embodiments, a biocide may be used to treat protective medium 18 to kill the destructive microbes (and fungi). This possible microbial degradation can lower the long-time effectiveness of protective medium 18 which is expected to protect contents of capsule 16 for up to 10,000 years or more.
It is further noted that the protective medium 18 may be an anoxic and/or an anaerobic medium. In some embodiments, capsule 16 and its contents may be purged with nitrogen to remove any air before the packaging process with protective medium 18 is complete. In such a case, specific oxygen scavengers and/or other corrosion retarding compounds may be included in protective medium 18.
In some embodiments, the system may further comprise a gas blanket. In some embodiments, the gas blanket may substantially fill in void space around the DU that is within the at least one capsule 16 to minimize a presence of oxygen in the at least one capsule 16. In some embodiments, the blanket gas may purge (push out) oxidizing gasses, such as oxygen present in air within the at least one capsule 16. In some embodiments, a gas for use in the gas blanket may be an inert gas or a substantially inert gas. In some embodiments, a gas for use in the gas blanket may be nitrogen gas.
In other embodiments the void space around DU kinetic elements 12 in capsule 16 may be filled with protective liquids and/or slurries containing selected oxygen (O2) scavenging agents and/or corrosion resistant agents. The oxygen scavengers may be organic, inorganic, and/or combinations thereof. The oxygen scavengers may be selected from the following: a sulfite compound, sodium sulfite, sodium bisulfite, ammonium sulfite, ammonium bisulfite, sodium meta-bisulfite, potassium sulfite, potassium bisulfite, potassium meta-bisulfite, calcium sulfite, calcium hydrogen sulfite, and/or combinations thereof. Commercially available brands of oxygen scavengers and/or corrosion inhibitors include: NOXYGEN™, AMI-TEC™, KD700™, and KD40™. In some embodiments, these oxygen scavengers and/or corrosion inhibitors may be added in the range of at least 0.1 gallon per 100 barrels to 500 barrels of liquids. The actual usage amount may vary with the oxygen concentration in the selected medium. In some embodiments, a film-coating inhibitor may be used to help protect DU kinetic elements 12 from corrosion. This combination of protective agents reduces the presence of oxidizing ions which decrease the tendency of DU kinetic elements 12 to corrode, degrade, deteriorate, and/or disintegrate. In some embodiments, protective medium 18 may include oxygen scavengers.
In some embodiments, void space around DU kinetic elements 12 in capsule 16 may be filled by other materials which can lower radionuclide migration or slow down capsule 16 and DU kinetic elements 12 degradation/corrosion. It is possible and contemplated in this patent application to store a large, but finite, fixed, and predetermined quantity of DU kinetic elements 12 inside a given capsule 16 depending on the radial dimensions and length of the given capsule 16. In some embodiments, contemplated sizes of capsule 16 may be fixed and predetermined, but may be from 5 inches in diameter to 24 inches in diameter. In other embodiments, capsule 16 have other fixed and predetermined diameters.
Efficient volumetric packing of DU kinetic elements 12 within a given capsule 16 may be possible using available packaging methods well known in the packaging industry. Further elements shown in the
In some embodiments, cement 19b may be a filler. In some embodiments, this filler (such as, but not limited, cement 19b), may substantially fill in space between an exterior of casing 20 and an interior of the at least one wellbore 25/26. See e.g.,
Continuing discussing
Continuing discussing
In some embodiments, capsule 16 body may be substantially constructed of structural steel or a similar metal. In this type of capsule 16 construction, multiple waste capsules 16 may form part of a chain of capsules 16 that are joined by couplings 24 to form a string (see e.g.,
In some embodiments, medium 19a may be protective. In some embodiments, medium 19a may be a filler. In some embodiments, this filler (medium 19a) may substantially fill in space between an interior of casing 20 and an exterior of the at least one capsule 16. In some embodiments, medium 19a may be drilling mud material or the like. In some embodiments, medium 19a may be comprised of specialized drilling mud or bentonites-like compounds if the disposal is intended as temporary (e.g., intended as less than permanent); or if the waste capsules/container 16 is expected to be retrieved after a reasonably short time, such as, but not limited to, 100 years. If the disposal process is intended as permanent, then medium 19a may be similar (or substantially similar) to cement 19b which may be intended as a permanent cement.
In an alternative embodiment, capsule 16 may be used primarily as a transport device in which the DU is transported from the earth's surface 8 (see e.g.,
In some embodiments, capsules 16 with DU kinetic elements 12 (e.g., as shown in
In some embodiments of the configuration shown in FIG.2D, an annular space between capsule 16 (which may be in a string of capsules 16) and casing 20 may be filled with medium 19a (which may be a drill mud material as noted above) which may remain gelled over time but would still allow capsule(s) 16 to be retrieved back to surface 8 (see e.g.,
In some embodiments, the system may comprise at least one additional capsule 16 (that may be in addition to the at least one capsule 16), wherein this at least one additional capsule 16 may be configured for receiving at least some DU within the at least one additional capsule 16. That is, in some embodiments, the system may comprise at least two capsules 16, the at least one capsule 16 and the at least one additional capsule 16. See e.g.,
In some embodiments, the system may further comprise at least one coupling 24; wherein the at least one coupling 24 may attach (removably so in some embodiments) the at least one capsule 16 to the at least one additional capsule 16 resulting in a string of capsules 16. In some embodiments, the system may comprise a string of capsules 16. In some embodiments, adjacent capsules 16 in the given string of capsules 16 may be attached to each other via coupling 24. In some embodiments, a string of capsules 16 may also be known as a plurality of capsules 16. In some embodiments, the string of capsules 16 may be arranged in a linear fashion end to end (as opposed to being arranged from side-wall to side-wall). See e.g.,
In some embodiments, the system further may comprise at least one nipple 24a. In some embodiments, the at least one nipple 24a may be attached to an end of the at least one capsule 16 (e.g., an end closer to surface 8). In some embodiments, the at least one nipple 24a may be an attachment structure for facilitating inserting or retrieving of the at least one capsule 16 within the at least one wellbore 25/26. See e.g.,
Continuing discussing
Further illustrated in
In some embodiments, deep geological rock formation 23 (host rock 23) may be one or more of: impermeable sedimentary rock, very low permeability sedimentary rock, impermeable metamorphic rock, very low permeability metamorphic rock, impermeable igneous rock, very low permeability ingenious rock, combinations thereof, and/or the like. “Impermeable” in this context may be with respect to water migration and/or with respect to radionucleotide migration. “Impermeable” may be having permeability measurements less than 10 nanodarcy. “Very low permeability” in this context may be with respect to water migration and/or with respect to radionucleotide migration. “Very low permeability” may be having permeability measurements between 10 and 1,000 nanodarcy.
In some embodiments, deep geological rock formation 23 (host rock 23) may be subterranean (underground), located at least 10,000 feet to 30,000 feet below an Earth surface 8 location, plus or minus 1,000 feet.
Continuing discussing
In some embodiments, at least one wellbore 25/26 may extend into the deep geological rock formation 23 (host rock 23); wherein the at least one wellbore 25/26 may be configured to receive the at least one capsule 16 (e.g., with some DU).
In some embodiments, the at least one wellbore 25/26 may be formed from drilling rig 9. See e.g.,
In some embodiments, the at least one wellbore 25/26 may be drilled from an Earth surface 8 location. See e.g.,
In some embodiments, the at least one wellbore 25/26 may be comprised of at least one substantially vertical section (generally denoted with reference numeral “25”), at least one substantially horizontal section (lateral section) (generally denoted with reference numeral “26”), and at least one transitional section (generally denoted with reference numeral “26”) that may links the at least one substantially vertical section 25 to the at least one substantially horizontal section 26; wherein “vertical” and “horizontal” may be with respect to an Earth surface 8 location located above the at least one wellbore 25/26, wherein the Earth surface 8 location may be deemed a substantially horizontal surface.
In some embodiments, a distal end of the at least one wellbore 25/26 may terminate at an end of the at least one substantially horizontal section 26.
In some embodiments, a distal end of the at least one wellbore 25/26 may terminate at an entrance to at least one human-made cavern 27, wherein the at least one human-made-cavern 27 may be located within the deep geological rock formation 23 (host rock 23).
In some embodiments, the at least one wellbore 25/26 may have at least one diameter that is drilled at a particular and predetermined size. In some embodiments, wellbore 25/26 may have different diameters, but each different diameter may be of a fixed sized. In some embodiments, a diameter of wellbore 25/26 may be from ten to 48 inches, plus or minus 6 inches.
In some embodiments, the at least one wellbore 25/26 may have a length from 5,000 feet to 30,000 feet, plus or minus 1,000 feet.
In some embodiments, a distal end of away from an Earth surface 8 location of the at least one wellbore 25/26 may be a final depository location for DU.
In some embodiments, the at least one wellbore 25/26 may be a transit means configured for transit of DU through the at least one wellbore 25/26.
In some embodiments, the at least one human-made cavern 27 may be substantially cylindrical in shape. In some embodiments, a length of human-made cavern 27 may be substantially parallel with the substantially vertical section of wellbore 25. See e.g.,
In some embodiments, the at least one human-made cavern 27 may have a volume that may be fixed and predetermined, wherein this volume may be selected from the range of 100,000 gallons to 2,000,000 gallons for a given at least one human-made cavern 27, plus or minus 10,000 gallons.
In some embodiments, the at least one human-made cavern 27 may be a final depository location for storage of at least some DU.
In some embodiments, the at least one capsule 16 (with at least some DU in some embodiments) may be received into the at least one human-made cavern 27.
In some embodiments, supernatant medium 28b may be at least one filler, wherein this at least one filler may fill in void space around DU that is inside of the at least one human-made cavern 27. See e.g.,
In some embodiments, human-made cavern 27 may be configured to receive DU in various forms and/or formats, such as, in capsules 16/28, DUP, DUM, DUF, solids, liquids, slurries, combinations thereof, and/or the like. In some embodiments, DU (in various forms and/or formats, such as, DUP, DUM, DUF, solids, liquids, slurries, combinations thereof, and/or the like) may be stored (and/or disposed of) in a given human-made cavern 27 without use of capsules 16/28.
In some embodiments, the at least one wellbore 25/26 may terminate in the at least one human-made cavern 27. See e.g.,
In some embodiments, the materials to be disposed of (stored) may be one or more of: DU kinetic element 12, waste DUM 28, solid or cementitious waste DUM 28a, and/or waste DUM 28a that was injected/pumped in as a slurry (or slurry like). In some embodiments, method 600 may comprise two sub-methods 100 and 200.
In some embodiments, sub-method 100 operations may be a method of DUP disposal/storage specifically applied to DU (penetrator) kinetic elements 12. In some embodiments, sub-method 100 may comprise steps 610 to 645. In some embodiments, in sub-method 100, in step 610 the DU (penetrator) kinetic elements 12 may be collected; and in step 620 the DU kinetic elements 12 may be encapsulated, forming capsule(s) 16 with DU kinetic elements 12. In step 630 the capsules 16 may be sequestered in lateral wellbores 25. In step 640 the capsules 16 may be loaded into human-made cavern(s) 27. In step 645 the lateral wellbores 25 and human-made cavern(s) 27 may be sealed.
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Some of the steps of method 600, sub-method 100, and/or sub-method 200 may be mandatory, while other steps may be optional. In some cases, some steps may be done out of order of the sequence noted in
In some embodiments, sub-task 300 may be a method of DUP disposal/storage. In some embodiments, sub-task 300 (method 300) may comprise steps 701 to 708. In some embodiments, sub task 300 (method 300) may relate generally to the disposal/storage of DUP(s).
In some embodiments, sub-task 400 may be a method of DUM disposal/storage. In some embodiments, sub-task 400 (method 400) may comprise steps 709 to 715. In some embodiments, sub task 400 (method 400) may relate generally to the disposal/storage of DUM as cementitious mixtures like slurries, slurry like, and/or similar flowable mixtures or materials.
In some embodiments, sub-task 500 may be a method of DUM immobilization. In some embodiments, sub-task 500 (method 500) may comprise steps 716 to 723. In some embodiments, sub task 500 (method 500) may relate generally to the disposal/storage of DUM as solids and/or immobilized materials.
Some of the steps may be mandatory, while other steps may be optional. In some cases, some steps may be done out of order of the sequence noted in
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In this step 703, it may be contemplated that the packaging of DU kinetic elements 12 may be somewhat similar to a typical “canning” operation in an industrial setting with the inclusion of the required safety considerations for the radioactive nature of the DUP waste. Nothing in the physical packaging process may be considered as being challenging in the industry today (2019).
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In some embodiments, step 704 may include the building of a “cheaper version” of a capsule 16 in which capsule 16 may be used for transporting the DU into the final emplacement position in the deep underground system. In this embodiment, this inexpensive type capsule 16 may normally be used only for sequestering DU waste in deep human-made caverns 27 where capsules 16 may be landed individually or in small batches from surface 8 by mechanical means and the cavern 27 walls and deep geological rock formation 23 (host rock 23) become the protective system for long term viability of the DU waste. In these embodiments, capsule 16 may be made of materials like PVC or similar inexpensive yet structurally competent materials. In some embodiments, successful completion of step 704 may then progress into step 705.
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Regardless of the form of the DUF products, the safest form for disposal needs to be determined and implemented. The DUF must be safely disposed of away from the ecosphere. The DUF conversion process occurs at sites remote from the well sites where waste disposal occurs. DUF conversion is a massive industrial undertaking at this time (2019).
In some embodiments, successful completion of step 716 may then progress into step 717. (In some embodiments, successful completion of step 716 may then progress into step 710.)
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In some embodiments, the system described herein may be a system for storing (and/or for long-term disposal of) depleted uranium (DU) in a deep geological rock formation 23 (host rock 23). In some embodiments, such a system may comprise at least one capsule 16. In some embodiments, the system may further comprise at least one wellbore 25/26.
In some embodiments, the system may further comprise at least one divider 17, wherein the divider 17 may be insertable into the at least one capsule 16. In some embodiments, the system may further comprise casing 20, wherein casing 20 may be inserted into the at least one wellbore 25/26 and around the at least one capsule 16. See e.g.,
In some embodiments, the system may further comprise protective medium 18. In some embodiments, protective medium 18 may substantially fill in void space around the DU that is within the at least one capsule 16. In some embodiments, protective medium 18 may be configured for minimizing degradation of the at least one capsule 16 from radiation emitted by the DU.
In some embodiments, the system may further comprise a gas blanket. In some embodiments, the gas blanket may substantially fill in void space around the DU that is within the at least one capsule 16 to minimize a presence of oxygen in the at least one capsule 16. In some embodiments, the blanket gas may purge (push out) oxidizing gasses, such as oxygen present in air within the at least one capsule 16. In some embodiments, a gas for use in the gas blanket may be an inert gas or a substantially inert gas. In some embodiments, a gas for use in the gas blanket may be nitrogen gas.
In some embodiments, the system may further comprise a centralizer 21. In some embodiments, the systems and/or methods described herein, may comprise at least three centralizes 21, substantially equal distant spaced around capsule 16. In some embodiments, the systems and/or methods described herein, may comprise four centralizes 21, substantially equal distant spaced around capsule 16, see e.g.,
In some embodiments, the system may comprise drilling rig 9, see e.g.,
In some embodiments, the system may further comprise a filler (such as, but not limited to, medium 19a), wherein this filler may substantially fill in space between an interior of casing 20 and an exterior of the at least one capsule 16.
In some embodiments, the system may further comprise a filler (such as, but not limited, cement 19b), wherein this filler may substantially fills in space between an exterior of casing 20 and an interior of the at least one wellbore 25/26.
In some embodiments, the system may further comprise at least one human-made cavern 27 configured for receiving at least some DU for storage, wherein the at least one human-made cavern 27 may be located within the deep geological rock formation 23 (host rock 23). See e.g.,
In some embodiments, the system may further comprise at least one filler (such as, but limited to, supernatant medium 28b), wherein the at least one filler may fill in void space around DU that is inside of the at least one human-made cavern 27. See e.g.,
In some embodiments, the system may further comprise a plurality of human-made caverns 27, each configured for receiving at least some DU, wherein this plurality of human-made caverns 27 may be located within the deep geological rock formations 23 (host rocks 23), wherein the at least one wellbore 25/26 may branch out to connect to each human-made cavern 27 selected from the plurality of human-made caverns 27. See e.g.,
In some embodiments, the storage time-frame contemplated for the systems and methods described herein may be intended for up to 10,000 years, plus or minus 100 years. In some embodiments, the storage time-frame contemplated for the systems and methods described herein may be configured for up to 10,000 years, plus or minus 100 years.
In some embodiments, the types of DU that the systems and/or methods described herein may be configured for storing, may comprise at least a portion of DU in a form as one or more of: at least a portion of a projectile; or at least a portion of a munition—such as, but not limited to, DU kinetic element 12 (DU penetrator 12).
In some embodiments, the types of DU that the systems and/or method described herein may be configured for storing, may comprise at least a portion of DU in a form as one or more of: at least a portion of a solid; at least a portion of a salt; at least a portion of a liquid; at least a portion of a slurry; at least a portion of an aggregate; at least a portion of a cement; at least a portion of a ceramic; at least a portion of a glass; at least a portion of a block; at least a portion of a powder; at least a portion of a pellet, combinations thereof, and/or the like. In some embodiments, the DU to be stored may be substantially pumpable and/or substantially flowable to facilitate transit through wellbore(s) 25/26.
In some embodiments, the system may comprise the DU to be stored or that is stored according to an embodiment of this present invention. In some embodiments, the DU to be stored may be substantially pumpable and/or substantially flowable to facilitate transit through wellbore(s) 25/26.
Means, systems, mechanisms, and methods for the long-term disposal and/or storage and/or of depleted uranium (DU) penetrators and DU materials as waste (e.g., nuclear waste) within deep lateral wellbores and/or within human-made subterranean cavities (caverns) within deep geological rock formations have been described. The foregoing description of the various embodiments of the invention have been presented for the purposes of illustration and disclosure. It is not intended to be exhaustive or to limit the invention to the precise form disclosed.
Many modifications and variations are possible in light of the above teaching without departing from the spirit and scope of the invention.
While the invention has been described in connection with what is presently considered to be the most practical and preferred embodiments, it is to be understood that the invention is not to be limited to the disclosed embodiments, but on the contrary, is intended to cover various modifications and equivalent arrangements included within the spirit and scope of the appended claims.
