| Class / Patent application number | Description | Number of patent applications / Date published |
|---|
| 588020000 | Treating radioactive liquid | 18 |
| 20090118560 | Nuclear waste removal system and method using wet oxidation - Methods for removing nuclear waste from a component are provided. In one embodiment, the method includes the steps of supplying oxalic acid to the nuclear waste on the component to form an oxalic acid/waste solution, feeding the oxalic acid/waste solution from the component, feeding an oxidant to the oxalic acid/waste solution to form carbon-dioxide, water and a precipitate, and separating the precipitate from the water. A system for removing nuclear waste is also provided. | 05-07-2009 |
| 20090306451 | Process for the treatment of phosphogypsum and in particular of phosphogypsum leachates - The present invention describes a process for treating phosphogypsum and in particular the related leachate that comprises the steps of feeding a continuous leachate flow with a dry content of below 5% by weight into a concentration unit heated to a predetermined temperature and equipped with dedicated mixing means, and continuously discharging a concentrated leachate flow having a dry content comprised between 20% and 95% by weight from the concentration unit. | 12-10-2009 |
| 20100069698 | TREATMENT OF NUCLEAR SLUDGE - A method for treating nuclear sludge comprising subjecting the nuclear sludge to a plasma treatment in a plasma chamber to melt at least some of the inorganic components of the sludge, wherein the plasma chamber comprises a crucible having a cooled inner surface, this surface cooled sufficiently such that the inorganic components in contact with the inner surface are in a solid state and form a barrier between the part of surface of the crucible with which they are in contact and the molten inorganic components of the sludge. | 03-18-2010 |
| 20100099938 | Method for extraction of metals by methyliminobisalkylacetamide - The present invention provides a method for extraction of metals selected from Cr, Mo, Pd, Tc, W, Re, and Pu using a new extractant of methyliminobisalkylacetamide represented by a formula (I): | 04-22-2010 |
| 20100185036 | METHOD FOR TREATING RADIOACTIVE LIQUID WASTE AND APPARATUS FOR THE SAME - A method for treating a radioactive liquid waste containing a sodium salt, which includes: feeding a radioactive liquid waste containing at least one of sodium hydroxide, sodium hydrogencarbonate and sodium carbonate to an anode chamber in an electrolytic cell provided with an anode and a cathode on both sides of a permeable membrane, which is selectively permeable to sodium ions, and electrodialyzing the radioactive liquid waste; separating sodium ions permeated through the permeable membrane as sodium hydroxide from the radioactive liquid waste in a cathode chamber; separating a radioactive substance remaining in the anode chamber as a concentrated radioactive liquid waste; and recovering the separated sodium hydroxide and concentrated radioactive liquid waste, respectively. | 07-22-2010 |
| 20110224474 | Advanced Microwave System for Treating Radioactive Waste - Systems and methods for reducing the volume of radioactive waste materials through desiccation, pyrolysis and vitrification carried out by microwave heating. The final product of the advanced microwave system is a dryer, denser, compacted waste product. The invention comprises systems in which a layer of waste material is treated by microwaves within a hopper before deposited within the final waste container; systems in which a thin layer of waste material is treated by microwaves after it has been deposited within the final waste container; and systems in which waste material is treated by microwaves within a hopper before being deposited within the final waste container. | 09-15-2011 |
| 20120022312 | METHOD FOR TREATING RADIOACTIVE LIQUID WASTE AND APPARATUS FOR TREATING THE SAME - A method for treating a radioactive liquid waste containing a sodium salt is described, including: a liquid waste reducing step of partially reducing sodium nitrate contained in a radioactive liquid waste to convert the radioactive liquid waste into a reduced solution containing at least one of sodium hydroxide, sodium hydrogencarbonate, and sodium carbonate; and an electrodialysis step of performing electrodialysis of the reduced solution by supplying the reduced solution to an anode chamber of an electrolytic cell, the electrolytic cell including an anode and a cathode disposed on both sides of a permeable membrane which a sodium ion selectively permeates. | 01-26-2012 |
| 20120065453 | Counter Weapon Containment - 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. | 03-15-2012 |
| 20130178686 | METHOD AND DEVICE FOR LIMITING THE DEGASSING OF TRITIATED WASTE ISSUED FROM THE NUCLEAR INDUSTRY - A method and device for limiting the degassing of tritiated waste issued from the nuclear industry are provided. The method reduces an amount of generated tritiated hydrogen (T | 07-11-2013 |
| 20130225899 | Method for the Conditioning of Waste Coming from Decommissioning of Nuclear Plants - A method is described for the treatment of ferrous nuclear waste, produced in operations of pickling of contaminated metallic surfaces, which makes it possible to minimize the volumes of liquid phases to be treated and to recycle the by-products thereof to the process. | 08-29-2013 |
| 20140005462 | SYSTEM AND METHOD FOR PROCESSING AND STORING POST-ACCIDENT COOLANT | 01-02-2014 |
| 20140058183 | Immobilization of Technetium by Electroless Plating - A process of incorporating technetium into an electroless deposit, forming an alloy that is extremely resistant to corrosion and reduces the mobility of technetium on a geologic time scale is disclosed and claimed. The process includes providing a liquid containing technetium, such as an aqueous waste stream generated during the used nuclear fuel reprocessing activities. The technetium is collected and concentrated, and provided into an electroless deposition bath. A substrate, such as suitably prepared zero valent iron or stainless steel, is introduced into the bath to initiate autocatalytic electroless deposition of the technetium onto the substrate due to the difference in electrochemical potential between the plating bath and ti metals in solution. This causes a layer of technetium metal to form on the substrate. The electroless deposition is continued until virtually all of the technetium has been removed from the bath, and then continues to build a layer of technetium-free material on the outermost surface of the substrate. One or more additional deposition steps may be performed to armor the plated substrate against leaching/corrosion in a nuclear waste disposal facility. | 02-27-2014 |
| 20140194666 | INSTALLATION FOR TREATING CARBONACEOUS RADIOACTIVE WASTE, PARTICULARLY GRAPHITE - The invention relates to the treatment of carbonaceous radioactive waste, comprising the delivery of waste to one or more radioactive isotope separation stations isotopes, said isotopes being among at least carbon 14, chlorine 36, and tritium. Advantageously, the delivery to each of the stations occurs in wet form, with water being a common medium for conveying the waste to each of the separation stations. | 07-10-2014 |
| 20150306644 | METHOD FOR DECONTAMINATING SOIL AND THE LIKE AND SYSTEM FOR DECONTAMINATING SOIL AND THE LIKE - An object to be decontaminated contaminated with radioactive material is introduced into an acid eluting solvent to dissolve the radioactive material. The radioactive material dissolved is concentrated and separated from the eluting solvent in the present method. The object to be decontaminated comprises contaminated soil and contaminated liquid. One or both of the contaminated soil and the contaminated liquid are collected and introduced into the eluting solvent. The radioactive materials and the object to be decontaminated dissolved in the eluting solvent are separated into solid and liquid. The decontaminated soil separated from the eluting solvent is collected. The eluting solvent used for separating the radioactive material and in which radioactive material is dissolved is concentrated. | 10-29-2015 |
| 20160042825 | Solid-Liquid Process For Extraction Of Radionuclides From Waste Solutions - The invention related to a complexing system for extracting a radionuclide from a waste water solution including calix[n]arene groups on the surface of a porous conducting material. | 02-11-2016 |
| 20160155524 | METHOD FOR REDUCING STRONTIUM ION CONCENTRATION | 06-02-2016 |
| 20160172064 | METHOD FOR DECONATIMNATING SOIL AND THE LIKE AND SYSTEM FOR DECONTAMINATING SOIL AND THE LIKE | 06-16-2016 |
| 20170236606 | APPARATUS AND METHOD TO CLEAN CONTAMINATED WATER FROM RADIOACTIVE MATERIALS | 08-17-2017 |
