71 results about "Radioactive Pollutants" patented technology

A tube cutting device and method thereof are disclosed, which are adapted for performing a remote tube cutting operation upon a tube. The tube cutting device is comprised of: a holding unit; a cutting unit; and a control unit, connected to the holding unit and the cutting unit in a remote manner; wherein, the control unit is capable of directing the holding unit to hold and move a tube to a specific position and thereafter directing the cutting unit to perform a cutting operation upon the tube. With the aforesaid tube cutting device, an operator operating the tube cutting device can perform an cutting operation upon the tube remotely without having to contact directly with the tube, and thus the operator is prevented from having to stay in a working environment containing hazardous materials, such as radioactive pollutants, gas / liquid with strong acid or alkali, etc., so that the safety of the tube cutting operation can be enhanced. In addition, as the tube cutting device is simple in structure, the manufacturing cost thereof is comparatively low but still possess high cutting efficiency.

The invention discloses a small high-yield and deuterium-deuterium neutron generator. Modular distributed high-frequency ion sources are adopted and evenly distributed on the outer surface of a ceramic cylinder with the spherical end, and deuterium ion beams distributed evenly are output, wherein the flow intensity of the deuterium ion beams is larger than 1 A, and the single atom proportion is larger than 80%; the deuterium ion beams are accelerated in a cylindrical accelerating electric field with the spherical end and bombard a cylindrical metal or ceramic self-forming target to cause a deuterium / deuterium reaction and then generate neutrons of 2.45 MeV, and the self-forming target is located at the high-potential end and provided with the spherical end. The number of the modular distributed high-frequency ion sources and the area of the self-forming target are not limited, the yield of the neutrons of the deuterium / deuterium reaction is larger than 1011 n / s, and no radioactive pollutants are discharged. The neutron generator is suitable for commercialized application such as the fields of boron neutron capture treatment, neutron radiography, on-line material component neutron detection, neutron irradiation modification and californium neutron source substitute products.

The invention relates to a laser cleaning system for removing nuclear power station radioactive contamination. The laser cleaning system comprises a laser generator, a laser transmitting device, a working monitoring system, a controlling system and a waste recycling system, the laser transmitting device is connected with a laser output port of the laser generator, the working monitoring system is arranged nearby target materials, the laser transmitting device comprises optical fibers, a mover, mechanical arms and an operating device, the optical fibers are connected with the laser output port of the laser generator and used for transmitting laser lights, the mover is used for moving laser output ports of the optical fibers onto the surfaces of radioactive contaminants, the operating device is arranged on the mechanical arms, the optical fibers are fixedly disposed in the mover, the laser output ports of the optical fibers are located at one end of the mover, one end of the mover is suspended in the air, the other end of the mover is installed on the mechanical arms, the operating device is used for controlling the mechanical arms and the mover to move, and the movement of the mover drives the laser output ports of the optical fibers to move.

A nanometre-class TiSi molecular sieve for removing pollutants of heavy metals and radioactive substance from environment and purifying nuclein has a mole formular Na1+ / -xTi1.5+ / -ySi1+ / -zO5, where x=0.01-0.2, y=0.1-0.5 and z=0.1-0.2. It is prepared from tetrabutyl titanate or tetraisopropyl titanate, ethyl n-silicate, sodium hydroxide and water jointly by the sol-gel method and the hydrothermal synthesis method. Its advantages are fine crystal grain, high reaction activity, low cost, high exchange capacity with radioactive elements and heavy metals, and high thermal stability and radioactive resistance.

Embodiments of the invention provide systems and methods for water purification and desalination. The systems have a preheater, a degasser, multiple evaporation chambers with demisters, heat pipes, and a control system, wherein the control system permits continuous operation of the purification and desalination system without requiring user intervention or cleaning. The system is capable of recovering heat from each distillation stage, while removing, from a contaminated water sample, a plurality of contaminant types including: microbiological contaminants, radiological contaminants, metals, salts, volatile organics, and non-volatile organics.

Disclosed is a radioactive contaminant container including a wall that defines a containing space for containing radioactive contaminants and shields at least a portion of radiation irradiated from the radioactive contaminants, and the wall has an outer shape of a hexagonal cylinder or a substantially hexagonal cylinder.

Surface or submersible sluiceable system for use in removing hazardous contaminants or radioactive isotopes from a fluid stream, such as a fluid stream from the primary coolant loop or secondary loop of a nuclear reactor system, a fluid stream from a spent-fuel pool or pond or hazardous or radioactive contaminants in ground water. Generally, this surface or submersible sluiceable system is adapted to be utilized in a surface skid or submersed in the fluid stream, and additionally the vessels are adapted to be sluiced and reused after use, resulting in a potentially stabilized, non-leaching final waste product with a substantially reduced volume for storage or disposal. The system can be utilized with any type of media, whether standard ion exchange beads or inorganic granular media.

The present disclosure provides, in an embodiment, a system for treating a contaminated fluid. The system may include multiple shielded modules in fluid communication with one another. Each module of the system of the present disclosure may include an inner pressure vessel designed to accommodate a treatment medium, the treatment medium being selected to remove radioactive contaminants from a fluid passed through the pressure vessel. The module may also include an outer shield vessel surrounding the pressure vessel and designed to attenuate the radiation from the radioactive contaminants accumulated by the treatment medium in the pressure vessel and facilitate ease of handling and storage of the module together with the contaminated treatment medium. Finally, an annular region may be defined between the pressure vessel and the shield vessel for passing a cooling medium therethrough to remove decay heat from the radioactive contaminants accumulated in the pressure vessel.

The invention relates to the field of chemistry and chemical engineering, in particular to a decontaminant for radioactive contamination on the metal surface and a using method of the decontaminant. The decontaminant is characterized in that the decontaminant is an equal-volume mixture of an oxidizing agent and a complexing agent; the oxidizing agent is an aqueous solution containing 5-10% of Cl<-1> and 5-10% of ClO<-1>, the complexing agent is a series of aqueous solutions of inorganic negative ion water-soluble compounds, wherein the series of aqueous solutions and positive ions such as Fe<+2,3>, Ni<+2>, Cr<+2,3> and Co<+2,3> form water-soluble complexes in the aqueous solutions. The using method comprises a mist spraying method, a wiping method and a soaking method. The decontaminant for the radioactive contamination on the metal surface and the using method of the decontaminant have the advantages that the etching decontamination speed is moderate, and the etching reaction speed, the etching depth and the like are controllable; the decontaminant is especially suitable for efficiently removing radioactive contaminants on the inner surface of a closed system, and the content of decontamination factors is high; and according to the using method, in the decontamination process, NO2 and acid mist which pollute the environment and corrode other equipment are not generated, dangerous substances such as explosive gas H2 are not generated, waste liquid generated in the decontamination process is treated properly, and secondary waste which cannot be treated by a nuclear facilitywaste treatment facility is not generated.

The invention provides a cigarette with a filter tip. The cigarette comprises the filter tip and a cut tobacco part, wherein the filter tip comprises chitosan fibers, the viscosity of the chitosan fibers is more than 800 mPa.s, the deacetylation degree is more than 90 percent, the ash content is less than 0.5 percent, the chitosan fiber number is between 1.2 and 5.0 dtex, the strength is more than 1.5 CN / dtex, the cracking elongation is more than 6 percent, the bacteriostasis rate is more than 85 percent, and the content of chitosan in the chitosan fibers is more than 99.9 percent. The invention also provides a preparation method for the cigarette with the filter tip. The filter tip for the cigarette has broad-spectrum antibacterial performance, has an ultrastrong adsorption effect on harmful substances and a function of obstructing radioactive pollutants, and is an environment-friend product. In addition, adjacent amino groups and hydroxyl groups exist in chitosan fiber molecules, so the cigarette has a good adsorption effect on tar. The prepared cigarette with the filter tip has a simple preparation process and is low in cost.

The invention belongs to the technical field of novel materials and particularly relates to anti-irradiation easy-decontamination paint and a preparation method thereof. The anti-irradiation easy-decontamination paint is formed by mixing of a component A and a component B. The component A is prepared from, by weight, 40-60% of fluorocarbon resin, 4-10% of tinting pigments, 15-25% of filler, 10-15% of anticorrosion pigments, 5-15% of a flame retardant, 0.5-1.5% of a dispersing auxiliary agent and 5-10% of a diluting agent. The component B is selected from one or both of a modified aromatic polyisocyanate curing agent and an aliphatic polyisocyanate curing agent. A coating of the paint prepared according to the method is not only resistant to irradiation, weather and corrosion but also easy to clean to remove radioactive pollutants.

Embodiments of the invention provide systems and methods for water purification. The systems have a preheater (30), a degasser (40), an evaporation chamber (50), a demister (70), and a control system (120), wherein the control system (120) permits operation of the purification system (10) through repeated cycles without requiring user intervention or cleaning. The system is capable of removing, from a contaminated water sample, a plurality of contaminant types including: microbiological contaminants, radiological contaminants, metals, salts, volatile organics, and non-volatile organics.

The invention discloses the technical field of cleaning agents and particularly relates to a cleaning agent used for eliminating a radioactive pollutant on the surface of an object, the cleaning agentcomprises the following components by volume: 35-45 parts of an EHS0106 cleaning agent, 1-2 parts of a mixture, and 150-300 parts of a solvent, the cleaning agent finishes cleaning the dirt by usingthe chemical dissolving action and the physical stripping action, the scale, the rust and the radioactive dirt on the surface of the object are separated from an iron body, the ions like Ca<2+>, Mg<2+>, Fe<2+>, UO22+ and U4+ rapidly form a complex and a chelate through the mixture, the dirt is promoted to dissolve rapidly, the dirt enters a cleaning fluid, the degree of the radioactive pollution of steel and iron materials and equipment on the production field are greatly reduced, the reuse ratios of the steel and iron materials and the equipment on the production field are increased, the level of radioactive pollution is reduced, the working environment is improved, and the cleaning agent is favorable for the body health of an operation staff.

A tube cutting device and method thereof are disclosed, which are adapted for performing a remote tube cutting operation upon a tube. The tube cutting device is comprised of: a holding unit; a cutting unit; and a control unit, connected to the holding unit and the cutting unit in a remote manner; wherein, the control unit is capable of directing the holding unit to hold and move a tube to a specific position and thereafter directing the cutting unit to perform a cutting operation upon the tube. With the aforesaid tube cutting device, an operator operating the tube cutting device can perform an cutting operation upon the tube remotely without having to contact directly with the tube, and thus the operator is prevented from having to stay in a working environment containing hazardous materials, such as radioactive pollutants, gas / liquid with strong acid or alkali, etc., so that the safety of the tube cutting operation can be enhanced. In addition, as the tube cutting device is simple in structure, the manufacturing cost thereof is comparatively low but still possess high cutting efficiency.

The invention discloses an electrochemistry in-situ dirt removing method of radioactive contaminant on the surface of metal. A liquid storage tank is involved in the method. A cathode plate is installed below the liquid storage tank. A guide wire is connected to the cathode plate. A through hole is formed in the bottom of the liquid storage tank. The bottom of the through hole penetrates through the liquid storage tank and the cathode plate sequentially. An anode contactor is detachably connected to the exterior of the liquid storage tank. The anode contactor is provided with a storing cavityused for storing the cathode plate. The anode contactor is provided with a ring-shaped sealing part. The interior of the ring-shaped sealing part and the bottom face of the anode contactor form a washing cavity. An opening is formed in the bottom of the anode contactor. The opening communicates with the storing cavity and the washing cavity. According to the method, for the small contaminant area,fixed-point in-situ dirt removing can be carried out on the radionuclide area by means of the washing cavity formed by the anode contactor and the ring-shaped sealing part, the dirt removing precision is high, the dirt removing effect is good, the electrolyte solution is prevented from being wasted on the surface of the metal which does not need to be washed, the washing cost is saved, and the amount of second-time waste liquid is small.

The invention discloses a preparation method and application of a polycyclotriphosphazen porous material, belonging to the field of functional polymer porous materials. The preparation method for the polycyclotriphosphazen porous material comprises the following steps: subjecting hexachlorocyclotriphosphazene monomer and a piperazine, pyrazine or pyrazole compound to a polycondensation and crosslinking reaction under the action of an acid binding agent; and then carrying out activation so as to obtain the porous material. The polycyclotriphosphazen porous material has the advantages of low cost, high specific surface area, capacity of regulating particle sizes in a large range at will, excellent stability and the like, is applied to a plurality of fields like catalyst carriers, gas capture and storage, in-depth treatment of metal ions and separation of radioactive pollutants, and especially has good capability in capturing micromolecules like iodine and iodomethane in CO2, iodine steam and solutions. The preparation method is simple and easily practicable in process, uses widely available raw materials and is especially suitable for industrial application.

The invention discloses a deep purifying system of water quality polluted by radioactive substances. The deep purifying system comprises a preprocessing system, a reverse osmosis deep purifying system, a sterilizing and disinfecting system and a radioactive pollutant concentrated collecting system. The preprocessing system is composed of one or more or more of a medium filter, a self-cleaning filter, a precise filter and an ultrafiltration apparatus. The radioactive pollutant concentrated collecting system is composed of a concentrated water concentrating device and a radioactive pollutant collector. The deep purifying system is simple in structure, convenient to operate and maintain and good in water quality purifying effect, can effectively remove radioactive pollutants in water, is particularly suitable for areas where water resources are affected with radioactive pollution, and belongs to the technical field of water treatment.

The invention provides a multifunctional field drinking water purification and disinfection device and an application method thereof and belongs to the technical field of drinking water purification and disinfection. The multifunctional field drinking water purification and disinfection device comprises a backpack, a water treatment device, a water treatment reagent and a water quality analysis instrument. According to the multifunctional field drinking water purification and disinfection device, excessive disinfectant is used for disinfecting field drinking water, and the oxidation and inactivation of chemical, biological and radioactive pollutants are realized by removing the excessive disinfectant through a dechlorinating agent; the removal of turbidity substances and chemical, biological and radioactive pollutants is achieved through coagulation and precipitation; active carbon and ion exchange resin are used as main adsorption materials, and chemical, biological and radioactive pollutants are removed through adsorption. According to the multifunctional field drinking water purification and disinfection device, the quality of treated water is detected by using the water qualityanalysis instrument so that the drinking safety of the purified water can be ensured. Meanwhile, the invention provides the application method of the disinfection device. The method is simple to operate and capable of rapidly obtaining large-volume safe drinking water.

The invention relates to a decontamination electrolyte and a decontamination method. The decontamination electrolyte comprises nitric acid, nitrate and oxalate. The final volume percentage of the nitric acid ranges from 5% to 15%, the final concentration of the nitrate ranges from 15g / L to 25g / L, and the final concentration of the oxalate ranges from 1g / L to 5g / L. The decontamination electrolyte can efficiently remove radioactive contaminants on the surface of a metal workpiece through the reasonable proportions of the nitric acid, the nitrate and the oxalate and the synergistic effect of the components.

The invention discloses a movable sorting apparatus for radioactive soil. The movable sorting apparatus is characterized by comprising a drying and screening device, an online detecting device, a cleaning and drying device, a separator plate mechanism, a soil sorting device and a packaging device. The drying and screening device is used for drying soil and separating stone from soil. The on-line detecting device detects the radioactivity degree of soil and sends a command signal to the separator plate mechanism and the soil sorting device. The separator plate mechanism separates soil with different radioactivity degrees through four different separator plates. The soil sorting device uses four different funnels and corresponding containers for collecting and buffering soil, and then the containers full of soil are pushed onto a conveyor belt by rack push rods, then transported to the packaging device by the conveyor belt for packaging work and finally transported out by the conveyor belt. The movable sorting apparatus of the invention sorts soil according to the radioactivity degree of contaminated soil, and performs targeted treatment on soil with different radioactivity degrees,so treatment efficiency is greatly improved and treatment cost is effectively reduced. At the same time, the apparatus can be disassembled and assembled, and can be fixedly connected with a containerthrough the rack and then be transported to a desired place via the container, is applicable to emergency treatment of radioactive pollutants, and has the advantages of flexibility, convenience and great economic value and strategic significance.

A wipe sampling device of radioactive contaminants on surface of spent nuclear fuel storage canisters is revealed. The wipe sampling device of radioactive contaminants takes samples from the storage canister to get at least one sample for monitoring radioactive contamination on the surface of the canister. The sampling device mainly includes a sample stick and a tube. The sample stick disposed in the tube is used to take samples from the surface of the canister. The wipe sampling device of radioactive contaminants on surface of the canister provides an effective sampling method for remote detection of canister contamination and ensures accuracy and representation of the detection results.

The invention relates to a decontamination electrolyte and a decontamination method. The decontamination electrolyte comprises nitric acid with the final mass percentage of 4-8%, nitrate with the final concentration of 10-35g / L and oxalate with the final concentration of 3-9g / L. Through joint efforts of the nitric acid, the nitrate and the oxalate, the decontamination electrolyte can efficiently remove radioactive pollutants on the surface of metal. Moreover, the decontamination electrolyte is compatible with a radioactive waste liquid treatment system, a small amount of secondary waste liquid is generated, the decontamination effect is good, and waste liquid can be conveniently treated.

The invention discloses a treatment technology of low-content radioactive pollutants in rare-earth smelting wastewater, and belongs to the technical field of radioactive wastewater treatment. According to the technology, the rare-earth smelting wastewater is adjusted to be neutral or slightly alkaline, and barium ions and sulfate ions are added, so that radium and other radioactive substances in the wastewater are primarily removed through co-precipitation; by adding a flocculating agent, precipitation is accelerated, and the time and cost required by precipitation are reduced; at the same time, a small part of low-content radioactive substances still existing after precipitation are further adsorbed and removed by using a fixed activated carbon adsorption bed, and after technical treatment, the radioactive substances in the wastewater can be discharged up to the standard. According to the technology, the characteristics of different treatment modes are fully utilized, the process costis reduced and the treatment efficiency are improved while the low-content radioactive pollutants in the wastewater are reduced and removed, and the application value is remarkable.

The invention relates to a preparation method of a garbage and sewage heavy metal degradation agent. A formula of the degradation agent comprises the following components in percentage by weight: 0.5to 1.5 percent of corn peptide, 0.3 to 1.3 percent of klebsiella oxytoca, 0.2 to 1.2 percent of black fungus, 1.6 to 2.6 percent of streptomyces jingyangensis, 2.2 to 2.2 percent of dismutase, 1.2 to2.5 percent of sodium dihydrogen phosphate, 0.1 to 1.1 percent of sodium chloride, 0.8 to 1.8 percent of potassium chloride, 0.9 to 1.9 percent of rhizoma fagopyri cymosi, 2 to 3 percent of soybean isoflavone, 1.9 to 2.9 percent of sodium diacetate, 2.5 to 3.5 percent of radix melastomae, 0.6 to 1.6 percent of ammonium propionate, 0.7 to 1.7 percent of herba pogostemonis extract, 1 to 2 percent ofnitrogen fixation actinomyces, 2.1 to 3.1 percent of bacillus licheniformis, 1.9 to 2.9 percent of zinc sulfate, 2.3 to 3.3 percent of radix pteroxygoni giraldii and 77.2 to 59.9 percent of water. The garbage and sewage heavy metal degradation agent has relatively good effects of removing bacteria, deodorizing, removing fluorine, aluminum and chromium, removing oil, removing turbidity, removing heavy metal and removing radioactive pollution substances.

A wipe sampling device of radioactive contaminants on surface of spent nuclear fuel storage canisters is revealed. The wipe sampling device of radioactive contaminants takes samples from the storage canister to get at least one sample for monitoring radioactive contamination on the surface of the canister. The sampling device mainly includes a sample stick and a tube. The sample stick disposed in the tube is used to take samples from the surface of the canister. The wipe sampling device of radioactive contaminants on surface of the canister provides an effective sampling method for remote detection of canister contamination and ensures accuracy and representation of the detection results.

The invention discloses a process unit for removing radioactive pollutants from drinking water. The process unit comprises a pre-filter, an ultrafiltration filtrator, a secure filter, a reverse osmosis filter set, a water yielding tank, a sterilization disinfector and a radioactive pollutant collector, wherein the pre-filter consists of one, two or three of media filters, self-cleaned filters and precise filters, the reverse osmosis filter set is made up of a plurality of series and parallel connected reverse osmosis membrane elements, and a radioactive pollutant concentrating and collecting system consists of concentrated water concentrating equipment and the radioactive pollutant collector. According to the process unit, a standard modular design is adopted, the mounting is convenient, the operation and maintenance are simple, the water treatment is thorough, the water purification effect is good, and the radioactive pollutants can be effectively removed from the drinking water, so that the process unit is particularly applicable to regions, of which water sources suffer from radioactive pollution.

The invention relates to the technical field of radioactive waste treatment devices, and discloses an online detection and sorting system for radioactive pollutants. Through the synergistic effect ofa material distributing assembly and a transferring assembly, materials can be distributed and transferred to different positions, a feeding hopper is located in the middle of a conveying belt, a second radiation detector can be arranged at the upstream position for background measurement, environmental interference is eliminated to improve radiation detection reliability, interference is eliminated to improve the radiation detection reliability, and a mechanism for flattening the materials is further arranged between the feeding hopper and a first radiation detector to avoid stacking of the to-be-detected materials. In an online detection and sorting method for the radioactive pollutants, by controlling the beat of a motor and then combining the synergistic effect of the material distributing assembly and the transferring assembly, accurate demarcation of polluted materials and non-polluted materials can be ensured, thus fixed-distance operation of the conveying belt and batched sorting of the materials are realized, then reliable measurement and accurate sorting of online detection and sorting of the radioactive pollutants are realized, and the great popularization value and wideapplication prospects are realized.