Class / Patent application number | Description | Number of patent applications / Date published |
588018000 | Chemical conversion to a stable solid for disposal | 23 |
20080228022 | Vacuumable Gel for Decontaminating Surfaces and Use Thereof - The present invention relates to a vacuumable gel that can be used for decontaminating surfaces, and also to the use of this gel. The decontamination may be, for example, a radioactive decontamination. The gel of the present invention is composed of a colloidal solution. It comprises from 5 to 25 wt % of an inorganic viscosity modifier relative to the total weight of the gel; from 0.01 to 0.2 wt % of a surfactant relative to the total weight of the gel, and, particularly preferably, a surfactant in an amount strictly below 0.1 wt % relative to the total weight of the gel; from 0.5 to 7 mol, per litre of gel, of an inorganic acid or base; and optionally from 0.05 to 1 mol, per litre of gel, of an oxidizer having a standard redox potential E | 09-18-2008 |
20090005628 | Reuse method of radioactive waste salt and the apparatus thereof - A reuse apparatus of eutectic salt waste produced in an electro refining process and a method thereof is a technology that in order to collect the eutectic salt of the eutectic salt waste, oxidizes/precipitates nuclides (rare earth and TRU) within the eutectic salt waste, an oxygen dispersing method is used to perform a layer separation into the eutectic salt layer and the precipitate layer. Then, the precipitate layer and eutectic salt layer are separated and collected, so that the eutectic salt layer is directly reused and the eutectic salt within the precipitates is reused by separating and collecting it using distillation/condensation processes. The reuse apparatus of the eutectic salt waste and a method thereof thereby increases the collecting efficiency of the eutectic salt and allows the compositions of the collected eutectic salt to have the same compositions as the eutectic salt used in the electro refining process. | 01-01-2009 |
20090093664 | Carbon nanotubes using for recovery of radionuclides and separation of actinides and lanthanides - Methods and compositions to extract radionuclides such as various actinides and lanthanides from organic and/or aqueous solutions by utilizing extractant functionalized carbon nanotubes are disclosed. More particularly, phosphorous-containing (such as phosphine oxides, phosphoric acids or phosphates) organic extractants and other predesigned extractants (such as crown ethers, calncrown derivatives, malonamide and diglycolamide derivatives, polyethylene glycol derivatives, cobalt dicarbollite derivatives, and N-donating heterocyclic ligands) can be covalently and/or non-covalently employed on the surfaces and/or ends (tips) of carbon nanotubes for the purpose of removal radionuclides such as various actinides and lanthanides from organic and/or aqueous solutions. Extractant functionalized carbon nanotubes can be used for extracting radioactive nuclides from nuclear waste or spent nuclear fuel, which are produced and/or reprocessed from the nuclear power generation or other nuclear application. The invention also relates to the solid-liquid separation process based on the contact of liquid radioactive waste by using the invention extracting agents as the solid phase. | 04-09-2009 |
20100234664 | CARBONACEOUS RADIOACTIVE WASTE TREATMENT - The invention relates to the treatment of carbon-containing radioactive waste. It particularly envisages:
| 09-16-2010 |
20100305384 | Process for Converting Alkaline-Earth Metal Chlorides to Tungstates and Molybdates and Applications Thereof - The invention relates to a process for converting an alkaline-earth metal chloride to at least one salt chosen from the tungstates and molybdates of this metal, which comprises the reaction of the alkaline-earth metal chloride with at least one precursor of tungsten or of molybdenum chosen from tungsten oxides, molybdenum oxides, tungstates and molybdates, this reaction being carried out in a solvent constituted by KCl or by an LiCl/KCl mixture and at a temperature at least equal to the melting point of this solvent. | 12-02-2010 |
20120088949 | Ion Exchange Regeneration and Nuclide Specific Selective Processes - A method of processing ion exchange resin radioactive waste, wherein the radioactive waste contains a plurality of fractions of radioactive waste based on density, which may include cation resin waste and anion resin waste, wherein at least one of the plurality of fractions comprises a total concentration of at least one radionuclide, including performing at least one of the following operations (i), (ii) or (iii): (i) separating the at least one of the plurality of fractions from the radioactive waste utilizing a moving freeboard; (ii) separating the radioactive waste into cation resin waste and anion resin waste; or (iii) removing at least a portion of the total concentration of the at least one radionuclide from: the radioactive waste; the at least one of the plurality of fractions separated by the moving freeboard; or at least one of the radioactive waste, the cation resin waste or the anion resin waste. | 04-12-2012 |
20120101324 | DESTRUCTION OF MIXED RADIOACTIVE WASTE BY CATALYZED CHEMICAL OXIDATION - Described are method of treating a radioactive organic waste stream comprising:
| 04-26-2012 |
20120165594 | SOLIDIFICATION METHOD OF RADIOACTIVE WASTE ACCOMPANYING CHLORIDE RECYCLING OR RADIOACTIVE IODIDE REMOVING AND THE DEVICE THEREOF - The present invention relates to a method and apparatus for solidifying radioactive waste accompanying chlorine recycling or radioactive iodine removal. The present invention provide a method and apparatus for treating radioactive waste composed of volatile metal halide with high corrosiveness at a high temperature through a solidifying system including crushing, mixing/dehalogenating and sintering. In the inventive method and apparatus for solidifying radioactive waste, a dechlorination process by using a dehalogenation material is performed on highly corrosive metal salt under an oxidizing atmosphere by using a method of controlling a temperature on the surface of a reactor, and solidification is carried out by removing radioactive iodine while reusing chlorine contained in an exhaust gas. Accordingly, the generated amount of total waste can be reduced, and therefore the inventive method and apparatus can be usefully used in preparing a solidified body with high durability. | 06-28-2012 |
20130289329 | DECONTAMINATION METHOD OF CLADDING HULL WASTES GENERATED FROM SPENT NUCLEAR FUEL AND APPARATUS THEREOF - The present disclosure relates to a decontamination method and apparatus for cladding hull wastes of spent nuclear fuels, capable of decontaminating a small quantity of spent nuclear fuels remaining on surfaces of the cladding hull wastes and radioactive fission products penetrated into the cladding hulls through an electrochemical dissolution. The method includes inserting the cladding hull waste into an anodic basket, immersing a reference electrode and a cathodic electrode as well as the anodic basket in a molten salt, dissolving a surface of the cladding hull waste by applying a voltage or current to the anodic basket with respect to the cathodic electrode or the reference electrode, removing the anodic basket, and removing a salt remaining on the surface of the cladding hull waste. | 10-31-2013 |
20140309473 | METHOD FOR TREATING A CLADDING CONTAINING SINTERED CALCIUM HYDRIDE - A method for treating a cladding within which there is a sintered material composed wholly or partly of sintered calcium hydride, the method comprising a step during which the sintered material is contacted with a reaction mixture comprising steam, carbon dioxide, and a chemically inert gas, the contacting being carried out for a duration allowing the sintered calcium hydride to be converted into a calcium carbonate powder. | 10-16-2014 |
20140378734 | Radioactive Organic Waste Treatment Method and System - Disclosed is a method for treating a radioactive organic waste, the radioactive organic waste including a cation exchange resin adsorbing radionuclide ions, the method including the step of bringing the radioactive organic waste into contact with an organic acid salt aqueous solution containing an organic acid salt and whereby desorbing the radionuclide ions from the cation exchange resin, in which the organic acid salt contained in the organic acid salt aqueous solution includes a cation that is more readily adsorbable by the cation exchange resin than hydrogen ion is. This enables reduction in concentration of a radioactive substance in the radioactive organic waste and reduction in amount of a high-dose radioactive waste. | 12-25-2014 |
20150310951 | Integrated Method And Apparatus For Remediation Of Uranium-Contaminated Soils - Apparatus and method are provided for the treatment of uranium-contaminated soil by using comprehensive joint technology. The apparatus include the pumping system, the electrokinetic remediation system, elution system, remediation-separation system and recharge system. The remediation technologies (i.e. chemical, photolysis and electrokinetic) are used to remedy the uranium-contaminated soil. First, extract uranium from the contaminated areas and make the ionized uranium extract from the soil phase to the solution phase. Then, use the electrokinetic remediation technology to drive uranium enrichment electromigrate to near the anode. Finally, return the repaired-soil and groundwater back to anode area and recharge well, respectively. This comprehensive joint apparatus can reduce the uranium volume in the contaminated soil or water, and recycle the obtained uranium, which are cleaning processes and have no secondary pollution. | 10-29-2015 |
20160141059 | METHOD AND PLANT FOR THE WET-ROUTE OXIDATION TREATMENT OF HAZARDOUS ORGANIC WASTE, NOTABLY RADIOACTIVE WASTE, CONTAINING MINERAL FILLERS - A method and plant for wet-route oxidation treatment of hazardous organic waste products, notably radioactive wastes, which may contain mineral fillers, the waste products being treated in a secure environment. The plant comprises a closed space, with a mechanism for bringing a volume of hazardous organic waste products containing mineral fillers, adding a given quantity of water mixed with a base to the predetermined volume in order to adjust the pH to a determined value so as to make a solution and/or a liquid suspension, with a pressure reactor and with mechanism for transferring the solution and/or liquid suspension into the pressure reactor, and a device for introducing an oxygen atmosphere into the pressure reactor and for pressurizing the atmosphere. A heating mechanism is provided for subjecting the contents of the pressure reactor to heat treatment at a temperature between 150 and 350° C. to complete the wet-route oxidation. | 05-19-2016 |
20160163405 | METHOD FOR TREATING AN ABSORBER PIN CONTAINING CONTAMINATED BORON CARBIDE AND SODIUM - Disclosed is a method for treating an absorber pin, wherein the pin comprises a cladding in which a sintered boron carbide-based material having cracks is located, the material having porosity less than 1% of the volume of the material, the cracks containing sodium and at least one radioactive material. The method includes contacting the material with a treatment reaction mixture including carbon dioxide and water, in such a manner that the production of sodium carbonate and the expansion thereof cause the opening of cracks and of the sheath from at least one slit provided in the sheath as well as the propagation of the treatment process within the material. The process overcomes the physical-chemical properties of a sintered boron carbide-based material as much as possible. These properties prevent an easy treatment of the sodium and radioactive material contained in the cracks of the material. | 06-09-2016 |
588019000 | Incineration, calcination, pyrolyzing to obtain solid residue | 9 |
20080214886 | EVAPORATOR/CALCINER - Disclosed herein is provided an evaporator/calciner in which hazardous materials, such as radioactive liquids, are converted into chemically stable, solid forms by evaporating, drying and calcination within a single vessel, that can then be sealed and used for long term storage. | 09-04-2008 |
20110319699 | CARBONACEOUS RADIOACTIVE WASTE TREATMENT - The invention relates to the treatment of carbon-containing radioactive waste. It particularly envisages: | 12-29-2011 |
20120220809 | Disposal and Decontamination of Radioactive Polyvinyl Alcohol Products - Methods and apparatus for decontaminating disposable protective products prepared from polyvinyl alcohol (PVA), used in a nuclear power plant, to less than minimum detectable activity (MDA) are disclosed. In the disclosed methods and apparatus, solid protective products made of PVA, generated from a nuclear power plant, are dissolved into a liquid, and then are decontaminated to less than MDA. The PVA solution decontaminated in this way is concentrated to an appropriate concentration or dried, and finally is subjected to self-disposal. This can fundamentally block the generation amount of combustible waste amounting to 50% or more of low and intermediate level waste of nuclear power plants, thereby considerably contributing to a reduction of the operating expenses of the nuclear power plants. The present invention further relates to methods and apparatus for self-disposing disposable protective products manufactured by conventional polyvinyl alcohol (PVA) through pyrolysis/catalytic oxidation of a PVA solution generated by concentration, and treating the decontaminated PVA solution within a plant. The PVA protective products are dissolved/concentrated/oxidized in water to remove firstly organic matter, and then PVA materials in the PVA solution are completely oxidized into CO | 08-30-2012 |
20130178685 | APPARATUS AND METHOD FOR THE GRANULATION OF RADIOACTIVE WASTE, AND VITRIFICATION METHOD THEREOF - An apparatus and method for the granulation of radioactive waste in which a preprocessing method for the vitrification of radioactive waste is simplified to conform to onsite conditions of a nuclear power plant, additives are improved, and pellets suitable for vitrification are manufactured. The apparatus for the granulation of radioactive waste includes: a body frame having an inlet and an outlet; a hopper supplying the radioactive waste to be transferred and fed through the inlet; a feeder transferring/supplying the radioactive waste supplied to a specific position and in a certain quantity; a stirrer pulverizing/mixing lumps of the radioactive waste supplied; an additive supply part supplying a lubricant to the radioactive waste fed into the stirrer; and a pellet press pressing the radioactive waste fed through the feeder into a pellet shape and discharging the pellet through the outlet. | 07-11-2013 |
20140121440 | Thermal Treatment of Carbonaceous Waste, Improved by the Choice of Gas Injected - A method is provided for the decontamination of radioactive carbonaceous material, such as graphite, in which an injection of steam is planned into the material, concurrent with a first roasting thermal treatment of the material at a temperature between 1200° C. and 1500° C. Advantageously, the first treatment may be followed by a second treatment at a lower temperature with an injection of carbon oxide for oxidation according to the Boudouard reaction. | 05-01-2014 |
20140343342 | METHOD FOR REMOVAL OF RADIOACTIVE CESIUM AND FACILITY THEREFOR - To provide a method and an apparatus for removing radioactive cesium from waste containing radioactive cesium at low cost. A radioactive cesium removal apparatus | 11-20-2014 |
20150025294 | Decontamination Method for Radioactively Contaminated Material - This invention relates to a method for decontaminating radioactively contaminated material, for example construction waste. The material is comminuted by means of voltage pulses and can be divided with a high degree of selectivity into non-contaminated or only weakly contaminated material and contaminated remainder. The majority therefore represents non-contaminated or only weakly contaminated waste material which can be disposed of much more easily than the contaminated remainder. Therefore, the method is particularly suitable for reducing the volume of radioactive waste material which is subject to stringent safety requirements in respect of its storage and disposal and therefore its storage and disposal incur high costs. | 01-22-2015 |
20150148582 | METHOD FOR REMOVING THE 137Cs FROM POLLUTED EAF DUSTS - The present invention refers to a method and related plants for removing, by means of redox reactions, the | 05-28-2015 |
20160379727 | APPARATUS AND METHODS FOR TREATMENT OF RADIOACTIVE ORGANIC WASTE - Treatment of radioactive waste comprising organic compounds, and sulfur-containing compounds and/or halogen-containing compounds. An apparatus comprises a reaction vessel comprising a filter for carrying out thermal treatment of the waste and a thermal oxidizer. Utilizing co-reactants to reduce gas phase sulfur and halogen from treatment of wastes. | 12-29-2016 |