Abstract: Process for treating compositions containing uranium and plutonium, including spent nuclear fuel, are provided.

Abstract: The invention relates to a method for producing a radioactive brachytherapy source material comprising indium-114m in radioactive equilibrium with indium-114 as main radioactive isotopes. A new radioactive brachytherapy source material comprises indium-114m in radioactive equilibrium with indium-114 as main radioactive isotopes. A new encapsulated radioactive brachytherapy source comprises the new radioactive brachytherapy source material.

Abstract: A method of stabilizing nuclear material is disclosed. Oxides or halides of actinides and/or transuranics (TRUs) and/or hydrocarbons and/or acids contaminated with actinides and/or TRUs are treated by adjusting the pH of the nuclear material to not less than about 5 and adding sufficient MgO to convert fluorides present to MgF2; alumina is added in an amount sufficient to absorb substantially all hydrocarbon liquid present, after which a binder including MgO and KH2PO4 is added to the treated nuclear material to form a slurry. Additional MgO may be added. A crystalline radioactive material is also disclosed having a binder of the reaction product of calcined MgO and KH2PO4 and a radioactive material of the oxides and/or halides of actinides and/or transuranics (TRUs). Acids contaminated with actinides and/or TRUs, and/or actinides and/or TRUs with or without oils and/or greases may be encapsulated and stabilized by the binder.

Abstract: The invention relates to a process for the preparation of a product based on a phosphate of at least one element M(IV), for example of thorium and/or of actinide(IV)(s). This process comprises the following stages: a) mixing a solution of thorium(IV) and/or of at least one actinide(IV) with a phosphoric acid solution in amounts such that the molar ratio PO 4 M ? ? ( IV ) ?is from 1.4 to 2, b) heating the mixture of the solutions in a closed container at a temperature of 50 to 250° C. in order to precipitate a product comprising a phosphate of at least one element M chosen from thorium(IV) and actinide(IV)s having a P/M molar ratio of 1.5, and c) separating the precipitated product from the solution. The precipitate can be converted to phosphate/diphosphate of thorium and of actinide(s). The process also applies to the separation of uranyl ions from other cations.

Abstract: A ceramic waste immobilizing material for the encapsulation of high level radioactive waste (HLW), e.g. resulting from the reprocessing of irradiated nuclear fuel. The ceramic waste immobilising material enables waste ions from at least fission products in irradiated nuclear fuel to be dissolved in substantially solid solution form. The ceramic waste immobilising medium has a matrix comprising phases of hollandite, perovskite and zirconolite in which the waste ions are dissolved. The invention also includes a method of immobilizing HLW from reprocessed nuclear fuel assemblies comprising the steps of mixing a liquor containing the HLW with a precursor material comprising oxides or oxide precursors of at least titanium, calcium and barium to form a slurry, drying the slurry, and calcining the dried slurry under a reducing atmosphere to form a powder comprising 30–65 weight % waste.

Abstract: A reactor coolant system of a pressurized water nuclear reactor with fuel assemblies in the core is simultaneously shutdown and decontaminated in less than 90 hours after the shutdown is initiated. A LOMI or Can-Derem decontamination reagent is added to reactor coolant to reduce iron and nickel in oxidized coatings before removing dissolved hydrogen and reducing the gamma emitting activity of the reactor coolant.

Abstract: An adhesive containing a far infrared radiation ceramic powder emitting far infrared rays and a radiation source ceramic powder emitting radiations and anions. The radiation source ceramic powder includes silicon dioxide, aluminum oxide, iron oxide, titanium oxide, calcium oxide, magnesium oxide, potassium oxide, sodium oxide and zirconium and/or radium. The adhesive according to the present invention relaxes human beings, helps spontaneous recovery from diseases and improves health by the synergistic effects of far infrared rays, anions and radiations.

Abstract: A gamma radiation source comprising selenium-75 or a precursor therefore, wherein the selenium is provided in the form of one or more thermally stable compounds, alloys, or mixed metal phases.

Abstract: Preventing incomplete combustion of fuel in a heat apparatus and equipment.

Abstract: A method for associating information with an article, an isotopic labeling composition to label an article with information using at least two different isotopes of an element, and an article labeled with the labeling composition. In the labeling composition, the isotopes of the labeling composition have an abundance ratio that is detectably different from the natural abundance ratio thereof. By detecting the abundance ratio(s) of the isotopes in the labeling composition, via laser ablation/magnetic spectroscopy, an NQR spectrometer, an NMR spectrometer, an IR spectrometer, or a microwave spectrometer, information about the article can be determined. The method and labeling composition may be used to identify, authenticate or determine the source or origin of an article or to provide detailed information about an article.

Abstract: A method of preparing high-specific-activity 195mPt includes the steps of: exposing 193Ir to a flux of neutrons sufficient to convert a portion of the 193Ir to 195mPt to form an irradiated material; dissolving the irradiated material to form an intermediate solution comprising Ir and Pt; and separating the Pt from the Ir by cation exchange chromatography to produce 195mPt.

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: Cesium dispensers based on the use of a mixture between a reducing agent and a cesium compound selected among molibdate, tungstate, niobate, tantalate, silicate and zirconate are described. Some processes for the use of these dispensers are also described.

Abstract: A process for the treatment of radioactive graphite which includes the following steps: (i) reacting the radioactive graphite at a temperature in the range of from 250° C. to 900° C. with superheated steam or gases containing water vapor to form hydrogen and carbon monoxide; (ii) reacting the hydrogen and carbon monoxide from step (i) to form water and carbon dioxide; and (iii) reacting the carbon dioxide of step (ii) with metal oxides to for carbonate salts. The process enables radioactive graphite, such as graphite moderator, to be treated either in-situ or externally of a decommissioned nuclear reactor.

Abstract: Disclosed is a composition of matter comprising a tributyl phosphate complex of a group 3, lanthanide, actinide, or group 13 salt in an organic carrier and a method of making the complex. These materials are suitable for use in solid or liquid organic scintillators, as in x-ray absorption standards, x-ray fluorescence standards, and neutron detector calibration standards.

Abstract: The present invention relates to a method for associating information with an article, an isotopic labeling composition to label an article with information using at least two different isotopes of an element, and an article labeled with the labeling composition. In the labeling composition, the isotopes of the labeling composition have an abundance ratio that is detectably different from the natural abundance ratio thereof. By detecting the abundance ratio(s) of the isotopes in the labeling composition, via laser ablation/magnetic spectroscopy, an NQR spectrometer, an NMR spectrometer, an IR spectrometer, or a microwave spectrometer, information about the article can be determined. The invention may be used to identify, authenticate or determine the source or origin of an article or to provide detailed information about an article.

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: Locally deposited polymer depots are used as a vehicle for the immobilization and local delivery of a radionuclide or radiopharmaceutical. Radionuclides are incorporated in their elemental forms, as inorganic compounds, or are attached to a larger molecule or incorporated into the polymer, by physical or chemical methods. Ancillary structure may be employed to control the rate of release. Standard radionuclides which have been used for local radiotherapy may be used, such as radionuclides of iodine, iridium, radium, cesium, yttrium or other elements.

Abstract: A method of producing an R--Fe--B-based, sintered permanent magnet, wherein R is at least one rare earth element including Y, having a small oxygen content. A coarse alloy powder prepared by a reductive diffusion method is milled and recovered into a solvent to form a slurry. The slurry is wet-compacted to form a green body which is then sintered after removing the solvent. The milling, recovering, wet-compacting, solvent-removing and sintering steps are carried out while preventing the powder, slurry and green body from being brought into contact with air to minimize the oxygen content in the final sintered permanent magnet. The sintered permanent magnet produced has a high density and a high magnetic properties due to a low oxygen content.

Abstract: Disclosed is a ceramic composition for the immobilization of actinides, particularly uranium and plutonium. The ceramic is a titanate material comprising pyrochlore, brannerite and rutile.

Abstract: Additives are proposed for compositions comprising radiolabelled organic compounds e.g. 32P-labelled nucleotides. Stabilizers are selected from tryptophan, para-aminobenzoate, indoleacetate and the azole group. Dyes are selected from Sulphorhodamine B, Xylene Cyanol, Azocarmine B and New Coccine. Preferred compositions contain both stabilizer and dye.

Abstract: The present invention provides a process of encapsulating depleted uranium by forming a homogenous mixture of depleted uranium and molten virgin or recycled thermoplastic polymer into desired shapes. Separate streams of depleted uranium and virgin or recycled thermoplastic polymer are simultaneously subjected to heating and mixing conditions. The heating and mixing conditions are provided by a thermokinetic mixer, continuous mixer or an extruder and preferably by a thermokinetic mixer or continuous mixer followed by an extruder. The resulting DUPoly shapes can be molded into radiation shielding material or can be used as counter weights for use in airplanes, helicopters, ships, missiles, armor or projectiles.

Abstract: A method of encapsulating mixed waste in which a thermoplastic polymer having a melting temperature less than about 150.degree. C. and sulfur and mixed waste are mixed at an elevated temperature not greater than about 200.degree. C. and mixed for a time sufficient to intimately mix the constituents, and then cooled to a solid. The resulting solid is also disclosed.

Abstract: The method for treating ignitable cutting swarf in accordance with the present invention involves collecting cutting swarf in a casting mold underwater and injecting a binder mixture comprising vinyl ester styrene into the vessel to fill void volume; and form a mixture comprising swarf and vinyl ester styrene; and curing the mixture. The method is especially useful for stabilizing the ignitable characteristics of radioactive zirconium cutting swarf, and can be used to solidify zirconium swarf, or other ignitable finely divided material, underwater. The process could also be performed out of water with other particulate wastes.

Abstract: The present invention discloses a method of creating a monolithic wasteform consisting of a binder which chemically immobilizes heavy metals and radioactive materials so as to render them environmentally safe. An apatite or apatite-like material may be employed in immobilizing the hazardous material. A preferred practice of the invention employs a hydroxyapatite or a calcium depleted hydroxyapatite into which the waste materials are substituted and immobilized. The stoichiometric apatite or calcium deficient hydroxyapatite may be formed in the aqueous solution containing heavy metals or radioactive materials, or both, wherein binding of the latter is effected. Alternatively, a preformed calcium deficient phosphate may be introduced into the solution having heavy metals or radioactive materials, or both, dissolved therein in effecting the desired binding in situ. A high strength monolithic wasteform which may be stored or buried for long-term, safe storage of the hazardous materials is produced.

Abstract: Additives are proposed for compositions comprising radiolabelled organic compounds e.g. 32P-labelled nucleotides. Stabilisers are selected from tryptophan, para-aminobenzoate, indoleacetate and the azole group. Dyes are selected from Sulphorhodamine B, Xylene Cyanol, Azocarmine B and New Coccine. Preferred compositions contain both stabiliser and dye.

Abstract: A method of synthesizing 9-cis-retinoic acid, all-trans-retinoic acid or 9-nor-retinoic acid is disclosed. The method comprises the steps of adding a Grignard reagent of ##STR1## to 2,2,6 trimethyl cyclohexanone is disclosed. R is a methyl group or H and the CH.sub.2 --OH group is in either the cis or trans orientation relative to the HC.tbd.C- group. The resulting product is converted into retinoic acid. In the preferable form of the present invention, a tritium-labelled retinoic acid is synthesized, wherein the labelling is at the C.sub.20 position. A preparation of tritium-labelled 9-cis-retinoic acid with a specific activity of greater than 65 Ci/mmol is also enclosed. In a most preferred embodiment, the specific activity is greater than 75 Ci/mmol.

Abstract: An article, such as a containment system (10), having sides (12) with walls (2) or (24) is made; in one method by using cast, cooled, melted, radioactive metal components where the melted metal has a specific activity over 130 Bq/g; or by providing a contaminated material in the form of a solid, liquid or mixture, and then mixing the contaminated material, to which no more than about 15 weight % of uncontaminated material has been reacted, with a binder, followed by forming the composition into a containment system and then curing it into a mass which contains both contaminated material, and uncontaminated binder acting as a matrix for the contaminated material. This article need not be a containment system but can be a wide variety of objects which are made out of radioactive waste, hazardous waste, and their mixtures.

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: 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: Additives are proposed for compositions comprising radiolabelled organic compounds e.g. 32P-labelled nucleotides. Stabilizers are selected from tryptophan, para-aminobenzoate, indoleacetate and the azole group. Dyes are selected from Sulphorhodamine B, Xylene Cyanol, Azocarmine B and New Coccine. Preferred compositions contain both stabilizer and dye.

Abstract: Additives are proposed for compositions comprising radiolabelled organic compounds e.g. 32P-labelled nucleotides. Stabilizers are selected from tryptophan, para-aminobenzoate, indoleacetate and the azole group. Dyes are selected from Sulphorhodamine B, Xylene Cyanol, Azocarmine B and New Coccine. Preferred compositions contain both stabilizer and dye.

Abstract: Novel compounds obtainable by reacting together an imido-reagent such as diphenylphosphonimido-triphenylphosphorane), or a phosphine oxide such as p-tolyldiphenylphosphine oxide, with a chelate of a transition or lanthanide or actinide metal, such as tris(dibenzoylmethide)europium III, have the property of fluorescing in UV radiation. The invention includes solid polymer bodies containing such compounds, or chelates of transition or lanthanide or actinide metals generally, the bodies having the property of emitting light or infra-red radiation when subjected to a flux of ultra-violet or ionising radiation by virtue of internally generated, e.g. by tritium ionising radiation. The body is preferably of polystyrene formed by polymerising the monomer in the presence of the compound or metal chelate.

Abstract: The present invention provides a composition and process for disposal of radioactive, hazardous and mixed wastes. The present invention preferably includes a process for multibarrier encapsulation of radioactive, hazardous and mixed wastes by combining substantially simultaneously dry waste powder, a non-biodegradable thermoplastic polymer and an anhydrous additive in an extruder to form a homogenous molten matrix. The molten matrix may be directed in a "clean" polyethylene liner, allowed to cool, thus forming a monolithic waste form which provides a multibarrier to the dispersion of wastes into the environment.

Abstract: This specification presents methods of containing/absorbing alpha, beta, gamma, X-ray, and neutron radiation using Fullerene molecules employing the resonant relativistic absorption phenomena based on a frequency dependant Doppler effect. Radioactive atoms, ions, and molecules (X.sub.rad) are encapsulated in a variety of Fullerene molecules (C.sub.60, onions, nanotubes, and capsules). The resulting radioactive material-holding Fullerene complexes (X.sub.rad @C.sub.n) will either decrease the intensity of escaping internally-generated radioactive emissions or, in certain optimal cases, absorb and/or contain all such internally-generated radioactive emissions which occur as the radioactive material decays.

Abstract: Anions of the formula (I):[DA.sub.5 M.sub.30-x O.sub.110-x (M'L).sub.x ].sup.m- (I)in which D is Na.sup.+, Ca.sup.2+ ; A is P, As, Sb, Si, Ge, or combinations thereof, M is W.sup.5+, W.sup.6+, or mixtures thereof; M' is a metallic element from groups 2 to 15 of the periodic table; other than W; L is O.sup.2-, OH.sup.-, H.sub.2 O; x is 0-10; and m is 10-20; selectively react with cations Z.sup.n+ to afford anions of the formula (II):[ZA.sub.5 M.sub.30-x O.sub.110-x (M'L).sub.x ].sup.(m+1-n)-(II)wherein n is 3 or 4; Z=Sm, Eu, Gd, Tb, Dy, Ho, Er, Tm, Yb, Lu, Y, or Bi, when n=3, and Z=Ce, U, Np, Pu, or Am, when n =4. This reaction may be used for the selective encapsulation of lanthanide or actinide cations, and salts containing anions of formula (II) may be vitrified to form glasses or reduced to form tungsten "bronze" materials suitable for the long-term storage of radioactive lanthanides or actinides.

Abstract: Disclosed is a method for converting spent nuclear fuel and surplus plutonium into a vitreous ceramic final waste form wherein spent nuclear fuel is bound in a crystalline matrix which is in turn bound within glass.

Abstract: A method for disposing of waste material employs an agglomerate formed by molding an admixture of waste material and thermosetting binder. The use of a thermoplastic resin sheet in conjunction with the agglomeration mold promotes the safety of the molding process. Dust and mold leakage is abated and it subsequently yields a resin coated agglomerate that is safe for handling. The performance of the agglomerate is enhanced by formation of a coating of resin chemically bonded onto its surface. The performance of the agglomerate may be further enhanced by the formation of a seam-free thermoplastic resin jacket over the resin coated agglomerate.

Abstract: A compound and method of making a compound for use as a diagnostic or therapeutic pharmaceutical comprises either a phosphorous or germanium core and at least two hydrazine groups forming a ligand for bonding to a metal extending from the phosphorous or germanium core.

Abstract: Methods for the synthesis of 9-cis monotritium-labeled retinoids, and their use in the discovery of Retinoid X Receptor ligands are provided. In addition, 9-cis monotritium-labeled retinoids, as well as novel intermediates and tritium-labeled intermediates formed during the synthesis of 9-cis monotritium-labeled retinoids are also provided.

Abstract: Novel compounds obtainable by reacting together an imido-reagent such as diphenylphosphonimidotriphenylphosphorane) with a chelate of a transition or lanthanide or actinide metal, such as tris(dibenzoylmethide) europium III, has the property of fluorescing in UV radiation. The invention includes solid polymer bodies containing such compounds, or chelates of transition or lanthanide or actinide metals generally, the bodies having the property of emitting light by virtue of internally generated, e.g. by tritium ionising radiation. The body is preferably of polystyrene formed by polymerising the monomer in the presence of the compound or metal chelate.

Abstract: A process for treating alkaline wastes for vitrification. The process involves acidifying the wastes with an oxidizing agent such as nitric acid, then adding formic acid as a reducing agent, and then mixing with glass formers to produce a melter feed. The nitric acid contributes nitrates that act as an oxidant to balance the redox of the melter feed, prevent reduction of certain species to produce conducting metals, and lower the pH of the wastes to a suitable level for melter operation. The formic acid reduces mercury compounds to elemental mercury for removal by steam stripping, and MnO.sub.2 to the Mn(II) ion to prevent foaming of the glass melt. The optimum amounts of nitric acid and formic acid are determined in relation to the composition of the wastes, including the concentrations of mercury (II) and MnO.sub.2, noble metal compounds, nitrates, formates and so forth.

Abstract: A method of containing hazardous and toxic wastes includes the steps of irporating the dried waste, in a salt form, in melted polymer, such as asphalt, and forming the waste salt and asphalt blend into aggregate pellets. The pellets are coated with a powdered coating material that is compatible with a portland cement-based mortar or other cementitious material which is used. The coated particles are mixed with mortar to form a polymer-aggregate concrete and cast into wasteforms for storage or burial. If it is desirable to produce a waste form with a continuous layer of mortar on the exterior of the concrete monolith the mold can be placed on a turntable and spun, or otherwise exposed to a centrifugal force to force the mortar to the outside of the mold. Centrifugal separation is possible because the polymer-waste mixture typically has a specific gravity near 1.5 while that of the cementitious mixture is typically greater than 2.0.

Abstract: Environmental pollution stemming from the industrial discharge and/or storage of water-soluble thorium compounds is avoided by converting same into essentially innocuous water-insoluble thorium phosphates, notably orthorhombic thorium phosphates, by (i) reacting such water-soluble thorium compounds, e.g., the nitrates and/or chlorides, with a base, for example aqueous ammonia, in an aqueous reaction medium, to precipitate a thorium hydroxide therein, (ii) next reacting the precipitate thus formed with a phosphating compound, e.g., phosphoric acid or a soluble phosphate salt, also in an aqueous reaction medium, to precipitate a thorium phosphate therein, and then (iii) separating such thorium phosphate precipitate.

Abstract: A process for determining the suitability of soil washing for various types of soils, sludges and other solids is disclosed. The process may be applied to relatively small soil samples which have been contaminated in order to determine the suitability and economics for treating the tested soil using a full-scale soil washing process. The process involves the steps of identifying the contaminated particle size ranges contained in the soil sample, identifying an effective extractant for removing the contaminant of interest, and identifying an effective leachate treatment approach for the particular soil sample of interest.

Abstract: Benzalkonium chloride and benzethonium chloride are each useful in radiopharmaceutical preparations as bacteriostatic agents which are compatible with anti-oxidants.

Abstract: The present invention provides conjugates formed from calcified tissues targeting agents and radiolabeled compounds. One such conjugate comprises a chelate and a targeting agent that is capable of associating with calcified tissue, wherein the chelate contains at least one nitrogen atom or at least one sulfur atom or combinations thereof as the donor atoms.Another aspect of the invention provides method for using the conjugates for diagnostic and therapeutic purposes, including those related to bone cancer.

Abstract: A stabilized radionuclide-colloid composition useful in therapeutic radiation ablation therapies is disclosed. The composition contains a viscosity modifier layered mixed metal hydroxide and optionally an ion exchange medium to stabilize the radioactive colloid.

Abstract: Radioactive high molecular weight metal-binding protein compositions and a method for therapeutic radiation treatment including the treatment of rheumatoid arthritis comprising injection of a radioactive high molecular weight metal-binding protein compositions are disclosed.

Abstract: Novel cementitious containers for storage of hazardous waste are disclosed having an inner layer of substantially unhydrated cement in contact with the hazardous waste and an outer layer of hydrated cement. Cementitious hazardous waste containers may be prepared by compressing powdered hydraulic cement around solid hazardous waste materials and then hydrating an outer layer of the powdered hydraulic cement. An inner layer of powdered hydraulic cement remains unhydrated and capable of reacting with any water which might breach the outer layer or originate with the hazardous waste itself. The inner layer of powdered hydraulic cement is also capable of reacting with any carbon dioxide or carbon monoxide generated by decomposition of organic waste materials.