Abstract: A composition to immobilize nuclear containing waste comprising at least one radioactive element or alloy of uranium, graphite, magnesium, and aluminum, and a method of using the same to immobilize the nuclear containing waste into a solid wasteform. The composition comprises at least one mineral phase forming element or compound for reacting with the at least one radioactive element or alloy. The composition further comprises at least one glass-forming element or compound to form a glass phase that will incorporate waste radioisotopes and impurities that do not react with the mineral phase forming element or compound.

Abstract: Methods for converting toxic waste, including nuclear waste, to quasi-natural or artificial feldspar minerals are disclosed. The disclosed methods may include converting, chemically binding, sequestering and incorporating the toxic waste into quasi-natural or artificial Feldspar minerals. The quasi-natural or artificial feldspar minerals may be configured to match naturally occurring materials at a selected disposal site. Methods for the immediate, long term, quasi-permanent disposal or storage of quasi natural or artificial feldspar materials are also disclosed.

Abstract: Techniques for disposing of one or more toxic materials, such as coal waste (e.g., fly ash, sludge, etc.), include incorporating the toxic materials into artificial feldspar or forming artificial feldspar from the toxic material(s). The artificial feldspar may be used to form an artificial aggregate, which may be used in a construction material, as road base, as a fill material or for any other suitable purpose. Artificial aggregates that are formed from toxic materials are also disclosed, as are construction materials that include such artificial aggregates.

Abstract: Disclosed herein is a method of treating radioactive metal waste using melt decontamination, wherein radioactive metal waste, which is generated from nuclear fuel processing facilities or nuclear fuel production facilities, and which cannot be easily treated by surface decontamination because it has a complicated geometric shape, and the surface contamination of which cannot be measured, can be treated by melt decontamination. The method is advantageous in that radioactive metal waste, which cannot be treated by conventional surface decontamination, can be treated, so that radioactive metal waste can be recycled, thereby obtaining economic profits, and further in that a large storage space necessary for cutting and then storing radioactive metal waste is not required, and in that excessive manpower and cost are not required.

Abstract: The present invention relates to a vacuumable gel and the gel use to decontaminate surfaces, for example, radioactive decontamination. The gel is composed of a colloidal solution comprising: from 5 to 25 wt % of an inorganic viscosity modifier; from 0.01 to 0.2 wt % of a surfactant, preferably, a surfactant in an amount strictly below 0.1 wt %, wt % relative to the total weight of the gel; from 0.5 to 7 mol, per liter of gel, of an inorganic acid or base; and optionally from 0.05 to 1 mol, per liter of gel, of an oxidizer having a standard redox potential Eo greater than 1.4 V in a strong acid medium or of the reduced form of this oxidizer; the remainder being water. The gel may be applied, by spraying, to a surface to be decontaminated, and removed in the form of dry residues by suction or brushing after drying.

Abstract: The present invention relates to a method of optimizing self-supporting film production. The method includes the steps of: determining at least one scrap factor which relates to a total amount of scrap in processing a film product; correlating the at least one scrap factor to at least one processing parameter; and adjusting the at least one processing parameter to reduce the total amount of scrap in processing the film product. The present invention also relates to a system for optimizing film production.

Abstract: The present invention provides processes to immobilize high alkaline radioactive and/or hazardous waste in a silicate-based glass, the waste containing one or more of radionuclides, hazardous elements, hazardous compounds, and/or other compounds. The invention also provides silicate-based glass compositions for use in immobilizing radioactive and/or hazardous waste.

Abstract: A matrix material for safe temporary and/or ultimate disposal of radioactive wastes suitable for the embedment of radioactive wastes, contains graphite and at least inorganic binder which can be glass, aluminosilicate, silicate, borate and lead sulfide.

Abstract: Methods for converting toxic waste, including nuclear waste, to quasi-natural or artificial feldspar minerals are disclosed. The disclosed methods may include converting, chemically binding, sequestering and incorporating the toxic waste into quasi-natural or artificial Feldspar minerals. The quasi-natural or artificial feldspar minerals may be configured to match naturally occurring materials at a selected disposal site. Methods for the immediate, long term, quasi-permanent disposal or storage of quasi natural or artificial feldspar materials are also disclosed.

Abstract: Materials and methods of synthesizing mixed-layered bismuth oxy-iodine materials, which can be synthesized in the presence of aqueous radioactive iodine species found in caustic solutions (e.g. NaOH or KOH). This technology provides a one-step process for both iodine sequestration and storage from nuclear fuel cycles. It results in materials that will be durable for repository conditions much like those found in Waste Isolation Pilot Plant (WIPP) and estimated for Yucca Mountain (YMP). By controlled reactant concentrations, optimized compositions of these mixed-layered bismuth oxy-iodine inorganic materials are produced that have both a high iodine weight percentage and a low solubility in groundwater environments.

Abstract: A method of rendering hazardous materials less dangerous comprising trapping the hazardous material in nanopores of a nanoporous composite material, reacting the trapped hazardous material to render it less volatile/soluble, sealing the trapped hazardous material, and vitrifying the nanoporous material containing the less volatile/soluble hazardous material.

Abstract: Materials and methods of making low-sintering-temperature glass waste forms that sequester radioactive iodine in a strong and durable structure. First, the iodine is captured by an adsorbant, which forms an iodine-loaded material, e.g., AgI, AgI-zeolite, AgI-mordenite, Ag-silica aerogel, ZnI2, CuI, or Bi5O7I. Next, particles of the iodine-loaded material are mixed with powdered frits of low-sintering-temperature glasses (comprising various oxides of Si, B, Bi, Pb, and Zn), and then sintered at a relatively low temperature, ranging from 425° C. to 550° C. The sintering converts the mixed powders into a solid block of a glassy waste form, having low iodine leaching rates. The vitrified glassy waste form can contain as much as 60 wt % AgI. A preferred glass, having a sintering temperature of 500° C. (below the silver iodide sublimation temperature of 500° C.) was identified that contains oxides of boron, bismuth, and zinc, while containing essentially no lead or silicon.

Abstract: The present invention provides processes to immobilize high alkaline radioactive and/or hazardous waste in a silicate-based glass, the waste containing one or more of radionuclides, hazardous elements, hazardous compounds, and/or other compounds. The invention also provides silicate-based glass compositions for use in immobilizing radioactive and/or hazardous waste.

Abstract: An alumino-borosilicate glass for the confinement, isolation of a radioactive liquid effluent of medium activity, and a method for treating a radioactive liquid effluent of medium activity, wherein calcination of said effluent is carried out in order to obtain a calcinate, and a vitrification adjuvant is added to said calcinate.

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: Systems and processes for reducing the volume of radioactive waste materials through pyrolysis and vitrification carried out by microwave heating and, in some instances, a combination of microwave heating and inductive heating. In some embodiments, the microwave-enhanced vitrification system comprises a microwave system for treating waste material combined with a modular vitrification system that uses inductive heating to vitrify waste material. The final product of the microwave-enhanced vitrification system is a denser, compacted radioactive waste product.

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: Treatment of a radioactive waste stream is provided by adding sodium hydroxide (NaOH) and/or potassium hydroxide (KOH) together with a rapidly dissolving form of silica, e.g., fumed silica or fly ash. Alternatively, the fumed silica can be first dissolved in a NaOH/KOH solution, which is then combined with the waste solution. Adding a binder that can be a mixture of metakaolin (Al2O3.2SiO2), ground blast furnace slag, fly ash, or other additives. Adding an “enhancer” that can be composed of a group of additives that are used to further enhance the immobilization of heavy metals and key radionuclides such as 99Tc and 129I. An additional step can involve simple mixing of the binder with the activator and enhancer, which can occur in the final waste form container, or in a mixing vessel prior to pumping into the final waste form container, depending on the particular application.

Abstract: The present invention provides processes to immobilize radioactive and/or hazardous waste in a borosilicate glass, the waste containing one or more of radionuclides, hazardous elements, hazardous compounds, and/or other compounds. The invention also provides borosilicate glass compositions for use in immobilizing radioactive and/or hazardous waste.

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: Briefly described, compositions, materials including the compositions, methods of using the compositions, and methods of degrading contaminants, are described herein. The composition can include a polyoxometalate/ cationic silica material. In addition, the compositions can be made of a polyoxometalate/cationic silica material, a copper (II) salt having a weakly bound anion, and a nitrate salts. Further, the compositions can be made of a polyoxometalate/cationic silica material, a copper (II) salt having a weakly bound anion, a compound selected from tetraethylammonium (TEA) nitrate, tetra-n-butylammonium (TBA) nitrate, and combinations thereof.

Abstract: The present invention provides processes to immobilize radioactive and/or hazardous waste in a borosilicate glass, the waste containing one or more of radionuclides, hazardous elements, hazardous compounds, and/or other compounds. The invention also provides borosilicate glass compositions for use in immobilizing radioactive and/or hazardous waste.

Abstract: A process of preparing a biogenic silica comprising the steps of incinerating a silica bearing organic source at a temperature up to 1200° C. and allowing the incinerated silica organic source to cool; adding the incinerated and cooled silica bearing organic source to an alkaline solution that has either been preheated to a temperature up to about 65° C. or to be heated with the added organic source to a temperature up to about 65° C., the alkaline solution being contained in a vessel and having a pH up to 14; applying heat so that the added organic source and the alkaline solution in the vessel are at a temperature between 100° C. and up to about 300° C. for 1 to 4 hours, thereby forming an aqueous biogenic silica and undissolved impurities derived from the added organic source; and extracting the aqueous biogenic silica from the vessel. The extracted silica can be solidified into a solid form.

Abstract: A process and an apparatus for removal of radon from indoor air. The process having the step of contacting indoor air with an adsorbent, that is a silver-exchanged zeolite. The apparatus for the removal of radon from indoor air comprises a silver exchanged zeolite.

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: The present invention provides processes to immobilize radioactive and/or hazardous waste in a borosilicate glass, the waste containing one or more of radionuclides, hazardous elements, hazardous compounds, and/or other compounds. The invention also provides borosilicate glass compositions for use in immobilizing radioactive and/or hazardous waste.

Abstract: The invention relates to methods of vitrifying waste and for lowering the melting point of glass forming systems by including lithia formers in the glass forming composition in significant amounts, typically from about 0.16 wt % to about 11 wt %, based on the total glass forming oxides. The lithia is typically included as a replacement for alkali oxide glass formers that would normally be present in a particular glass forming system. Replacement can occur on a mole percent or weight percent basis, and typically results in a composition wherein lithia forms about 10 wt % to about 100 wt % of the alkali oxide glass formers present in the composition. The present invention also relates to the high lithia glass compositions formed by these methods.

Abstract: This invention relates to a method for conditioning a waste constituted of an aqueous solution of sodium hydroxide NaOH of 3 to 10 M, possibly radioactive. The method is as follows: a) a metakaolin powder is added to the aqueous solution such that a suspension is obtained capable of solidifying and forming a crystalline phase of the zeolite A type; b) the suspension is introduced into a mould; c) the suspension is left to solidify in the mould in order to obtain a moulded solid product based on zeolite A; d) the moulded product is dried; and e) the zeolite A phase is converted into a nepheline type phase by heat treatment at a temperature of 1000° C. to 1500° C.

Abstract: A process for chemical fixation of radionuclides and radioactive compounds present in soils, solid materials, sludges and liquids. Radionuclides and other radioactive compounds are converted to low-temperature Apatite-Group structural isomorphs (general composition: (AB)5(XO4)3Z), usually phosphatic, that are insoluble, non-leachable, non-zeolitic, and pH stable by contacting with a suspension containing a sulfate, hydroxide, chloride, fluoride and/or silicate source and a phosphate anion. The Apatitic-structure end product is chemically altered from the initial material and reduced in volume and mass. The end product can be void of free liquids and exhibits sufficiently high levels of thermal stability to be effective in the presence of heat generating nuclear reactions. The process occurs at ambient temperature and pressure.

Abstract: The invention relates to methods of vitrifying waste and for lowering the melting point of glass forming systems by including lithia formers in the glass forming composition in significant amounts, typically from about 0.16 wt % to about 11 wt %, based on the total glass forming oxides. The lithia is typically included as a replacement for alkali oxide glass formers that would normally be present in a particular glass forming system. Replacement can occur on a mole percent or weight percent basis, and typically results in a composition wherein lithia forms about 10 wt % to about 100 wt % of the alkali oxide glass formers present in the composition. The present invention also relates to the high lithia glass compositions formed by these methods.

Abstract: A phosphosilicate apatite useful as a confinement matrix for radioactive waste, and having the formula: MtCaxLnyHfwPuz−w(PO4)6−u(SiO4)uF2  (I) wherein: M represents an alkaline metal, Ln represents at least one cation selected from lanthanides, and t, x, y, z, w and u are such that: 0≦t≦1, 8≦x≦10, 0≦y≦1, 0<z≦0.5, 0≦w≦z, and 0<u≦y+2z, and the total number of positive charges provided by the alkaline metal, Ca, Ln, Hf and Pu cations are equal to 20+u is prepared by a sintering-reaction of a mixture of reagent powders, in a neutral or reducing atmosphere, with application of pressure before or during sintering.

Abstract: The invention relates to methods of vitrifying waste and for lowering the melting point of glass forming systems by including lithia formers in the glass forming composition in significant amounts, typically from about 0.16 wt % to about 11 wt %, based on the total glass forming oxides. The lithia is typically included as a replacement for alkali oxide glass formers that would normally be present in a particular glass forming system. Replacement can occur on a mole percent or weight percent basis, and typically results in a composition wherein lithia forms about 10 wt % to about 100 wt % of the alkali oxide glass formers present in the composition. The present invention also relates to the high lithia glass compositions formed by these methods.

Abstract: A method for remediating non-homogeneous radioactive waste to significantly reduce the waste mass/volume and to convert such waste to products that meet federal regulatory compliance standards is disclosed. High level waste (HLW) stored in underground tanks is typically a multi component mixture. After removal of the waste from the tanks or other storage areas the waste is isolated in a thermal desorption-type reaction vessel where the waste is pyrolized at pre-determined and carefully controlled temperatures, pressures, and atmospheres. This process eliminates organics, volatile metals, moisture and other low boiling temperature/high vapor pressure components and converts non-volatile waste to more stable metal oxides. Off-gas treatment systems scrub, treat and dispose of all off-gas components. A thermal desorption-type apparatus especially well suited for performing the method of the present invention is also disclosed.

Abstract: The invention relates to the containment of caesium and/or rubidium, in particular 135Cs and 137Cs in an apatitic matrix of formula: MtCaxLny(PO4)6−u(SiO4)uX in which: M represents Cs and/or Rb, Ln represents at least one trivalent cation, X represents at least one anion chosen from among 2F−, S2−, 2Cl−, 2Br−, 2I−, 2OH− and O2−, and t, x, y, and u are such that: 0<t·2.5 2·x·8 1·y·7 0·u·6 x+y+t=10 and the total number of positive charges provided by the cations M, Ca and Ln are equal to (20+u).

Abstract: The aim of the present invention is a process for preparing a mineral matrix by melting, which is implemented according to the method of direct cold crucible induction melting. The method employs a step for initiating the melting. During the initiation step, a conductive mineral load is generated, by introduction of constituent elements of the matrix, into a bath of a conductive liquid, brought by induction to a suitable temperature, in the cold crucible. The intervening conductive liquid has the property of being a liquid and an electric conductor at a temperature between &thgr;1 of less than 600° C., advantageously of between 100 and 500° C., and a temperature &thgr;2 at least equal to the temperature at which the constituent elements of the matrix melt to generate the matrix. The conductive liquid is advantageously a molten sodium hydroxide bath. The preparation of such a glass matrix is advantageously implemented within the context of a method of vitrifying radioactive waste materials.

Abstract: A treated waste has been treated so as to prevent diffusion of a substance to be disposed, of e.g., radionuclide “I”, that tends to occur when the waste is disposed of in reducing environment at an ultra-deep underground. The treated waste has a low-resolution compound containing “I”, e.g., “AgI”, and a high oxygen potential agent having a higher oxygen potential than the compound, e.g., “Fe2O3”. Ionization of the substance to be disposed, attributable to reduction of the compound, can be suppressed over a long time.

Abstract: A process for chemical fixation of radionuclides and radioactive compounds present in soils, solid materials, sludges and liquids. Radionuclides and other radioactive compounds are converted to low-temperature Apatite-Group structural isomorphs (general composition: (AB)5(XO4)3Z), usually phosphatic, that are insoluble, non-leachable, non-zeolitic, and pH stable by contacting with a sulfate, hydroxide, chloride, fluoride and/or silicate source and with a phosphate anion in either a one or two step process. The Apatitic-structure end product is chemically altered from the initial material and reduced in volume and mass. The end product can be void of free liquids and exhibits sufficiently high levels of thermal stability to be effective in the presence of heat generating nuclear reactions. The process occurs at ambient temperature and pressure.

Abstract: Organic materials are mixed with metal oxide, such as hydrated metal oxides, prior to or during heat treatments in aerated or oxygenated environments to stabilize thermal decomposition or incineration of the organic materials and to suppress the emission of volatile, hazardous organic compounds. The organic materials may be ion exchange resins and polymeric sorbents, for example, and include contaminated materials such as hazardous wastes. The hydrated metal oxides may be hydrated ferric oxide, hydrated aluminum oxide or hydrated titania oxide, for examples. Ferrihydrite is preferred. The heat treatment may be a preparation for a waste disposal process, such as immobilization in ferric oxide, cement, concrete, a polymer, bitumen or glass, for example. Immobilization processes in ferric oxide are also discussed, including the use of additives such as magnesium oxide, ammonium dihydrogen phosphate and phosphoric acid, enabling consolidation at room temperature and pressures less than 15,000 psi.

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: The invention relates to a method of manufacturing compounds of the Monazite type, doped or not doped with actinides, to a method of packaging radioactive waste, high in actinides and in lanthanides by incorporating this waste in a confining matrix based on Monazite, and to a block for the packaging of radioactive waste that includes a Monazite matrix containing the radioactive elements. This method includes mixing, in the solid phase, reactants comprising an inactive compound of the lanthanide metaphosphate type Ln (PO.sub.3).sub.3 and one or more lanthanide oxides and/or one or more compounds capable of reacting with this oxide or these oxides during a thermal sintering process; the shaping of the mixture thus obtained, and the reaction sintering of said formed mixture, as a result of which a Monazite or a compound of the Monazite type is obtained.

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 process for chemical fixation of radionuclides and radioactive compounds present in soils, solid materials,sludges and liquids. Radionuclides and other radioactive compounds are converted to low-temperature Apatite-Group structural isomorphs (general composition: (AB).sub.5 (XO.sub.4).sub.3 Z), usually phosphatic, that are insoluble, non-leachable, non-zeolitic, and pH stable by contacting with a sulfate, hydroxide, chloride, fluoride and/or silicate source and with a phosphate anion in either a one or two step process. The Apatitic-structure end product is chemically altered from the initial material and reduced in volume and mass. The end product can be void of free liquids and exhibits sufficiently high levels of thermal stability to be effective in the presence of heat generating nuclear reactions. The process occurs at ambient temperature and pressure.

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 immobilizing waste chlorides salts containing radionuclides and hazardous nuclear material for permanent disposal, and in particular, a method for immobilizing waste chloride salts containing cesium, in a synthetic form of pollucite. The method for synthesizing pollucite from chabazite and cesium chloride includes mixing dry, non-aqueous cesium chloride with chabazite and heating the mixture to a temperature greater than the melting temperature of the cesium chloride, or above about 700.degree. C. The method further comprises significantly improving the rate of retention of cesium in ceramic products comprised of a salt-loaded zeolite by adding about 10% chabazite by weight to the salt-loaded zeolite prior to conversion at elevated temperatures and pressures to the ceramic composite.

Abstract: The invention relates to a process for the conditioning of radioactive waste using silicated apatites as the confinement matrix.This process consists of incorporating the waste (1) into a phosphosilicated apatite-based confinement matrix (3) e.g. complying with the formula:M.sub.t Ca.sub.x Ln.sub.y A.sub.z (PO.sub.4).sub.u (SiO.sub.4).sub.6-u X (I)in which M is an alkali metal, Ln a rare earth, A an actinide, X is S.sup.2-, 2F.sup.-, 2Cl.sup.-, 2Br.sup.-, 2I.sup.- or 2OH.sup.- and u is between 0 and 6.

Abstract: A method for reprocessing metal parts that are radioactively contaminated with uranium includes smelting the metal parts so that a melt and a slag are formed. U.sub.235 -depleted uranium is admixed with the metal parts and/or the melt and/or the slag. It is contemplated for the U.sub.235 -depleted uranium to be admixed in the form of uranium glass.

Abstract: The invention relates to the conditioning or packaging of radioactive iodine, particularly iodine 129, using an apatite as the confinement matrix. Having the iodine, said apatite corresponds to the formula:M.sub.10 (XO.sub.4).sub.6-6x (PO.sub.4).sub.6x I.sub.2 (I)in which M represents Cd or Pb, X represents V or As, I is the radioactive iodine to be conditioned and x is such that 0.ltoreq.x<1. This iodoapatite (1) can be surrounded by an apatite (3) not containing iodine serving as a physical barrier.The iodoapatite can be obtained from a solid compound of the iodine, e.g. an iodide such as silver iodide or lead iodide, by reaction with a compound of formula:M.sub.3 (XO.sub.4).sub.2-2x (PO.sub.4).sub.2x (II)orM.sub.10 (XO.sub.4).sub.6-6x (PO.sub.4).sub.6x Y.sub.2 (III)in which M, X and x are as defined hereinbefore and Y can represent OH, F, Cl or O.sub.1/2.

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: A method for cleaning contaminated surfaces or for cleaning bulk contamination of hydrocarbons or chemicals. To clean hydrocarbon or chemical contaminated surfaces, a basic aqueous silica solution is sprayed onto the contaminated surface and allowed to dry. The resulting dry material will flake off, leaving a cleaned surface, without damaging the surface. To clean bulk contamination of hydrocarbons or chemicals, the basic silica solution is mixed with hydrocarbons or chemicals and then an acidic aqueous polymer solution is added and mixed. An amorphous silica material is immediately formed which permanently encapsulates the hydrocarbons or chemicals and which dries to an inert powder.

Abstract: This invention provides a process wherein hazardous or radioactive wastes in the form of liquids, slurries, or finely divided solids are mixed with finely divided glassformers (silica, alumina, soda, etc.) and injected directly into the plume of a non-transferred arc plasma torch. The extremely high temperatures and heat transfer rates makes it possible to convert the waste-glassformer mixture into a fully vitrified molten glass product in a matter of milliseconds. The molten product may then be collected in a crucible for casting into final wasteform geometry, quenching in water, or further holding time to improve homogeneity and eliminate bubbles.