45results about How to "Reduce radioactive contamination" patented technology

The present invention belongs to a process for extracting and separating thorium from sulfo-phosphoric mixed acid and extracting rare earth chloride. Said process adopts primary amine added mixed alcohol as extracting agent, and makes direct fractionation of rare earth slurry to extract thorium, and the thorium content in the separated rare earth slurry is ThO2/REO is less than or equal to 5X10 to the minus sixth. Said invention utilizes the thorium being in organic phase and adopts countercurrent reextraction process by means of nitric acid to obtain thorium nitrate product, its purity is 99%, and thorium recovery is up to 99%. Said invention adopts magnesium oxide precipitation method to remove the iron and phosphorus in the rare earth reffinate, uses ammoniated P507-kerosene to extract organic phase.

The invention discloses a method for producing nanometer humus refined powder. The method for producing nanometer humus refined powder comprises the following production steps: raw material treatment: crushing brown coal into fine particles with a grain size smaller than 16 meshes through a crusher, then drying the fine particles to water content of 9 to 13 percent by using cold drying, and performing filtration and screening for future use; proportioning treatment: mixing brown coal with reagent according to a ratio of 100:1, and putting the proportioned materials into a grinder; grinding treatment: grinding the proportioned materials to a nanometer scale by using a planetary trajectory ball-milling equipment with balls and a cylinder which are made of special materials, emit less heat and dissipate heat quickly, so as to change molecular structures and generate nanometer humus medium powder in a machine body; packaging treatment: settling, outputting and packaging the nanometer humus powder to obtain the nanometer humus refined powder disclosed by the invention. The nanometer humus refined powder obtained through the method can be used for conditioning soil activity, controlling saline-alkali soil and sand soil, controlling heavy metal pollutants in soil, reducing radioactive contamination and purifying sewage.

The invention provides a radioactive isotope neutron source, which comprises a source core and a shell, wherein the source core is a ceramic body. The preferable source core of the neutron source comprises americium oxide and/or plutonium oxide and metal beryllium, wherein the granularity of the metal beryllium is between 100 and 200nm, and the americium oxide and/or the plutonium oxide and the metal beryllium are made into nanoscale particles by ball grinding in the preparation process. Additionally, the invention also provides a method for preparing the radioactive isotope neutron source. Because the source core is the ceramic body, the radioactive isotope neutron source has firm and stable source core, does not expand after being soaked in water and reduces the radioactive pollution. In addition, the nanoscale particles are formed in the source core by the ball grinding, so the internal metal beryllium particles are evenly distributed and have even sizes, and neutrons are evenly and stably output.

The invention discloses a manufacturing method of a high-intensity environmental-friendly board. The manufacturing method comprises the following steps: pretreatment of timber, preparation of main material, preparation of sizing agent, preparation of auxiliary material, preparation of base material and preparation of board material. By fully using tailings of an industrial and mineral industry, tailings of a timber processing industry, crop straw wastes and other natural raw materials, the purpose of consuming the least resource and energy is realized; meanwhile, a plurality of inorganic modified materials are added, and formed to be a high-intensity ecological environmental-friendly board through low-temperature die pressing in a certain ratio and self-condensing reaction of the material; the whole production process is low-carbon, environmental-friendly and energy-saving; the produced board is fireproof, insect-prevention, waterproof, high-intensity fracture resistance, aging resistance, and free from formaldehyde, methylbenzene and other harmful matters and also free from radioactive contamination; every performance quality is excellent.

The invention discloses an evaluation method for an initiative emission decision of a containment vessel in a nuclear power plant. The evaluation method comprises an overpressure threat relieving decision evaluation step and further comprises a hydrogen threat relieving decision evaluation step, an emission stopping decision evaluation step and a radioactive fission product release relieving evaluation step, wherein the overpressure threat relieving decision evaluation step comprises the steps of calculating an initiative emission radioactive dosage consequence desired value M1; firstly calculating the overpressure critical failure probability of the containment vessel when the M1 is equal to a no-emission radioactive dosage consequence desired value N1; then determining overpressure critical failure pressure F1 of the containment vessel; calculating a pressure recommended setting value F0 of the containment vessel after certain allowance is considered; requesting to execute initiative emission when the pressure of the containment vessel is up to the F0. The evaluation method disclosed by the invention is used for the initiative emission decision of the containment vessel under a serious accident, and provides decision basis for emergency command, containment vessel emission is initiatively carried out, overpressure or hydrogen threat of the containment vessel is relived, the releasing of fission products is relieved, and radioactive pollution after the serious accident can be reduced.

The invention discloses a fluorescence three-dimensional imaging tumor available receptor density quantitative method based on PET guide irradiation. Based on the phenomenon that rare earth doping objects are stimulated by high-energy rays emitted by a radioactive nuclide probe to emit fluorescence, a specific radiation nanometer molecular probe is constructed, fluorescence image information emitted by a target molecular probe is further used, PET image information of the nuclide probe serves as reference input for fluorescence three-dimensional imaging quantitative analysis, and therefore the aim of quantifying tumor available receptor density information is achieved. The method solves the problems that through an existing technology and an existing method, non-intrusive type living body quantifying on tumor area receptor density cannot be achieved, and meanwhile too-large radioactive pollution, complex experimental design and the like are avoided. The method has the advantages that non-intrusive type living body quantifying on the tumor area receptor density and metabolism information can be achieved at the same time, the radioactive pollution is small, and experiment operation is simple; the method can be applied to the field of medical optical imaging.

The invention belongs to the technical field of analysis and treatment of radioactive waste, and discloses a waste liquor sampling device. The device comprises a carrying and moving mechanism, an operation panel, a vacuum pump, a sampling tank and a buffer tank, wherein the operation panel, the vacuum pump, the sampling tank and the buffer tank are all fixed on the carrying and moving mechanism; the sampling tank is positioned under the buffer tank and is connected with the buffer tank through a pipeline; the vacuum pump is connected with the top of the buffer tank through a pipeline to pump negative pressure of the buffer tank and the sampling tank so as to enable waste liquor to get into the sampling tank from a waste liquor storage tank. The device has the advantages that the movement is convenient, the sampling is simple, and the quantitative sampling is realized.

The invention discloses the technical field of a cleaning agent, and particularly relates to the field of a cleaning agent for removing radioactive contaminants and a preparation method thereof. The cleaning agent is prepared from the following ingredients in parts by weight: 30 to 45 parts of an EHS0107 cleaning agent, 1.5 to 3 parts of a compounding agent and 100 to 300 parts of a solvent; undera room temperature condition, a steel plate material is subjected to one-step soaking, wherein the cleaning is performed for 1 h and the cleaning efficiency can reach 80 percent or more; production field equipment is subjected to one-step spray coating cleaning, wherein the cleaning is performed for 10 minutes and the cleaning efficiency can reach 50 percent or more; the characteristics of high efficiency, high speed, small substrate corrosion, convenient use and the like are realized; the radioactive contamination degree of steel and iron materials and the production field equipment is greatly reduced; the reutilization rate of the steel and iron materials and the production field equipment is improved; the radioactive contamination level is reduced; the work environment is improved; thebody health of operators is facilitated.

The invention belongs to the technical field of radioactive substance preparation, and relates to a freely combined low enriched uranium foil target with multiple single pieces. The freely combined low enriched uranium foil target is used for producing fission <99> Mo by means of irradiation. The freely combined low enriched uranium foil target comprises a target barrel, low enriched uranium foils, a target core plug, a pressure plug and sealing covers. The target core plug is placed in the hollow target barrel, so that the multiple pieces of freely combined low enriched uranium foils can be compressed between the inner wall of the target barrel and the target core plug; the target core plug is compressed by the pressure plug in the target barrel from the upper side of the target core plug; two ends of the target barrel are sealed by the sealing covers by means of welding. The freely combined low enriched uranium foil target with the multiple single pieces has the advantages that processes for preparing the freely combined low enriched uranium foil target can be simplified, the irradiation efficiency can be improved, self-shielding can be reduced, the freely combined low enriched uranium foil target is safe in reactor irradiation periods and is easy to release in follow-up procedures, and the quality of the produced <99> Mo can be guaranteed.

The invention discloses an online foreign matter removing device for tobacco shred making. The foreign matter removing device comprises a supporting machanism, a detection mechanism and a removal mechanism; the detection mechanism comprises an X-ray machine and a detection module composed of a plurality of detectors, wherein the X-ray machine is located above a conveyor belt, and the detection module is located below the conveyor belt; and the removal mechanism is located below the discharge end of the conveyor belt, and comprises a foreign matter remover and a remover bracket, wherein the foreign matter remover comprises a plurality of high-pressure nozzles, and electromagnetic valves each are arranged at the air inlet end of each of the high-pressure nozzles. The online foreign matter removing device has the advantages that foreign matters in the tobacco shred making process can be imaged and displayed so that online impurity identification and accurate removal can be more accuratelyrealized, the online identification and removal of magnetic, low-magnetic and non-magnetic metal objects can be realized at the same time, removal effect is good, precision is high, practicability ishigh, and quality of tobacco leaves and working efficiency of tobacco shred making are indirectly improved.

The invention belongs to the technology of processing of artificial stone materials and especially relates to a colorized three-color energy-storage luminescent composite wood-grain stone material and a preparation method of the same. The stone material includes following components, by weight: 4.5-7% of glass sand (which is granules after glass waste materials crushed), 12.5-15.5% of epoxy resin, 0.26-0.65% of a curing agent, 0.3-0.7% of a coupling agent, 4-6% of luminescent stone powder comprising three colors, wherein each color accounts for 1/3 of the total amount, 1.5-2.5% of titanium dioxide and the balance being a wood-grain stone waste material, wherein the granularity distribution of the glass sand is 2-70 meshes and the granularity distribution of the wood-grain stone waste material is 4-325 meshes. The cured moulded stone material is dried at 65-80 DEG C. The stone material is good in night luminescent effect, is high in strength, is colorful, is free or radiation pollution and is low in production cost.

The invention discloses a ceramic whitening agent. The ceramic whitening agent is characterized by comprises the following substances in parts by weight: 51-66 parts of zirconium silicate, 31-40 parts of feldspar, 2-3 parts of calcite, 10-18 parts of talc, 4-5 parts of zinc oxide, 4-6 parts of barium carbon, 0-5 parts of quartz powder, 0-5 parts of raw kaolin, 0-5parts of calcined kaolin, 50-99.5 parts of hydrated aluminum hydroxide, 15-40 parts of activated silicon micropowder, 3-5 parts of zirconium boride, 1.5-3.6 parts of nickel oxide, 1.5-2.8 parts of magnesium olivine and 0.6-4.8 parts of sodium carbonate serving as a mineralizer. The invention has the beneficial effects that the costs of ceramic enterprises are reduced, the limited zircon sand resource is saved and the radioactive contamination of the ceramic is reduced.

Relating to the technical field of material feeding and taking in uranium enrichment plants, the invention specifically discloses a protective device and method for uranium enrichment plant material container disassembly and assembly operation, and can achieve evacuation blow-wash on a container connecting tube during disassembly and assembly of a material container in a material feeding and taking plant. According to the protective device provided by the invention, in the whole disassembly and assembly process, the residual harmful gas in the container connecting tube does not escape into theplant, and is condensed by a freezer of the device, and is further captured and purified by an adsorption tower and a filter, thus greatly reducing the radioactive contamination of the plant.

This invention relates to hydroxyl-ethidene diphosphoric acid test method, which comprises the following steps: adding buffer, shield and indicating agents into the HEDP solution and dripping solution to test the light absorption degree and make dripping curve and figure out dripping agent volume V and make standard working curve; adding buffer, shield and indicative agents in the sample to test light absorption degree to make dripping curve and to figure out volume Vx, and to figure out the HEDP concentration by the standard working curve; the concentration degree multiplies the diluting times to get the effective content of HEDP.

The invention discloses a low level radioactive waste liquid adsorption-solidification integrated treating system which comprises a low level radioactive waste liquid pool, an adsorption device, a purification water pool, an alkali-activator container and a metakaolin container. The low level radioactive waste liquid pool is communicated with the waste liquid inlet of the adsorption device, the purification water pool is communicated with the purification water outlet of the adsorption device, and the alkali-activator container and the metakaolin container are communicated with the alkali-activator inlet and the metakaolin inlet of the adsorption device respectively. The invention further discloses a low level radioactive waste liquid treating technology which comprises the steps of raw material preparation, adsorption and purification, alkali-activated zeolite and polymerization and solidification. The low level radioactive waste liquid adsorption-solidification integrated treating system is small in equipment number, simple in corresponding treating method and technology, and small in radioactive contamination. The low level radioactive waste liquid treating method can fully activate the activity of sliicon-alumininm in the zeolite, and can enhance the performance of the geopolymer solidified body remarkably.

The invention discloses a circulation loop for preparing I-125 through reactor irradiation. The circulation loop comprises a loop pipeline, an irradiation part, a recovery device, a gas blocking device, a raw material gas cylinder, a tail gas purification device and a molecular pump, wherein an electromagnetic valve is arranged on the loop pipeline so as to carry out node control; the irradiationpart, the recovery device, the gas blocking device, the raw material gas cylinder, the tail gas purification device and the molecular pump are all connected to the loop pipeline; and the irradiation part is arranged in a reactor. The beneficial effects of the invention are as follows: the loop system is used for controlling the amount of the raw material gas filled in the irradiation bottle, so that the preparation yield of <125>I can be accurately controlled, and the automatic control effects of high irradiation efficiency, good irradiation safety of thecirculation loop, little radioactive pollution and little radiation injury to operators during <125>I reactor irradiation production are achieved. The input amount of the raw material target gas can be determined according to the yield requirement, and continuous circulation and intermittent circulation can be carried out according to the yield requirement.

The invention provides an ecological cultivation medium with water retention, pollution control and nutrition functions. The ecological cultivation medium has functions of retaining water, resisting drought, improving soil property and supplying rich nutrients. The ecological cultivation medium is characterized by being prepared from 1-20 parts of a conditioner, 20-70 parts of organic fertilizer, 20-70 parts of turfy soil, 1-5 parts of vermiculite, 1-5 parts of medical stone and 1-5 parts of 0.15% formalin aqueous solution.

The embodiment of the invention provides a radioactive gas fan and a reactor radioactive gas trapping system, relates to the technical field of nuclear radiation safety, and is used for solving the problem that a fan in the related technology cannot meet the requirement for radioactive gas conveying. The radioactive gas fan provided by the embodiment of the invention comprises an isolation sleeve, a rotor assembly and a magnetic driving device. An air inlet and an air outlet are formed in the isolation sleeve, and the isolation sleeve is made of an anti-radiation material. The rotor assembly is arranged in the isolation sleeve, the magnetic rotor assembly comprises a magnetic rotor and blades, and the magnetic rotor is fixedly connected with the blades. The magnetic driving device is arranged outside the isolation sleeve corresponding to the magnetic rotor, the magnetic driving device is fixed with the isolation sleeve, and the magnetic driving device is used for generating a magnetic field to drive the magnetic rotor to rotate so that the blade drives the radioactive gas in the isolation sleeve to flow from the air inlet to the air outlet. The radioactive gas fan is used for providing power for transmission of the radioactive gas.