Abstract: A solidification method of radioactive waste is provided, including kneading a binder and an inorganic adsorbent to obtain a kneaded object, the in organic adsorbent included radionuclides; extruding the kneaded object to obtain an extruded material object; cutting the extruded material object to obtain at least one extruded material block; and firing the at least one extruded material block to solidify the at least one extruded material block.

Abstract: A waste form for and a method of rendering hazardous materials less dangerous is disclosed that includes fixing the hazardous material in nanopores of a nanoporous material, reacting the trapped hazardous material to render it less volatile/soluble, and vitrifying the nanoporous material containing the less volatile/soluble hazardous material.

Abstract: A hydrogel having a floatability where from 40% to 90% of a solution and/or suspension to be thickened are thickened starting from the surface of the liquid and the rest of the solution and/or suspension to be thickened is thickened starting from the bottom of the container, a process for preparing the hydrogel and also its use for absorbing blood and/or body fluids, especially in hygiene articles, or for thickening aqueous solutions and/or suspensions, especially for thickening medical wastes.

Abstract: A radioactive containment composition may be created for containing radionuclides from a radioactive material by mixing a clay mineral with water. This mixture may form an aqueous clay suspension. The mixture can be refined by filtering to remove coarse material. The aqueous clay suspension may be applied to a radioactive material, allowing the radionuclides to be exchanged with cations in the aqueous clay suspension. The resulting aqueous slurry, a silver-based solution may be added to produce a suspension. The suspension may be collected, heated and analyzed.

Abstract: Clay-based compositions capable of absorbing contaminants from surfaces or objects having surface faces may be applied to a surface and later removed, the removed clay-based compositions absorbing at least a portion of the contaminant from the surface or object to which it was applied.

Abstract: A radioactive containment composition may be created for containing radionuclides from a radioactive material by mixing a clay mineral with water. This mixture may form an aqueous clay suspension, which in turn can be refined by filtering to remove coarse material. The aqueous clay suspension may be applied to a radioactive material, allowing the radionuclides to be exchanged with cations in the aqueous clay suspension. The resulting aqueous slurry may be collected, heated and analyzed.

Abstract: A radioactive material sequestration system may include a radionuclide containment composition dispenser and a sorption based media container. The radionuclide containment composition dispenser may be configured for holding a radionuclide containment composition and be capable of dispensing the radionuclide containment composition to remove radionuclides from a radioactive material. The radionuclide containment composition is a mixture of a clay mineral and water. The sorption based media container may be configured for holding a sorption based media; receiving dispensed radionuclide containment composition; and sequestering the radionuclides. The radioactive material sequestration system may also include a probe.

Abstract: A radioactive containment composition may be created for containing radionuclides from a radioactive material by mixing a clay mineral with water. This mixture may form an aqueous clay suspension, which in turn can be refined by filtering to remove coarse material. The aqueous clay suspension may be applied to a radioactive material, allowing the radionuclides to be exchanged with cations in the aqueous clay suspension. The resulting aqueous slurry may be collected, heated and analyzed.

Abstract: A radioactive containment composition may be created for containing radionuclides from a radioactive material by mixing a clay mineral with water. This mixture may form an aqueous clay suspension. The mixture can be refined by filtering to remove coarse material. The aqueous clay suspension may be applied to a radioactive material, allowing the radionuclides to be exchanged with cations in the aqueous clay suspension. The resulting aqueous slurry, a silver-based solution may be added to produce a suspension. The suspension may be collected, heated and analyzed.

Abstract: A radioactive material sequestration system may include a radionuclide containment composition dispenser and a sorption based media container. The radionuclide containment composition dispenser may be configured for holding a radionuclide containment composition and be capable of dispensing the radionuclide containment composition to remove radionuclides from a radioactive material. The radionuclide containment composition is a mixture of a clay mineral and water. The sorption based media container may be configured for holding a sorption based media; receiving dispensed radionuclide containment composition; and sequestering the radionuclides. The radioactive material sequestration system may also include a probe.

Abstract: A radioactive containment composition may be created for containing radionuclides from a radioactive material by mixing a clay mineral with water. This mixture may form an aqueous clay suspension. The mixture can be refined by filtering to remove coarse material. The aqueous clay suspension may be applied to a radioactive material, allowing the radionuclides to be exchanged with cations in the aqueous clay suspension. The resulting aqueous slurry, a silver-based solution may be added to produce a suspension. The suspension may be collected, heated and analyzed.

Abstract: A radioactive containment composition may be created for containing radionuclides from a radioactive material by mixing a clay mineral with water. This mixture may form an aqueous clay suspension, which in turn can be refined by filtering to remove coarse material. The aqueous clay suspension may be applied to a radioactive material, allowing the radionuclides to be exchanged with cations in the aqueous clay suspension. The resulting aqueous slurry may be collected, heated and analyzed.

Abstract: The present invention utilizes one or more processes to immobilize a waste that contains one or more of radionuclides, hazardous elements, hazardous compounds, and/or other compounds present in the waste. Each of the processes create a barrier against leaching and diffusion of the wastes. The first barrier is created by integrating the waste with an immobilizing mineral. The second barrier is a layer of non-radioactive or non-hazardous material that covers the first barrier. The second barrier may be created using an overgrowth procedure or by sintering. The third barrier is created by a rock or glass matrix that surrounds the first and/or second barriers. The fourth barrier is created by ensuring that the rock or glass has the same or similar composition as the indigenous rock at the disposal site. The resultant rock or glass matrix is in equilibrium with the groundwater or local hydrothermal solutions that are saturated with components of the indigenous rock of the disposal area.

Abstract: Building bricks and tiles are made by mixing 60% to 75% clay, 20% to 40% sludge and 1% to 10% sand, all percentages being by weight of the total composition. This process utilizes industrial waste products to provide building materials which are lighter and stronger than conventional materials.

Abstract: A ceramic composition made from waste materials and a method for manufacturing the same are disclosed. The ceramic composition comprises between 5 and 75 by weight part of a solid stated waste material including heavy metals, between 15 and 45 by weight part of a fly ash and between 5 and 55 by weight part of a clay. The ceramic composition is manufactured by compositely stabilizing various waste materials and is available for a building material or an engineering material. Therefore, the waste materials are effectively recycled without causing environmental pollution.

Abstract: A process for treating thickened phosphatic clay suspensions, waste clay and phosphogypsum produced in the processing of phosphate ore by water beneficiation and chemical processing, the thickened phosphatic clay suspension having a solid content of from about 4 to about 40 percent by weight, includes mixing a sufficient amount of deflocculating agent with a thickened phosphatic clay suspension to cause deflocculation of the suspension to an extent sufficient to reduce the viscosity thereof to a value enabling the deflocculated suspension to be readily pumped from one location to another, the deflocculating agent comprising an alkali compound of a phosphorus oxide. The deflocculated suspension of reduced viscosity is pumped from one location to another and separated into a clay suspension and a phosphatic mineral and sand suspension.

Abstract: A method for forming a radiation-absorbing barrier around a radioactive component by flowing a radiation-absorbing cement grout into a container which encloses the component. The radiation-absorbing cement grout comprises a cement slurry, a finished foam material, a bentonite gel, and a radiation-absorbing metal constituent.

Abstract: A unique method for solidification of solutions containing boric acid and/or borates is disclosed in this invention. The boron species in the solutions are polymerized to form polyborates, and the solutions are then solidified by mixing with solidification agents which are prepared completely from inorganic materials. Therefore, the solid form produced by this method has no aging problem. The boron species in the solution are not merely wastes to be encapsulated or embedded, they take part in the solidification reaction and share a major portion of total reactants. Thus, the total volume of solid forms produced in this invention is less than 1/10 of that produced in conventional cementation.

Abstract: A red brick comprising waste foundry sand of 30.about.50 wt %, dusts of 5.about.10 wt %, and a remainder of clay. The waste foundry sand and dusts can be efficiently recycled, and the quantity of the sand used, the supply of which sand which is nearly exhausted, can be reduced. The heating temperature in the red brick manufacturing process is remarkably lowered, and the economical efficiency of the manufacturing process is improved greatly by using iron oxide included in dusts, instead of a chemical compound to obtain desired color.

Abstract: Treatment compositions and a method are provided for the removal of a plurality of heavy metals and radioactive isotopes from wastewater. The treatment compositions comprise an alkali; adsorbents, such as montmorillonite and illite clays; catalysts, such as polyelectrolytes and sodium carbonate; one or more flocculants, such as a metal salt and calcium hydroxide; zirconium as a chelating and complexing agent; and boron as a neutron absorbent. The selected composition is introduced into and mixed with the wastewater, which is then filtered to produce a sludge containing the contaminants.

Abstract: A method for forming a radiation-absorbing barrier around a radioactive component by flowing a radiation-absorbing cement grout into a container which encloses the component. The radiation-absorbing cement grout comprises a cement slurry, a finished foam material, a bentonite gel, and a radiation-absorbing metal constituent.

Abstract: A safely encapsulated hazardous waste product free of unwanted leaching of contaminated metal constitutents and process therefor wherein a quantity of hazardous waste and a quantity of shale material characterized by having an aluminosilicate content containing at least 9.35% by weight of Fe.sub.2 O.sub.3, wherein the shale is reduced to a fine mesh before mixing, and defines a brick-like form as fired at about 1,150.degree. C. for a period of time to change the shale material into a semi-molten state and thereafter cooled to safely encapsulate the waste within the shale as a unit-handled product. The product of the invention satisfies and exceeds RCRA and LDR (EPA) requirements as shown by Toxicity Characteristic Leaching Procedure (TCLP) results.

Abstract: The method of the invention provides a geopolymeric binder in powder, used for the ultra rapid treatment of materials, soils or mining tailings, containing toxic wastes. Said geopolymeric binder has a setting time equal to or greater than 30 minutes at a temperature of 20.degree. C. and a hardening rate such as to provide compression strengths (Sc) equal to or greater than 15 MPa, after only 4 hours at 20.degree. C., when tested in accordance with the standards applied to hydraulic binder mortars having a binder/sand ratio equal to 0.38 and a water/binder ratio between 0.22 and 0.27. The preparation method includes the following three reactive constituents:a) an alumino-silicate oxide (Si.sub.2 O.sub.5, Al.sub.2 O.sub.2) in which the Al cation is in (IV-V) coordination as determined by MAS-NMR analytical spectroscopy for .sup.27 Al;b) a disilicate of sodium and/or potassium (Na.sub.2.K.sub.2)(H.sub.3 SiO.sub.4).sub.

Abstract: A decontamination composition comprises 40 to 60 percent of a compound selected from the group consisting of oxalic acid, alkali metal and ammonium salts of oxalic acid and mixtures thereof; 5 to 20 percent of a compound selected from the group consisting of citric acid, alkali metal and ammonium salts of citric acid and mixtures thereof; 20 to 40 percent of a compound selected from the group consisting of polyaminocarboxylic acid, alkali metal and ammonium salts of polyaminocarboxylic acid and the combination of a polyaminocarboxylic acid and a neutralizing compound, and mixtures thereof; 0 to 2 percent of a nonionic surfactant; about 0 to 2 percent of a dispersant; and about 0 to 2 percent of a corrosion inhibitor. The present invention also relates to a method of decontaminating a surface whereby contaminants in the form of NORMs are removed therefrom.

Abstract: A method for treating materials such as wastes for solidification to form a solid, substantially nonleachable product. Addition of reactive silica rather than ordinary silica to the material when bringing the initial molar ratio of its silica constituent to a desired ratio within a preselected range increases the solubility and retention of the materials in the solidified matrix. Materials include hazardous, radioactive, mixed, and heavy metal species. Amounts of other constituents of the material, in addition to its silica content are also added so that the molar ratio of each of these constituents is within the preselected ranges for the final solidified product. The mixture is then solidified by cement solidification or vitrification.

Abstract: Remediation of soil, concrete and groundwater using electropotential gradient induced migration of a target ion and immobilization and/or confinement of the target ion by a host receptor matrix (HRM). In addition to immobilizing and/or confining the target ion, the HRM can comprise a buffer or an ionizable species which releases an exchange ion during application of the electropotential gradient. The exchange ion, when less mobile than a (H.sup.+) ion or hydroxyl (OH.sup.-) ion, increases the efficiency of energy usage during decontamination. The exchange ion can also perform other tasks in the vicinity of the electrodes which improve the decontamination process. The host receptor matrix can comprise a material which is water impermeable and which has a low surface energy, such as a layer of polytetrafluoroethylene film. When such a material is used, the host receptor matrix can comprise a receptacle in which there is a liquid and/or solid composition.