Entries |
Document | Title | Date |
20090062592 | Apparatus for disposal of low-level surface radioactive pollutants - An apparatus for disposal of low-level surface radioactive pollutants has a container body which center has accommodating space with opening at its top. Around the accommodating space there is a layer of barrier space for holding water. At the periphery of the barrier space there is a non-barrier hollow channel for the accommodating space to connect outside. A rotating disk is located at the bottom of the accommodating space in the container body for holding and turning the low-level radioactive waste to be treated and also facilitating the worker to pass through the non-barrier hollow channel for cleaning task. | 03-05-2009 |
20100168497 | CHEMICAL DECONTAMINATION APPARATUS AND DECONTAMINATION METHOD THEREIN - A chemical decontamination apparatus of the present invention chemically dissolves radioactive substance-containing oxide films formed or adhering on the surface of a decontamination object by using ozone water to conduct decontamination. The chemical decontamination apparatus includes an ozone generating unit for generating ozone gas, an ozone supplying device for supplying the generated ozone gas to an ozone supplying unit in water, and a sintered metal element | 07-01-2010 |
20100217060 | Method of Decontaminating Radioisotope-Contaminated Surface Vicinity Region by Use of Nonthermal Laser Peeling Without Re-Melting, Without Re-Diffusion and Without Re-Contamination, and Apparatus Therefor - The current methods of removing the surface-deposited layer contaminated by radioisotopes has the disadvantage of rigorous applicability conditions in such terms as the substance to be treated, the area and the shape, so the scope of their applicability is quite limited; in addition, 100% decontamination is not guaranteed and in spite of more than 50% that can be decontaminated, a greater part of the deposited radioisotopes remain unremoved, limiting the decontamination performance of the methods. | 08-26-2010 |
20100305383 | Systems and Methods for Reducing the Storage Time of Spent Nuclear Fuel - Systems and methods are provided for reducing the storage time of spent nuclear fuel. In one embodiment, a method is provided that includes providing a sample of spent nuclear fuel and irradiating the spent nuclear fuel with substantially collimated gamma ray photons having energy levels of about 10 MeV to about 15 MeV for a predetermined time period to initiate a photofission reaction in the remaining fertile fissile material in the spent nuclear fuel. | 12-02-2010 |
20110040137 | Automated mechanical cleaning method for radioactively contaminated metal - A rotary-drum mechanical surface decontamination method for radioactively contaminated metal first places a feed chute fully loaded with radioactively contaminated metal on a hydraulic lift platform of a dual-chain roller conveyor and then moves the feed chute to a hydraulic cover-opening machine for positioning, and then uses a hydraulic cover-opening machine to open the cover of the feed chute, while non-covered feed chute will advance further to the post on a feed hopper of a drum spray washer, and then drop the workpieces into a conical drum for rotary multi-angular spray washing. The decontaminated metal waste is transferred by a vibrating discharger onto a conveyor and then into a discharge tank, and to the hydraulic cover-opening machine by a dual-chain roller conveyor, and to the hydraulic lift platform to complete the decontamination process. | 02-17-2011 |
20110098521 | METHOD OF TREATING A STRUCTURE CONTAINING SODIUM AND A RADIOACTIVE SUBSTANCE - Method of treating sodium contained in the interconnected open pores of a structure placed in a cladding, the pores furthermore containing a radioactive substance. The method comprises the following successive steps: a) at least two slits are made over the entire length of the cladding; b) the sodium is converted to sodium carbonate by a carbonation reaction by bringing the structure into contact, via the slits, with a reactive gas mixture comprising steam, carbon dioxide and a gas inert with respect to sodium, in such a way that the expansion of the carbonate causes the cladding and the structure to open starting from the slits and results in the carbonation reaction propagating into the structure. | 04-28-2011 |
20120184795 | Apparatus for Separation of Constituents From Matrices - The present invention provides an apparatus useful for the separation of hazardous and non-hazardous organic and inorganic constituents from various matrices. A method of separating such constituents is also provided. | 07-19-2012 |
20130211172 | METHOD FOR PARTIALLY DECONTAMINATING RADIOACTIVE WASTE - Methods for partially decontaminating radioactive waste wherein the waste is first mixed, or brought in contact, with at least one corrosive medium. Activation energy is then supplied to the corrosive medium, so that at least a portion of the radionuclide present in the waste is converted into at least one gaseous reaction product, or is dissolved, by hydrogen or hydrogen ions, oxygen or oxygen ions, and/or halogen (for example chlorine) or halogen ions from the corrosive medium. The aim is that of decontaminating a | 08-15-2013 |
20130237741 | DECONTAMINATION METHOD AND APPARATUS FOR SOLID-STATE MATERIAL CONTAMINATED BY RADIOCESIUM - A decontamination method of solid-state material contaminated by radiocesium comprising bringing the solid-state material containing radiocesium in contact with a first processing solution and preferably eluting cesium ion from the solid-state material to the liquid phase under the presence of potassium ion or ammonium ion. | 09-12-2013 |
20140073829 | METHODS AND APPARATUSES FOR STABILIZING FUEL CONTAINING REACTIVE SODIUM METAL - A method of stabilizing a fuel containing a reactive sodium metal may include puncturing a cladding of a fuel pin enclosing the fuel containing the reactive sodium metal to form an injection passage and an extraction passage. A reaction gas may be injected into the fuel pin through the injection passage to react with the reactive sodium metal to form a stable sodium compound. A ratio of a product gas and a remaining quantity of the reaction gas exiting the fuel pin through the extraction passage is subsequently measured, wherein the product gas is a reaction product of the reaction gas and the reactive sodium metal within the fuel pin. Once the measured ratio indicates that a reaction between the reaction gas and the reactive sodium metal is complete, the injection passage and the extraction passage are sealed so as to confine the stable sodium compound within the fuel pin. | 03-13-2014 |
20140249345 | Apparatus And Methods For Vaporization And Remediation Of Radioactive Contamination - An aspect of the present disclosure relates to a method for collecting volatile radioactive substances. The method includes irradiating a volatile radioactive substance on or under a contaminated material surface using microwave radiation and vaporizing the volatile radioactive substance, wherein the volatile radioactive substance comprises at least one of cesium and iodine. The method further includes recovering the vaporized volatile radioactive substance from the contaminated material. The method may be accomplished with and/or without physically collecting or isolating the contaminated material. | 09-04-2014 |
20140350320 | PROCESSING OF CHLORINE-CONTAINING CARBON-BASED RADIOACTIVE WASTE - A system and method for processing of carbon-based radioactive waste, comprise at least: a) soaking in an acid solution, and b) a heat treatment, of a thermal shock type, said acid solution recovering radioactive material resulting from said waste at least after the implementation of step b). | 11-27-2014 |
20140378733 | Oxidation Decontamination Reagent for Removal of the Dense Radioactive Oxide Layer on the Metal Surface and Oxidation Decontamination Method Using the Same - The present invention provides an oxidative decontamination reagent for removal of the dense radioactive oxide layer on a metal surface, which comprises an oxidizing agent, a metal ion, and an inorganic acid. The oxidative decontamination reagent of the present invention is characteristically prepared by adding a metal ion to the conventional oxidative decontamination reagent containing an oxidizing agent and an inorganic acid. When the oxidative decontamination reagent of the present invention is used, electric potential of the metal parts of the primary system of the nuclear power plant can be regulated as passive potential owing to the added metal ion during the oxidative decontamination of the primary metal part of the nuclear power plant. Therefore, by maintaining electric potential of the metal part as passive potential, local corrosion can be inhibited and at the same time secondary waste can be significantly reduced. | 12-25-2014 |
20150073198 | Method of Chemical Decontamination for Carbon Steel Member of Nuclear Power Plant - A circulation pipe of a chemical decontamination apparatus including a malonic acid injection apparatus and an oxalic acid injection apparatus is connected to a purification system pipe, which is made of carbon steel, of a boiling water nuclear power plant. A malonic acid aqueous solution is injected from the malonic acid injection apparatus into the circulation pipe. An oxalic acid aqueous solution is injected from the oxalic acid injection apparatus into the circulation pipe. A reduction decontaminating solution including a malonic acid of 5200 ppm and an oxalic acid within a range of 50 to 400 ppm is supplied into the purification system pipe through the circulation pipe. Reduction decontamination for an inner surface of the purification system pipe is executed. After the reduction decontamination for the purification system pipe finishes, the malonic acid and oxalic acid included in the solution are decomposed and furthermore, the solution is purified. | 03-12-2015 |