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46results about How to "Reduce radioactive contamination" patented technology
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Process for extracting and separating thorium and extracting rare earth chloride from sulfuric and phosphoric mixed acid system
InactiveCN1394971AReduce radioactive contaminationReduce negative impactRadium compoundsRare earth metal compoundsKeroseneFractionation
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.
Owner:CHANGCHUN INST OF APPLIED CHEMISTRY - CHINESE ACAD OF SCI
Method for producing nanometer humus refined powder
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.
Owner:ZHEJIANG FENGYU ECOLOGICAL TECH CO LTD
Emulsion whitening agent for ceramic and preparation method thereof
InactiveCN103880475AReduce radioactive contaminationUnchanged structureAluminum Hydroxide HydrateAluminium hydroxide
The invention relates to the field of a ceramic product, and particularly relates to an emulsion whitening agent for ceramic and a preparation method thereof. The emulsion whitening agent for the ceramic consists of the following raw materials in parts by weight: 60-98 parts of zirconium silicate and 2-40 parts of a dopant mixture. The preparation method comprises the steps of wet-mixing active aluminum oxide or / and aluminum hydroxide hydrate as well as active silica powder or / and metasilicic acid and sodium carbonate according to the parts in weight so as to form the dopant mixture; wet-mixing zirconium silicate and the dopant mixture according to the parts in weight, grinding to 325 meshes, drying and then adding into a kiln, roasting under a micro-pressure of 0-0.2 Mpa, cooling and then wet-grinding, drying and packaging. The emulsion whitening agent for the ceramic provided by the invention is used for replacing the existing generally-used zirconium silicate so as to lower the cost of a ceramic enterprise, save limited zircon sand resources and reduce radioactive pollution of the ceramic.
Owner:JIANGSU MIRAFUL NANO MATERIAL CO LTD
Radioactive isotope neutron source and preparation method thereof
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.
Owner:北京树诚科技发展有限公司
Manufacturing method of high-intensity environmental-friendly board
ActiveCN104760113AIncrease added valueHigh technology contentSolid waste managementLaminationRadioactive contaminationHigh intensity
Owner:河北宜美康环保科技股份有限公司
Efficient filter shell of nuclear power plant and recycling method thereof
PendingCN109273126AShorten the production cycleIncrease productivityRadioactive decontaminationNuclear powerRadioactive contamination
The invention discloses an efficient filter shell of a nuclear power plant and a recycling method thereof. The recycling method of the efficient filter shell of the nuclear power plant comprises the following steps of: disassembling a filter plate and mounting plate on a used efficient filter shell; peeling off the filter material on the filter plate; respectively measuring the radioactive pollution of the filter plate and mounting plate; if the radioactive pollution of the filter plate is less than a release value, adhering the filter plate with a new filter material to assemble into a new efficient filter shell for repeated use; If the radioactive pollution of the mounting plate is less than a release value, assembling the mounting plate into a new efficient filter shell for repeated use. The cost of inventory and replacement is saved, the production period is shortened, and the production efficiency is improved; the efficient filter shell is repeatedly utilized, so that the volume of radioactive wastes can be reduced, the environmental benefit and the responsibility for society can be fully embodied, and certain economic benefits can be generated; meanwhile, the method has important significance for protecting environment and reducing radioactive pollution.
Owner:LINGDONG NUCLEAR POWER +5
Evaluation method for initiative emission decision of containment vessel in nuclear power plant
ActiveCN104504259ARelieve excess pressureMitigating the Hydrogen ThreatSpecial data processing applicationsHydrogenNuclear power
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.
Owner:NUCLEAR POWER INSTITUTE OF CHINA
Fluorescence three-dimensional imaging tumor available receptor density quantitative method based on PET guide irradiation
InactiveCN104939852AOvercomes the disadvantage of requiring separate injections at regular intervalsSimplify complexityRadiation diagnosticsHigh energyFluorescence
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.
Owner:XIDIAN UNIV
Waste liquor sampling device
ActiveCN103424282ASmall doseReduce radioactive contaminationWithdrawing sample devicesProcess engineeringRadioactive waste
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.
Owner:CHINA INSTITUTE OF ATOMIC ENERGY
Method for recycling pre-filter frame of nuclear power plant
PendingCN109273127AShorten the production cycleReduce volumeRadioactive decontaminationNuclear plantNuclear power
The invention discloses a method for recycling a pre-filter frame of a nuclear power plant, which comprises the following steps of: peeling off the used pre-filter frame and filter material; measuringthe radioactive contamination of the pre-filter frame; if the radioactive contamination of the pre-filter frame is less than a release value, bonding the pre-filter frame with a new filter material for recycling. Because the filter material which is polluted by filtering is peeled off from the pre-filter frame, the radioactive contamination of the pre-filter frame is measured, and the pre-filterframe with a radioactive contamination without exceeding a release value can be recycled, the pre-filter frame which is not radioactively polluted or has less pollution can be recycled, inventory andreplacement costs of spare parts are saved, the production cycle is shortened and the production efficiency is improved; the pre-filter frame is recycled, the volume of the radioactive waste can be reduced by about 80%, the environmental benefit and the responsibility for the society can be fully embodied, and certain economic benefits can be generated; meanwhile, the method has important significance for protecting environment and reducing radioactive pollution.
Owner:LINGDONG NUCLEAR POWER +5
Perspective positioner
InactiveCN102068273AReduce the chance of infectionImprove irradiation efficiencyPatient positioning for diagnosticsRadiation safety meansPlastic materialsX-ray
The invention relates to a perspective positioner with a positioning function and a protective isolation function. The positioner is in a cover shape which is consistent with that of a receiver or a transmitter of an X-ray machine, comprises a positioning part, a cover surface, a cover edge and a cover edge bayonet, is made of a plastic material which X-rays can permeate, is positioned in the geometric center of the cover surface and is vertical to the cover surface. The positioner on the cover of the X-ray machine can acquire an accurate and satisfying image as long as the positioning part is aligned with an area which is needed to be irradiated to perform perspective shooting; and the positioner is sterile and can prevent an operation area from being polluted by the X-ray machine so as to greatly improve an accurate imaging rate and reduce the infection probability to the greatest extent.
Owner:孙小东
Cement-based polymer mortar specially used for repairing and preparation method of mortar
The invention discloses cement-based polymer mortar specially used for repairing and a preparation method of the mortar, and relates to the technical field of building mortar. The mortar comprises thefollowing raw materials: Wudalianchi volcanic mud, modified composite mineral micropowder, phosphogypsum residues, sodium-based bentonite, diabase fibers, aminopropyltriethoxysilane, a silicone resinpolyether emulsion, sodium tripolyphosphate, polyacrylamide, calcium chloride, an adhesion auxiliary agent, a water reducing agent, a foaming agent and an anti-irradiation agent; and the mortar is prepared by performing mixing and grinding on the raw materials. The mortar disclosed by the invention is simple and convenient for preparation, and has the characteristics of excellent workability, volume structure stability, high compressive bonding strength, shock resistance, cracking resistance, seepage resistance, freeze resistance, corrosion resistance and the like; and the mortar has remarkably improved application durability, long service life and a wide range of application.
Owner:合肥市闵葵电力工程有限公司
Method for preparing nuclear-pure thorium tetrafluoride from thorium oxalate through purification
ActiveCN106629807AMeet the purity requirementsReduce radioactive contaminationRadium compoundsHigh concentrationSlag
The invention provides a method for preparing nuclear-pure thorium tetrafluoride from thorium oxalate slag through purification. The method comprises the following steps: (1) dissolving thorium oxalate in nitric acid after alkali conversion; (2) reducing tetravalent cerium with hydrogen peroxide, extracting uranium with low concentration TBP and extracting thorium with high concentration TBP; (3) precipitating and dehydrating thorium tetrafluoride. The thorium tetrafluoride prepared and obtained by a set of technological method from conversion of thorium oxalate slag to extraction and preparation of thorium tetrafluoride in the invention meets standards of raw materials for a molten salt reactor, has the experimental transformation ability reaching the kilogram level, and has the production capacity easy to expand.
Owner:CHINA NUCLEAR BAOTOU GUANGHUA CHEM IND
Cleaning agent for removing radioactive contaminants and preparation method thereof
PendingCN109536308AReduce corrosionEasy to useOrganic non-surface-active detergent compositionsCleaning and washing methodsSolventCorrosion
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.
Owner:沈阳泰琦科技有限公司
Freely combined low enriched uranium foil target with multiple single pieces
InactiveCN109147965AEnsure radiation safetySimple manufacturing processOptical rangefindersFuel elementsRadioactive agentIrradiation
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.
Owner:CHINA INSTITUTE OF ATOMIC ENERGY
Online foreign matter removing device for tobacco shred making
PendingCN107617580AImprove accuracyImprove work efficiencyTobacco preparationSortingForeign matterX-ray
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.
Owner:CHINA TOBACCO HENAN IND
Three-color energy-storage luminescent composite wood-grain stone material
InactiveCN104829166AGood light transmission performanceImproves strength and wear resistanceTitanium dioxideRadioactive contamination
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.
Owner:WUDING COUNTY STONE CO LTD TIAN HAO
Ceramic whitening agent
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.
Owner:QINGDAO XIANGHAI ELECTRONICS
Protective device and method for uranium enrichment plant material container disassembly and assembly operation
InactiveCN109646983AWon't escapeReduce radioactive contaminationDispersed particle filtrationVapor condensationRadioactive contaminationEngineering
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.
Owner:中核第七研究设计院有限公司
High-performance composite heat insulation mortar and preparation method thereof
The invention discloses high-performance composite heat insulation mortar and a preparation method thereof and relates to the technical field of heat insulation materials. The mortar is prepared fromthe following raw materials: Zhanjiang volcanic mud, blast furnace slag, modified pitchstone powder, faujasite, bauxite, sodium bentonite, composite mineral fibers, lignin, EVA emulsion, sodium polyacrylate, triethanolamine, trimethylolpropane, a dispersant, a thickening time control agent and an anti-freezing agent. The preparation method of the high-performance composite heat insulation mortar is characterized by mixing and grinding the raw materials to prepare the high-performance composite heat insulation mortar. The heat insulation mortar is simple and convenient to prepare, long in service life and wide in application, and has the characteristics of excellent workability, volume structure stability, high compressive adhesion strength, seismic resistance, cracking resistance, permeation resistance, freezing resistance and corrosion resistance; the application durability of the heat insulation mortar can be obviously improved.
Owner:合肥聪亨新型建材科技有限公司
Method for detecting 1-hydroxy ethylene-1, 1-diphosphonic acid
InactiveCN1670510AReduce dosageLow priceChemical analysis using titrationMaterial analysis by observing effect on chemical indicatorTitration curveTest light
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.
Owner:XIAMEN UNIV +1
Low level radioactive waste liquid adsorption-solidification integrated treating system and technology
InactiveCN103500594AReduce the number of devicesReduce radioactive contaminationRadioactive decontaminationMetakaolinRadioactive contamination
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.
Owner:SOUTHWEAT UNIV OF SCI & TECH
While-drilling controllable source density logging device
PendingCN110056341AImprove detection accuracyReduce radioactive contaminationSurveyConstructionsHigh energyHigh pressure
The invention relates to a while-drilling controllable source density logging device, which comprises an independent while-drilling controllable neutron source and a while-drilling density detection system. A radioactive source is a while-drilling controllable neutron source independent bin and comprises a while-drilling controllable source body, a neutron tube compressive cylinder and a shield, and the neutron source is mounted in the neutron tube compressive cylinder; the while-drilling density detection system comprises a detector body, a near-source-distance detector, a thermal neutron detector, a far-source-distance detector, a central processing circuit and an ultrasonic hole diameter measurer; and the central processing circuit comprises a microprocessor, a signal amplification, shaping and screening circuit, a storage, an interface circuit, a bus driver and a bus. The while-drilling controllable source is mounted in the neutron tube compressive cylinder and the while-drilling controllable source body, the independent while-drilling controllable neutron source is formed, during high-voltage powering-on, high-energy fast neutrons are stimulated, in the process that the fast neutrons penetrate through a stratum, gamma rays are attenuated, and attenuation of the gamma rays also mainly depends on the density of electrons constituting the stratum.
Owner:CHINA PETROCHEMICAL CORP +4
Circulation loop for preparing I-125 through reactor irradiation
InactiveCN110648779ASafe and efficient complete transferSimple structureSpecific isotope recoveryConversion in nuclear reactorThermodynamicsRadiation injury
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.
Owner:CHINA INSTITUTE OF ATOMIC ENERGY
Ecological cultivation medium with water retention, pollution control and nutrition functions
InactiveCN106472276APrevent compactionReduce fertilizationGrowth substratesCulture mediaSoil propertiesOrganic fertilizer
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.
Owner:苏州蓝士环保科技有限公司
Heatseal
ActiveUS10532115B2Easy to replaceReduce radiation exposureProcess control/regulationIsotope introduction to organic compoundsLine tubingProcess engineering
The present invention relates to systems and methods to facilitate replacement between runs of a kit or cassette from an automated radiosynthesis device located in a hot cell. The method and apparatus of the invention enable automated disconnection of the outlet line by sealing the tubing hermetically by means of heat and by cutting the tubing where it is sealed in such a way that there is no risk of environmental contamination with radioactive material. The invention enables disconnection of the outlet line without manual intervention before opening the shielded enclosure.
Owner:GE HEALTHCARE LTD
Electrochemical decontamination electrolyte and preparation method and application thereof
ActiveCN112176393AEasy to handleReduce radioactive contaminationRadioactive decontaminationOXALIC ACID DIHYDRATEElectrolytic agent
Owner:SICHUAN ENVIRONMENTAL PROTECTION ENG CO LTD CNNC
Uranium foil target member of low enriched uranium for irradiation production fission <99>Mo
ActiveCN106875999AReduce radioactive contaminationAvoid radioactive contaminationConversion in nuclear reactorRadioactive contaminationEngineering
The invention belongs to the technical field of target member preparation and discloses a uranium foil target member of low enriched uranium for irradiation production fission <99>Mo. The target member is of a sandwich-type structure and comprises an inner target cylinder, an outer target cylinder and uranium foil. The uranium foil is positioned between the inner target cylinder and the outer target cylinder. The internal diameter of the inner target cylinder is unchanged, the outer wall of the inner target cylinder is designed into a tapered structure with the conicity of 1:160. The uranium foil wraps the outer side of the inner target cylinder. The thickness of the uranium foil is 120-150[mu]m, the inner and outer surfaces of the uranium foil are plated with a fission recoil protection layer respectively, and the thickness of the protection layer is 12-18[mu]m. The outer diameter of the outer target cylinder is unchanged, the inner wall of the outer target cylinder is designed into a tapered structure, and the inner diameter and the inner wall conicity of the outer target cylinder are matched with the outer diameter and the outer wall conicity of the inner target cylinder respectively. The uranium foil target member has the beneficial effects that the target unbinding and melting is simple, the radiation efficiency is high and the radioactivity pollution can be reduced.
Owner:CHINA INSTITUTE OF ATOMIC ENERGY
Transfer and adsorption method for radioactive elements in tailings in high-cold and high-altitude areas
PendingCN113628778ALarge specific surface areaHigh mechanical strengthOther chemical processesAlkali metal oxides/hydroxidesMicrosphereSlurry
The invention relates to the field of radioactive pollutant removal, in particular to a transfer and adsorption method for radioactive elements in tailings in high-cold and high-altitude areas, which comprises the following steps: (S.1) tailings containing a radioactive element thorium are heated and dried, ground, and added with water to obtain tailing slurry; (S.2) the tailing pulp is immersed into a hydrofluoric acid-sulfuric acid system, so that the radioactive element in the tailings is leached out; (S.3) after the tailings are filtered out, adsorption microspheres are added into the leachate to adsorb the radioactive element; and (S.4) the adsorption microspheres are filtered out to complete the transfer of the radioactive element, wherein the adsorption microspheres in the step (S.3) are nano iron oxide / graphene oxide / chitosan composite microspheres. According to the method, leaching of the radioactive element thorium can be accelerated through the hydrofluoric acid-sulfuric acid system, meanwhile, the adsorption rate of thorium in the leachate can be greatly increased by adopting the nano iron oxide / graphene oxide / chitosan microsphere adsorption material, and efficient adsorption of the radioactive element thorium is achieved.
Owner:FUJIAN UNIV OF TECH
Radioactive gas fan and reactor radioactive gas trapping system
ActiveCN114033718AReduce risk of leakageReduce distractionsShieldingMechanical energy handlingNuclear radiationRadioactive gas
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.
Owner:CHINA INSTITUTE OF ATOMIC ENERGY
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