57 results about "Radioactive decontamination" patented technology

The method provides a dry vertical shaft storage system for spent fuel of a nuclear power station and a storage method thereof. The system comprises a loading subsystem, a storage subsystem, a reloading subsystem, a transferring subsystem, a residual heat discharge subsystem, a negative pressure ventilation subsystem, a fuel suction subsystem and an air blowing subsystem. The system saves a water-cooling system and a water purification system on the basis of the water storage method; the storage vertical shaft is arranged underground, so that the influence of an external event can be effectively prevented, such as airplane crash; when the spent fuel needs to be transferred, a spent fuel storage tank can be taken out of a storage depot, and then directly loaded in a spent fuel shielding transport cask through lifting equipment so as to be conveniently transported; a plant and structural equipment are not polluted by radioactive materials, so the spent fuel storage depot can be normally disassembled and retired after the spent fuel storage tank is transferred; radioactive decontamination is not needed and the spent fuel storage depot can be conveniently retired; and the storage tank can be processed in different phases to reduce initial cost according to the operation of the power station.

The invention discloses a mobile online radioactive decontamination system for a nuclear power plant, which includes a mixing tank, an injection pump, a buffer tank, a decontamination pump and an electric heater. The decontamination system includes at least two movable modules, and each movable module All are equipped with input and output interfaces for connecting with other movable modules or equipment to be decontaminated; mixing tanks, injection pumps, buffer tanks, decontamination pumps and electric heaters are respectively set in the movable modules; when in use, the The movable module is moved to a suitable position, and the movable module and the online equipment to be decontaminated are connected to each other in a predetermined order through the connection interface, so that the liquid in the mixing tank can pass through the pipeline in turn through the injection pump, buffer tank, decontamination pump and electric decontamination pump. After the heater enters the equipment to be decontaminated, the equipment to be decontaminated is decontaminated online. The advantages of the present invention are as follows: the present invention can carry out online decontamination of the equipment to be decontaminated in the nuclear power plant, thereby simplifying the operation, reducing the radiation dose of personnel and reducing the risk of radiation exposure.

The invention relates to a radioactive surface strippable detergent and a preparation method thereof, and belongs to the technical field of application of polymer chemical coating materials to nuclearfacility surface radioactive decontamination. The radioactive surface strippable detergent is prepared by taking polyvinyl alcohol as a main film-forming agent, taking water as a solvent and adding an auxiliary agent, wherein the auxiliary agent is prepared from the following components: a gelatinizing agent, a dispersing agent, a reinforcing agent, a surfactant, an adhesive, a chelating agent, an auxiliary film-forming agent, a lubricating agent, an anti-freezing agent, a plasticizer, Vaseline, an emulsifying agent and a thickening agent. The prepared strippable film detergent is good in film-forming property, long in quality guarantee period and good in strippability, and can meet the operation requirements of short-term and medium-term storage and stainless steel surfaces for radioactive waste pits and hot chambers.

A method for the removal of embedded contamination from a metallic surface in which a laser beam is directed on to the contaminated surface. The laser beam has sufficient power density to cause direct ejection of laser-generated melt pool liquid from the metallic surface thereby removing a metallic surface layer containing the embedded contamination. Means are provided for the collection of laser ejected material in order to prevent recontamination of the metallic surface or contamination of previously uncontaminated surfaces.

The invention relates to a polyvinyl alcohol-based strippable film detergent, a preparation method and a use method thereof, and belongs to the technical field of application of polymer chemical detergents to nuclear facility surface radioactive decontamination. The polyvinyl alcohol-based strippable film detergent takes 100-300 parts by weight of polyvinyl alcohol as a main film-forming agent andwater as a solvent, and is added with the following components in parts by weight: 2-10 parts of a gelatinizing agent, 1-6 parts of a surfactant, 2-10 parts of an adhesive, 1-5 parts of a thickeningagent, 2-10 parts of a reinforcing agent, 0.5-2.0 parts of a composite chelating agent, 1-5 parts of a dispersing agent, 1-5 parts of a lubricating agent, 5-10 parts of a plasticizer and 2-8 parts ofa preservative, wherein the composite chelating agent is composed of EDTA-2Na and sodium tripolyphosphate according to a weight ratio of 1-3:1-3. The prepared strippable film detergent is excellent indecontamination performance, good in film-forming property, long in shelf life and good in strippability, and has very high application value.

The invention provides a pressure drainage type radioactive sewage filter, and belongs to the technical field of radioactive decontamination of nuclear power plants. The filter comprises a shielding shell, an inner cylinder and a positioning sealing disc, an outer ring and an inner ring on the lower surface of the positioning sealing disc are respectively aligned and hermetically welded to upper ports of the shielding shell and the inner cylinder, and an interlayer space formed by welding the inner cylinder, the shielding shell and the positioning sealing disc is filled with a shielding lead plate, a recess for embedding a filter element adapter disc is formed in the middle of the upper surface of the positioning sealing disc, a shielding ring is fixed around the recess, the middle part ofthe filter element adapter disc is a filter element area, vertical drainage holes are distributed in the periphery of the filter element adapter disc at intervals, a shielding cover is arranged on the upper surface of the filter element adapter disc, an isolating ring for separating the filter element area from the vertical drainage holes is arranged on the lower surface of the shielding cover, and a medium inlet hole and a medium outlet hole are formed in the shielding cover. By the pressure drainage type radioactive sewage filter, the filtering effect can be guaranteed, the ideal anti-radiation performance is achieved, and maintenance and replacement are convenient.

The invention belongs to the technical field of radioactive decontamination, and particularly relates to a saturated steam decontamination device, which comprises a medicine box part, a water tank part, a heating boiler part and a water gun part. Deionized water is heated into saturated steam with the temperature of 180 DEG C and the pressure of 10 bar, the saturated steam is combined with a decontamination reagent and sprayed out through a water gun, and therefore, a decontamination effect is achieved. The medicine box part is mainly used for holding the decontamination reagent used in the decontamination process, and the decontamination reagent and saturated steam are mixed through a liquid medicine pump to jointly complete decontamination work. The water tank part can hold deionized water for providing the saturated steam in the decontamination process, and the deionized water is conveyed to a boiler for heating through a boiler water pump. Compared with a traditional ultrasonic oxidation-reduction decontamination device, the provided saturated steam decontamination device is obvious better in decontamination effect through field tests.

The invention belongs to the technical field of nuclear power plant equipment radioactive decontamination, particularly relates to a cleaning tool for a detection device for a nuclear reactor rod cluster control assembly (RCCA). A connection plate is in a rectangular hollow cavity structure, a plurality of holes communicated with the rectangular hollow cavity are evenly distributed in one lateral surface, and two ashore air pipe connectors communicated with the rectangular hollow cavity are symmetrically installed on the other lateral surface. Cleaning rods are respectively in a cylindrical hollow cavity structure, wherein a plurality of air holes are evenly distributed in each cleaning rod. A connection handle is in a rectangular plate-shaped structure, wherein a plurality of through holes are evenly distributed in the connection handle. A plurality of the cleaning rods are combined into a cleaning rod group through the connection handle, the upper end of each cleaning rod is connected and fixed with one through hole in the connection handle and is connected with a corresponding hole in the connection plate through an air pipe, an air source is respectively connected with the two ashore air pipe connectors through a pipeline, and the pipelines between the air source and the two ashore air pipe connectors are sequentially provided with a stop valve and a pressure regulating valve. The cleaning tool for the detection device for the nuclear reactor RCCA is capable of effectively removing pollutant on the detection device, and lowering the radioactive dosage of the detection device.

The invention belongs to the technical field of radioactive decontamination treatment and particularly relates to a movable radioactive decontamination device. The movable radioactive decontamination device comprises a cleaning tank with a hanging basket, a tank cover, a manual spraying device, a spraying valve, a stainless steel heater, an ultrasonic generator, rubber wheels with brakes, a blow-off pipe and a rack. The cleaning tank with the hanging basket is installed in the rack, the tank cover is arranged on the top of the rack, and the rubber wheels with the brakes are installed in the four corners of the bottom of the rack respectively. A circulating filtration system is arranged at the bottom of the cleaning tank with the hanging basket. The manual spraying device is connected with one end of the spraying valve, and the other end of the spraying valve is connected with the circulating filtration system. The stainless steel heater is installed on the right side of the cleaning tank with the hanging basket. The blow-off pipe is installed on the left side of the cleaning tank with the hanging basket. The ultrasonic generator is installed on a tank body of the cleaning tank with the hanging basket. The problems existing in existing decontamination equipment can be solved, the decontamination efficiency is high, and the movable radioactive decontamination device is suitable for radioactive movable radioactive decontamination device of small parts of a nuclear power plant.

The invention belongs to the technical field of radioactive decontamination, and relates to oxidation decontamination gel as well as a preparation method and application thereof. The oxidation decontamination gel is prepared from the components including, by weight, 5%-15% of a gel base material serving as a gel framework material, 5%-10% of a surfactant, 0.5%-5% of a thixotropic multiplication agent, 3%-20% of a strong oxidant, 3%-20% of acid, 1%-5% of a modifier and 25%-82.5% of water. By means of the oxidation decontamination gel as well as the preparation method and application thereof, the oxidation decontamination gel can be better prepared, the prepared oxidation decontamination gel is the oxidation gel for decontamination of second-generation radioactive contaminated metal, water washing is not needed after decontamination is completed, the residual oxidation decontamination gel can be automatically dried and cracked, and a brush is conveniently used for cleaning, or a dust collector is used for sucking and collecting the gel, so that secondary liquid waste is not generated in the decontamination process, and the gel is more suitable for field decontamination.

The invention relates to a modular mobile type purification device for airborne radioactive matter. The device comprises an air inlet module, a fan module, and a filter part arranged between the air inlet module and the fan module; and the filter part comprises one or more selected from a smoke filter module, an aerosol filter module and an iodine adsorption module, the filter part is selectivelycombined with the air inlet module and the fan module according to the requirements in a use occasion, and the modules are tightly connected by connecting mechanisms and sealed by sealing members. According to the device provided by the invention, through the modular design, the modules can be separately transported, moved and further recombined; through a combination of the modules, the filteringrequirements in different environments can be realized; and through arrangement of an easily-torn film of an outer shell, the easily-torn film can be peeled off every time after the device is used, so that the problem of surface contamination of the device can be effectively solved.

The invention belongs to the technical field of nuclear power plant master pump radioactive decontamination techniques and particularly relates to a nuclear power plant movable master pump impeller radioactive decontamination apparatus, comprising a decontamination liquid preparation module A, a decontamination configuration module B, and a desalted water system; the decontamination liquid preparation module A is connected with the desalted water system through a hose, and the decontamination liquid preparation module A is connected with the decontamination configuration module B through a hose to deliver a decontamination liquid. The nuclear power plant movable master pump impeller radioactive decontamination apparatus has the advantages that labor intensity of operators is reduced, decontamination time is saved, and decontamination effect and efficiency are improved.

The invention discloses a method for producing radioactive strontium-90 and caesium-137 simultaneously by adopting a centrifugal extractor and belongs to the technical field of radioactive wastewatertreatment. The method includes: adopting the centrifugal extractor, taking crown ether as an extraction agent of <90>Sr to extract radioactive <90>Sr in high-level liquid waste after acid adjustment,adopting nitrite acid solutions of different concentrations as washing agents and back extracting agents, and sequentially washing and back extracting extraction agents loaded with impurities and <90>Sr elements to obtain radioisotope <90>Sr products; taking crown as an extraction agent of <137>Cs, extracting radioactive <137>Cs from high-level liquid waste after <90>Sr is extracted, adopting nitrite acid solutions of different concentrates in the centrifugal extractor as washing agents and back extracting agents, sequentially washing and back extracting extraction agents loaded with impurities and <137>Cs to obtain radioisotope <137>Cs products. The method has the advantages of good transferring effect, high selectivity of <90>Sr and <137>Cs and radioactive decontamination factor and thelike, continuous production can be realized, and two kinds of high-purity radioisotope<90>Sr and <137> Cs products with important applications are obtained efficiently.

The invention belongs to the technical field of radioactive decontamination, and relates to a method for removing radioactive contamination deposited oxides. The method comprises the following steps: (1) oxidizing and decontaminating a part by using an oxidizing decontaminating agent solution; (2) rinsing the component; (3) reducing and decontaminating by using a reducing decontaminant solution of the part; (4) rinsing the component; and (5) airing the components. According to the method for removing the radioactive contamination deposited oxide, the metal oxide deposited on the surface of the zinc injection reactor component can be removed on the basis of a traditional chemical decontamination technology, and a base body is not damaged.

The invention provides an ultra-low pressure reverse osmosis system, wherein a feeding device is provided with a raw water tank; a stock solution at an outlet of the raw water tank is pressed into a multi-medium filter through a centrifugal pump; the multi-medium filter changes membrane pressure through a multi-stage pump and enables the stock solution to enter a reverse osmosis membrane componentfor treatment; and a concentrated water outlet pipe of the reverse osmosis membrane component is provided with a valve to adjust a standard recovery rate of the system. The invention also discloses amethod for treating iodine ions in radioactive polluted water by adopting the system, which comprises the following steps: under the conditions that the operating pressure is 0.3-0.8MPa, the temperature is 20+/-3 DEG C and the standard recovery rate of the system is 15.0%-17.0%, the maximum radioactive decontamination factor of iodine ions of the reverse osmosis system can reach 920 by using a polyamide roll composite membrane. The method can effectively remove iodine ions in radioactive polluted water, the separation process has no phase change, energy consumption is low and operation can becarried out at normal temperature. The method has wide application prospect in the fields of emergency water supply, radioactive wastewater treatment, nuclear concentration and the like in sudden nuclear accidents.

The invention discloses a composite nanosecond laser decontamination device and method for radioactive decontamination. The cooperative decontamination method comprises the following steps: driving anoptical module of the composite nanosecond laser decontamination device to perform scanning type stepping movement above a to-be-decontaminated workpiece, and keeping a preset time interval between two adjacent stepping movements, after each stepping movement, firstly starting a high-efficiency nanosecond laser, stopping the high-efficiency nanosecond laser after running for a first time period,starting an ultra-high-energy nanosecond laser after running for a second time period, stopping the ultra-high-energy nanosecond laser after running for a third time period, and stopping the ultra-high-energy nanosecond laser until the high-efficiency nanosecond laser is started next time at an interval of a fourth time period; and making the optical module perform stepping movement according to the steps until the upper surface of the to-be-decontaminated workpiece is scanned. The two paths of lasers cooperate at intervals for composite operation, dirt attached on a surface to be cleaned canbe removed after once scanning, deep peeling and decontamination of a radioactive member can be completed, and the decontamination efficiency is improved.

The invention belongs to the technical field of nuclear power station radioactive decontamination, and provides an automatic detection and classification device for radioactive contamination parts of a nuclear power station. The automatic detection and classification device is characterized in that a conveying mechanism is arranged on a rack and is used for conveying the radioactive contamination parts, and a clamping mechanism is arranged on the rack and is used for clamping and moving the radioactive contamination parts; and a radiation detector is arranged on the rack and is used for carrying out radioactivity detection on the radioactive contamination parts clamped by the clamping mechanism, and a storage part is arranged on the rack and is used for storing the radioactive contamination parts which are clamped by the clamping mechanism and are qualified or unqualified after radioactivity detection. According to the automatic detection and classification device, radioactive detection can be automatically carried out on the radioactive contamination parts, the radioactive contamination parts which are detected to be unqualified are automatically classified and collected in the storage part, and the radioactive contamination parts which are detected to be qualified are conveyed to the next station by the conveying mechanism to be automatically classified and collected, so that the working efficiency is remarkably improved, and the radiation risk of workers can be reduced.