US3379013A - Method of disposing of waste materials - Google Patents

Method of disposing of waste materials Download PDF

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Publication number
US3379013A
US3379013A US421783A US42178364A US3379013A US 3379013 A US3379013 A US 3379013A US 421783 A US421783 A US 421783A US 42178364 A US42178364 A US 42178364A US 3379013 A US3379013 A US 3379013A
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Prior art keywords
waste
slurry
cement
formation
radioactive
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US421783A
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English (en)
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Knox A Slagle
Tamura Tsuneo
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Halliburton Co
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Halliburton Co
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Priority to GB1054740D priority Critical patent/GB1054740A/en
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Priority to US421783A priority patent/US3379013A/en
Priority to FR32436A priority patent/FR1458501A/fr
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04—Treating liquids
    • G21F9/20—Disposal of liquid waste
    • G21F9/24—Disposal of liquid waste by storage in the ground; by storage under water, e.g. in ocean
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B09—DISPOSAL OF SOLID WASTE; RECLAMATION OF CONTAMINATED SOIL
    • B09B—DISPOSAL OF SOLID WASTE NOT OTHERWISE PROVIDED FOR
    • B09B1/00—Dumping solid waste
    • B09B1/008—Subterranean disposal, e.g. in boreholes or subsurface fractures
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04—Treating liquids
    • G21F9/06—Processing
    • G21F9/16—Processing by fixation in stable solid media
    • G21F9/162—Processing by fixation in stable solid media in an inorganic matrix, e.g. clays, zeolites
    • G21F9/165—Cement or cement-like matrix

Definitions

  • ABSTRACT OF THE DISCLOSURE A method of disposing of radioactive waste materials, wherein the materials are added to a hydraulic cement slurry comprising attapulgite and illite type clays, the cement slurry is pumped into an earth formation under fracturing pressure and allowed to set in the fractures created.
  • the present invention relates to a new and improved method of disposing of waste materials by hydraulic fracturing and particularly to a method of disposing of radioactive wastes or materials.
  • US. Patent No. 3,108,439 discloses a number of prior art methods of disposing of radioactive waste materials and particularly a method of underground disposal of radioactive liquids or slurries wherein an impermeable rock formation is fractured and the radioactive slurry injected thereinto and subsequently injecting a sealing material into the impermeable formation to thereby seal the radioactive slurry in the impermeable rock formation.
  • the process of said prior art patent is carried out by first drilling a well so that it traverses a suitable formation with the depth selected to give adequate shielding from the most energtic fraction to be handled.
  • the well is then equipped with a casing which is sealed both above and below the fracturable formation, for example, with cement to insure its isolation.
  • the formation is fractured in a substantially horizontal direction. This may be performed according to any of the several recognized techniques, namely, gun perforating, preslotting the pipe, acid cutting, and the like, followed by injection of any suitable fracturing fiuid.
  • the formation can be fractured by using radioactive waste liquid or slurry as the fracturing fluid.
  • the waste can be employed alone or in combination with any of the conventional fracturing fluids or fracturing fluid additives, for example, fluid loss additives.
  • a well is drilled so as to traverse an impermeable, nonforaminous formation.
  • the formation is isolated as by cementing.
  • the nonporous formation is perforated by, for example, gun perforation. It may be found desirable to isolate the perforated zone with packers in some cases.
  • the fracturing fluid which may be the radioactive waste is pumped into the well under pressure, thereby building up a hydrostatic pressure. When the hydrostatic pressure exceeds the formation breakdown pressure, the formation will part or fracture. The pressure ceases to rise as fluid is injected and assumes a roughly constant value. The fluid pressure measurements at the surface indicate that the formation breakdown pressure has been reached.
  • the pressure drop may be small when the formation breakdown pressure is reached.
  • the formation breakdown pressure therefore, may be more accurately defined as the pressure at which the increase of the rate of fluid injection into the formation will not materially increase the fluid pressure.
  • the present invention utilizes the formation fracturing procedures hereinabove and is an improvement of this prior art method of waste disposal by fracture injection wherein cement and other additives are mixed or blended with the waste slurry to form a low viscosity pumpable slurry which sets into a hard mass after a predetermined time.
  • the drawing illustrates a schematic perspective view of a typical fracturing disposal plant for carrying out the method of the present invention and a partially sectional view of the earth formation beneath the plant.
  • radioactive waste fluids or materials are stored in suitable storage tanks 10.
  • Underground lines connect the storage tanks to a source of supply (not shown) and to the mixing equipment 11.
  • a pump house 12 has pumps located therein and suitably connected to the underground lines for pumping the waste material to the mixing equipment in the mixer cell.
  • the mixer cell contains suitable blending and mixing equipment 11, such as a dry solid blender and a jet mixer.
  • a water supply source .14 is also located nearby for providing water when the liquid content of the waste is less than that desired for preparing a suitable injection slurry or for such other uses as may be desired, and is connected to the mixing equipment or apparatus 11 by an underground line.
  • Additional underground lines connect the mixing equipment 11 to the wellhead fracturing manifold or Christmas tree 15.
  • a high pressure fracturing pump .16 is installed adjacent the mixer cell for pumping the slurry of the present invention from the mixing equipment 11 into the wellhead 15 and down the cased wellbore 17 into the earth formation 18.
  • a waste pit 19 is located near the mixer cell to catch any overflow or leakage from the wellhead 15 or the mixing apparatus -11. Suitable drainage is provided for enabling any excess or overflow slurry to run into the waste pit 19.
  • the waste pit is connected to both the mixing apparatus 11 and the storage tank by underground lines so that fluids collected therein may be disposed of when convenient.
  • an emergency trench or pit 20 is located near the waste pit 19 for collecting any overflow fluids therefrom. Sufficient drainage is provided for this.
  • Suitable shielding such as concrete, earth or other materials for protection from radioactive materials is placed around the various plant components.
  • the injection well 17 is cased from the wellhead to its lower end 17a to prevent fluids from escaping into areas of the formation in which no slurry is injected.
  • the drawing of the earth formation is partially cutaway so that the distribution of the slurry 21 into the earth formation 18 may be readily seen.
  • One or more cased observation wells 22 are located on the perimeter of the plant site for viewing the distribution of the slurry 21 in the earth formation 18.
  • the present invention eliminates this dangerous occurrence by adding relatively small amounts of cement, certain clays and other additives to the waste material to cause it to set, after displacement in the underground formation, into 'a solid mass of sufficient strength that it is substantially unaffected by overburden pressures.
  • a solid mass having a compressive strength of 50 to p.s.i. is suitable for most disposal operations. Greater or lesser compressive strengths may be had by varying the composition and amounts of additives in the fracturing slurry.
  • the slurry of the present invention for use in hydraulic fracturing and disposal of waste material in the fractured earth formation is one which may be pumped for periods of time to allow large quantities to be injected, is economical to prepare, does not exhibit any phase separation, sets into a reasonably hard solid mass, and in the case of radioactive waste materials, adequately retains radioactive nuclides.
  • a settable fracturing slurry may be prepared by adding cement, an adsorption type clay like attapulgite, and a chemical cement retarding agent to a waste material for disposal thereof in an underground formation fracture.
  • the slurry must contain sufficient water to form a pumpable slurry. The lower the viscosity of the slurry, the less pumping pressure required to move it.
  • a slurry having a viscosity of about 20 poises or less is preferred and is suitable for most uses.
  • the liquid waste material most frequently encountered had a viscosity of not more than about 3 poises.
  • the viscosity of high viscosity waste materials can be lowered to the preferred range by the addition of water or other suitable liquids.
  • the waste material in using the above slurry constituents, must have a pH of 7 or more.
  • the pH of the waste material can be increased by the addition of water thereto or by any other suitable means.
  • a material is added to the slurry which has the ability to retain radioactive isotopes by adsorption, ion exchange or some other mechanism.
  • a slurry may be prepared by using materials and amounts as follows:
  • Material Amount Portland cement 3l0 lbs/gal. of waste. Attapulgite clay 4-25% by weight of cement.
  • Illite clay 4-15% by weight of cement.
  • Chemical cement retarder 0.1-0.5 by weight of cement.
  • a slurry mix suitable for disposal of most types of liquid radioactive wastes in generally impervious beddedshale formations is as follows:
  • bentonite or other similar type clays may be substituted for the attapulgite clay, either in whole or in part, depending upon amount of radioactive ions present.
  • Bentonite is a good water retention agent, but flocculates in the process of high ionic content wastes.
  • Attapulgite clay, and particularly Attapu1gus-150 does not flocculate and is very effective in preventing phase separation, thus enabling a constant viscosity and a constant cement/ liquid ratio for the desired strength to be maintained.
  • Attapulgus-ISO substantially larger amounts of cement would be required; thus significantly increasing the cost of the mix.
  • radioactive cesium is the nuclide most easily leached from radioactive waste-containing cement. Thus, it is desirable to provide for increased retention of this and other problem nuclides.
  • the mineral Illite the principal constituent of Grundite clay, is effective in retaining cesium; therefore, the Grundite clay was added for this purpose.
  • cement-clay mixes set up rather rapidly, e.g., 2-3 hours.
  • the mix must retain its fluidity for several times that length of time, e.g., 15-20 hours.
  • the salts within the waste may contribute partially to the setting retardation; however, it is necessary to extend the setting time.
  • a relatively small amount of delta glucono lactone extends the setting time to the order of 18-20 hours.
  • Other suitable cement retarding agents may be used, including calcium lignosulfonate and calcium-sodium lignosulfonate.
  • a control is needed to regulate the addition of dry constituents to the liquid waste.
  • One effective method is that of measuring the density of the resultant slurry and varying the additions to maintain the desired density. Difliculty may be encountered in this measurement because of foam sometimes produced in the process of mixing the solids and waste liquid.
  • antifoaming agents used in other chemical processes, including several organic materials which may be used to control foam. Tributylphosphate was found to be effective when present in less than 300 parts per million concentration in the waste. Any suitable anti-foaming agent may be used.
  • Attapulgite The chief mineral in the fullers earth from Florida and Georgia, USA. An extensive replacement of Al for Mg is possible in its formula.
  • Attapulgus-150 Trade name of an attapulgite clay manufactured by Minerals and Chemicals Corp. of America.
  • Bentonite.--A rock composed essentially of mixture of montmorillonite and beidellite with the former predomimating-also a trade name given to highly adsorptive clays or swelling drilling muds.
  • Illite Gr0up.--A group related to the micas and of a complex chemical composition with the general formula (OH) K (Al .Fe .Mg .Mg (Si .Al 0 This group embraces the most common and widespread of the clay minerals and is the chief constituent of clay minerals and shales.
  • I liter- A general term for a group of mica-like minerals so common in argillaceous sediments; not a specific mineral species.
  • a typical example of the disposal of radioactive waste by hydraulic fracturing is as follows. An injection well is drilled to a depth of 1000 feet into an impermeable bedded-shale formation. This well is cased to the bottom with cement used as a sealant between the casing and the rock. One or more observation wells are placed along what is expected to be the periphery of the grout sheetused in water with a pressure of 3000 to 3700 p.s.i. and the casing is penetrated in about /2 hour. The initial fracture of the rock may be made at this time, or following the withdrawal of the slotting jet, by hydraulically pressurizing the well at the slot at about 4000 p.s.i. (as measured at the well head).
  • the character of the rock may be determined by a fluid-loss test; that is, measuring the rate and amount of bleedback fluid following separate injections of a given amount of water (e.g., 1700 gal.) at a selected pressure followed by the injection of the same amount of water to which is added a given amount of fluid-loss-additive. If any significant difference is noted, a fluid-loss-additive may be required in the final cement mixture.
  • a fluid-loss-additive may be required in the final cement mixture.
  • This tail-cut slurry not only functions as a flush, but also provides a strong plug behind the waste containing slurry.
  • This tail-out or normal cement slurry is preferably a normal ASTM Type I or Type II cement prepared using fresh water and does not contain any waste fluid. It is somewhat faster setting than the waste disposal slurry and sets to a higher compressive strength.
  • the observation wells are frequently logged to determine the pattern of the grout sheet, and the level thereof, as the grout approaches or passes around the observation well. This primarily assures that the grout sheet remains at a level where future release to the environment is improbable. Since these wells are eased, the escape of grout up the well shaft is prohibited.
  • an injection well was drilled to a depth of 1,055 feet and cased with 157 feet of 9%"-36#J55 surface casing and 1,050.96 feet of 5 /2-23#N80 Extreme Line casing cemented to the surface.
  • the injection tubing was 2 /s"6.4#N Extreme Line tubing.
  • the casing was slotted at 890.00 feet using 40 sacks of 1030 sand and a pump pressure up to 3,800 p.s.i.
  • the liquid waste material contained 5000 curies of cerium and synthetic waste solution as set forth hereinabove. Cerium was added so that core samples could be taken from the observation well and the grout sheet formed by this slurry could be distinguished from the grout sheets previously formed.
  • the fracturing slurry was made up as follows:
  • ASTM Type II cement was used rather than ASTM Type I, as the synthetic waste had a high sulfate content.
  • the Type II cement offered some degree of protection from the deleterious elfect of the sulfate. Similar slurry properties were obtained with both types of cements.
  • a Slurries contained tributyl phosphate de-foamer at a ratio cl 1 quart/1000 gallons of 10X waste.
  • the present invention while being particularly suitable for the disposal of waste materials containing radioactive nuclides or isotopes, it is also suitable for disposal of any other waste materials, such as non-radioactive industrial wastes and sewage products.
  • the water phase separation In disposing of non-radioactive wastes, while it is desirable that the water phase separation be low, it is not necessary that it be as low as in the case of disposing of radioactive wastes.
  • the small amount of liquids (nonradioactive) which might vomtcly escape to the earths surface could be sufficiently filtered so as not to pollute or contaminate surrounding areas.
  • the water phase separation should be relatively low.
  • a water phase separation in the slurry of less than about 1% is preferred, especially when disposing of radioactive wastes.
  • greater water phase separation may be permitted, as some water adsorption is made by the formation adjacent the slurry.
  • the amount of the adsorption will of course vary somewhat with the type of formation being fractured.
  • the present invention is especially adapted 1 1 for disposal of waste materials in substantially impermeable or bedded-shale formations, the invention is not so limited and may be carried out in any type of earth formation found to be satisfactory.
  • the present invention may be effective for disposal of waste materials in even incompetent sands, wherein actual fracturing is not necessary, but just a mere injection of the slurry into the formation and subsequent setting thereof.
  • the present invention relates to a new and improved method of disposing of wastes in an underground earth formation, wherein such wastes are introduced into the formation in a highly liquid or low viscosity state and then allowed to set into a hard mass, with the mass being substantially confined to the area injected therein.
  • a method of subterranean disposal of radioactive materials which comprises: providing a wellbore having a casing therein which penetrates an earth formation; fracturing through said earth formation to provide at least one fracture which extends into the formation at an angle with respect to the axis of said wellbore; injecting into a fracture so formed in the earth formation a settable fracturing slurry having a viscosity of less than about 20 poises, consisting essentially of the radioactive waste material, water in a sufiicient amount to provide the required slurry viscosity, hydraulic cement in an amount of from about 3 to about pounds per gallon of waste and water, an attapulgite clay in an amount of about 25% to about 4% by weight of cement, an illite type clay in an amount of about to about 4% by weight of cement and a chemical retarding agent in amount sufiicient to delay the setting of the slurry a relatively long period of time and subsequently permit the slurry to set into a hard mass; and,
  • hydraulic cement is selected from the group consisting of ASTM Type I cement and ASTM Type II cement.
  • a method of subterranean disposal of radioactive material which comprises: providing a wellbore having a casing therein which penetrates an earth formation; fracturing through said earth formation to provide at least one fracture which extends into the formation at an angle with respect to the axis of said wellbore; injecting into a fracture so formed in the earth formation a settable fracturing slurry having a viscosity of less than about 20 poises, less than about one percent water separation, a thickening time of from about 15 to about 18 hours and upon setting has a compressive strength of at least about 50 pounds per square inch; said slurry consisting essentially of the radioactive waste material, water in a sufficient amount to provide the required slurry viscosity, hydraulic cement in an amount sufficient to provide the required compressive strength, an attapulgite clay in an amount sufficient to provide the required minimum water separation, an illite type clay in an amount sufficient to substantially absorb the radioactive ions present in the slurry, and a cement retarding agent in an amount sufficient
  • said cement is selected from the group consisting of ASTM Type I cement and ASTM Type II cement and is present in an amount less than about 6 pounds per gallon of waste material and water
  • said attapulgite type clay is present in an amount of from about 8 to about 10% by weight of cement
  • said illite type clay is present in an amount of from about 6 to about 8% by weight of cement
  • said retarding agent is delta glucono lactone in an amount of from about 0.2% to about 0.3%by weight of cement.
  • the slurry contains from about 200 to about 400 parts per million of tributyl phosphate anti-foaming agent.

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Cited By (18)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3665716A (en) * 1970-08-10 1972-05-30 Z W Rogers Refuse disposal method
US4178109A (en) * 1977-10-11 1979-12-11 Krutenat Robert A Method for the disposal of nuclear or toxic waste materials
US4400314A (en) * 1980-10-14 1983-08-23 Chevron Research Company Method for the ultimate disposal of high level radioactive waste
US4468154A (en) * 1979-09-27 1984-08-28 Preussag Aktiengesellschaft Metall Method of disposal or temporary storage of waste material
US4576513A (en) * 1981-10-22 1986-03-18 Wintershall Ag Process for terminal storage of pumpable wastes
AU585950B2 (en) * 1985-02-15 1989-06-29 Elf France Cationic bituminous emulsions
US4900196A (en) * 1987-11-20 1990-02-13 Iit Research Institute Confinement in porous material by driving out water and substituting sealant
US6284681B1 (en) 1999-03-05 2001-09-04 Westinghouse Savannah River Company Reactive composite compositions and mat barriers
NL2009485C2 (nl) * 2012-09-18 2014-03-19 Grovawa B V Het bergen van verontreinigd materiaal.
US9539625B2 (en) 2014-04-22 2017-01-10 Grovawa B.V. Storage of contaminated material
US9630225B2 (en) 2014-01-28 2017-04-25 Red Leaf Resources, Inc. Long term storage of waste using adsorption by high surface area materials
US9833819B2 (en) 2015-04-06 2017-12-05 Safe Nuclear Solutions, LLC System for deep underground storage of radioactive waste
WO2018049205A1 (en) * 2016-09-12 2018-03-15 Grand Abyss, Llc Emergency method and system for in-situ disposal and containment of nuclear material at nuclear power facility
US10751769B1 (en) 2019-02-21 2020-08-25 Deep Isolation, Inc. Hazardous material repository systems and methods
US10861614B2 (en) * 2015-12-24 2020-12-08 Deep Isolation, Inc. Storing hazardous material in a subterranean formation
EP3592948A4 (en) * 2017-04-06 2021-01-27 MWD-IP Holdings, LLC NUCLEAR WASTE STORAGE AND MONITORING PROCESS AND SYSTEM
US10926306B2 (en) 2017-06-05 2021-02-23 Deep Isolation, Inc. Hazardous material storage repository in a subterranean formation
US11393604B2 (en) * 2015-07-27 2022-07-19 Harbin Qingrui Science And Technology Development Co., Ltd. Device for disposing nuclear waste using deep geological repository

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4560503A (en) * 1982-08-30 1985-12-24 John D. Gassett Fluid waste disposal

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US2776903A (en) * 1953-09-08 1957-01-08 American Marietta Co Hydraulic cement compositions containing air detraining agents and methods of making same
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US2961399A (en) * 1959-01-19 1960-11-22 Alberti Rudolf Method for neutralizing obnoxious radiation
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US2549507A (en) * 1947-12-13 1951-04-17 Standard Oil Dev Co Oil well cementing
US2531812A (en) * 1948-01-16 1950-11-28 Ernst A Hauser Application of drilling fluids
US2582459A (en) * 1948-11-03 1952-01-15 Standard Oil Dev Co Composition for oil well cementing
US2776903A (en) * 1953-09-08 1957-01-08 American Marietta Co Hydraulic cement compositions containing air detraining agents and methods of making same
US2815293A (en) * 1956-01-31 1957-12-03 Mary I Randall Insulating finishing cement and structural material
US3108439A (en) * 1958-09-24 1963-10-29 Continental Oil Co Underground disposal of radioactive liquids or slurries
US3274784A (en) * 1958-12-31 1966-09-27 Continental Oil Co Composition and method for fixing atomic waste and disposal
US2961399A (en) * 1959-01-19 1960-11-22 Alberti Rudolf Method for neutralizing obnoxious radiation
US3262274A (en) * 1962-09-27 1966-07-26 Mobil Oil Corp Containment of radioactive wastes

Cited By (28)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3665716A (en) * 1970-08-10 1972-05-30 Z W Rogers Refuse disposal method
US4178109A (en) * 1977-10-11 1979-12-11 Krutenat Robert A Method for the disposal of nuclear or toxic waste materials
US4468154A (en) * 1979-09-27 1984-08-28 Preussag Aktiengesellschaft Metall Method of disposal or temporary storage of waste material
US4400314A (en) * 1980-10-14 1983-08-23 Chevron Research Company Method for the ultimate disposal of high level radioactive waste
US4576513A (en) * 1981-10-22 1986-03-18 Wintershall Ag Process for terminal storage of pumpable wastes
AU585950B2 (en) * 1985-02-15 1989-06-29 Elf France Cationic bituminous emulsions
US4900196A (en) * 1987-11-20 1990-02-13 Iit Research Institute Confinement in porous material by driving out water and substituting sealant
US6284681B1 (en) 1999-03-05 2001-09-04 Westinghouse Savannah River Company Reactive composite compositions and mat barriers
NL2009485C2 (nl) * 2012-09-18 2014-03-19 Grovawa B V Het bergen van verontreinigd materiaal.
EP2708293A1 (en) * 2012-09-18 2014-03-19 Grovawa B.V. Method, installation and composition for the storage of contaminated material
US9630225B2 (en) 2014-01-28 2017-04-25 Red Leaf Resources, Inc. Long term storage of waste using adsorption by high surface area materials
US9539625B2 (en) 2014-04-22 2017-01-10 Grovawa B.V. Storage of contaminated material
US9833819B2 (en) 2015-04-06 2017-12-05 Safe Nuclear Solutions, LLC System for deep underground storage of radioactive waste
US11393604B2 (en) * 2015-07-27 2022-07-19 Harbin Qingrui Science And Technology Development Co., Ltd. Device for disposing nuclear waste using deep geological repository
US10861614B2 (en) * 2015-12-24 2020-12-08 Deep Isolation, Inc. Storing hazardous material in a subterranean formation
US10115489B2 (en) 2016-09-12 2018-10-30 Grand Abyss, Llc Emergency method and system for in-situ disposal and containment of nuclear material at nuclear power facility
CN109891046A (zh) * 2016-09-12 2019-06-14 格兰德爱比丝有限公司 用于在核电设施处核材料就地处理与控制的应急方法和系统
US11270805B2 (en) 2016-09-12 2022-03-08 Grand Abyss, Llc Emergency method and system for in-situ disposal and containment of nuclear material at nuclear power facility
CN109891046B (zh) * 2016-09-12 2022-05-31 格兰德爱比丝有限公司 用于在核电设施处核材料就地处理与控制的应急方法和系统
WO2018049205A1 (en) * 2016-09-12 2018-03-15 Grand Abyss, Llc Emergency method and system for in-situ disposal and containment of nuclear material at nuclear power facility
EP3592948A4 (en) * 2017-04-06 2021-01-27 MWD-IP Holdings, LLC NUCLEAR WASTE STORAGE AND MONITORING PROCESS AND SYSTEM
US10926306B2 (en) 2017-06-05 2021-02-23 Deep Isolation, Inc. Hazardous material storage repository in a subterranean formation
US11135629B2 (en) 2017-06-05 2021-10-05 Deep Isolation, Inc. Storing hazardous material in a subterranean formation
US11338337B2 (en) 2017-06-05 2022-05-24 Deep Isolation, Inc. Storing hazardous material in a subterranean formation
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