Product
Patsnap Eureka
For R&D, Patsnap Eureka makes reading and utilizing patents & technical documents easy.
Patsnap Eureka AIR
Designed for self-driven R&D workflows. Generate viable solutions, solve complex R&D challenges, empower your innovation with AI.
Patsnap Eureka Materials
Designed for material experts only. Revolutionize your material R&D, from search, analyze, to developing new materials.
Feature
TechResearch
Generate reliable direction feasibility study reports for your R&D in just a few steps.
TechSeek
Discover and master advanced knowledge NOW. Basics, ideas, possibilities, all at once.
TechMind
As an expert in R&D Theories, TechMind can generates customized viable solutions instantly.
TechRisk
Analyze your overall solution with one click, know your potential R&D risks in advance.
TechMonitor
Get weekly tech updates, stay abreast of the latest tech innovations and key insights.
Patents
Literature
Hiro is an intelligent assistant for R&D personnel, combined with Patent DNA, to facilitate innovative research.
67 results about "Tritiated water" patented technology
Efficacy Topic
Property
Owner
Technical Advancement
Application Domain
Technology Topic
Technology Field Word
Patent Country/Region
Patent Type
Patent Status
Application Year
Inventor
Tritiated water is a radioactive form of water where the usual protium atoms are replaced with tritium. In its pure form it may be called tritium oxide (T₂O or ³H₂O) or super-heavy water. Pure T₂O is corrosive due to self-radiolysis. Diluted, tritiated water is mainly H₂O plus some HTO (³HOH). It is also used as a tracer for water transport studies in life-science research. Furthermore, since it naturally occurs in minute quantities, it can be used to determine the age of various water-based liquids, such as vintage wines.
Process for tritium removal from light water
InactiveUS20070246344A1Simpler to start-up and shutdown and operateSmall elemental hydrogen isotope inventoryCombination devicesDistillation in boilers/stillsElectrolysisDistillation
A process for light water detritiation comprised of water distillation for tritium stripping and enriching, followed by chemical conversion of tritium enriched water to elemental hydrogen, and finally by one or more thermal diffusion columns for final tritium enrichment. The combination of process steps takes advantage of water distillation large throughput capability at low tritium concentration with the simplicity of thermal diffusion for small throughput final tritium enrichment. The water distillation front-end and the thermal diffusion back end processes are compatible with any intermediate chemical conversion process such as electrolysis or water gas shift reaction to convert tritiated water to elemental hydrogen.
Owner:GE HEALTHCARE LTD
Advanced Tritium System and Advanced Permeation System for Separation of Tritium from Radioactive Wastes and Reactor Water
InactiveUS20110243834A1Reduce the amount of waterIncrease concentrationIsotope separationWater/sewage treatment by ion-exchangeRadioactive wastePermeation
Systems, methods, and apparatuses for separating tritium from radioactive waste materials and the water from nuclear reactors. Some embodiments involve the reaction of tritiated hydrogen gases with water in the presence of a catalyst in a catalytic exchange column, yielding a more concentrated and purified tritiated water product. Some embodiments involve the use of a permeation module, similar in some respects to a gas chromatography column, in which a palladium permeation layer is used to separate tritiated hydrogen gas from a mixture of gases.
Owner:KURION INC
Process for tritium removal from water by transfer of tritium from water to an elemental hydrogen stream, followed by membrane diffusion tritium stripping and enrichment, and final tritium enrichment by thermal diffusion
ActiveUS20100239481A1Economical and simpleSimpler to start-up and shutdown and operateTransuranic element compoundsRadium compoundsDiffusionMembrane diffusion
A diffusion based process for tritium removal from water by tritium transfer from water to an elemental hydrogen stream, followed by a membrane diffusion cascade for tritium stripping and enrichment, and final tritium enrichment by one or more thermal diffusion columns. The combination of process steps takes advantage of membrane diffusion's large throughput capability at low tritium concentration with the simplicity of thermal diffusion for small throughput final tritium enrichment. The membrane diffusion stages use supported or unsupported microporous or hydrogen permeable metal membranes (such as Pd / Ag alloy). The diffusion process is compatible with any front-end process to transfer tritium from tritiated water to elemental hydrogen. The process may be designed and operated at low pressure, with small gas inventory, and no inherent overpressure hazard.
Owner:BWXT NUCLEAR ENERGY CANADA INC
Process for tritium removal from light water
InactiveUS7470350B2Simpler to start-up and shutdown and operateSmall elemental hydrogen isotope inventoryCombination devicesHydrogen separationElectrolysisDistillation
Owner:GE HEALTHCARE LTD
On-site calibration device of airborne tritium monitoring instrument
InactiveCN104536028AIncrease contact areaLarge dispersion areaX/gamma/cosmic radiation measurmentWater vaporStandard uncertainty
The invention discloses an on-site calibration device of an airborne tritium monitoring instrument. The on-site calibration device of the airborne tritium monitoring instrument comprises an air processor, a bubbling unit, a transmission instrument, an aspirator pump and a recovery unit, all of which are sequentially connected, wherein the air processor is used for filtering and drying inlet air, the bubbling unit is used for bubbling tritiated water to form saturated tritium flow, the transmission instrument is used for being connected with a calibrated detection instrument and measuring the activity and concentration of the tritium flow generated on site, the aspirator pump is used for pumping the tritium flow into the recovery unit for recovery after the activity and concentration of the tritium flow generated on site are detected, and the recovery unit is used for cooling and recovering the recovered tritium flow. The ranges of the activity and concentration of the tritium flow generated by the on-site calibration device of the airborne tritium monitoring instrument in a bubbling mode depend on the total activity of the tritium flow for bubbling and can meet the calibration of most existing nuclear facilities using the measuring span of the tritium monitoring instrument. The uncertainty of the synthesis standard of the activity and concentration of the bubbled tritium flow is less than or equal to 10 percent, and the recovery rate of the tritiated water vapor by the recovery unit is more than 99 percent.
Owner:NUCLEAR POWER INSTITUTE OF CHINA
Advanced Tritium System for Separation of Tritium from Radioactive Wastes and Reactor Water in Light Water Systems
InactiveUS20130336870A1Process stabilityIncrease wasteSpecific isotope recoveryTransuranic element compoundsElectrolysisHydrophobic polymer
Systems, methods, and processes for a high throughput, low concentration processing of low activity tritiated light water include the electrolysis of at least some of the tritiated water to produce hydrogen and tritium gas. The hydrogen and tritium gas produced by electrolysis in some cases are combined with heated water vapor to increase throughput and passed through a liquid phase catalytic exchange column, which generally includes a catalyst that includes palladium coated with a hydrophobic polymer. As the hydrogen and tritium gas, along with heated water vapor, rise through the LPCE column, the tritium is retained on the catalyst. Deionized wash water passes down the column (i.e., in the opposite direction of the flow of the hydrogen gas and heated water vapor) and carries the retained tritium out of the LPCE column. Useful in separating tritium from radioactive waste materials and from the water from nuclear reactors.
Owner:KURION INC
Device of recycling tritium from tritiated water and implementation method of same
The invention discloses a device of recycling tritium from tritiated water, which includes, in a successively connected manner through pipelines, a gas circulating pump, a buffer tank filled with an inert carrier gas, a tritiated water storage tank filled with the tritiated water, a first water decomposing bed filled with iron powder, a first adsorption bed filled with a 5A molecular sieve, and a first hydrogen storage bed filled with a zirconium-series hydrogen-storing alloy. The first hydrogen storage bed is also back-connected to the gas circulating pump. The device is compact in structure, is low in cost, is convenient to use, can be used for recycling the tritium from tritiated water continuously without generation of solid waste, and has excellent practical and popularizing values.
Owner:MATERIAL INST OF CHINA ACADEMY OF ENG PHYSICS
Process for tritium removal from water by transfer of tritium from water to an elemental hydrogen stream, followed by membrane diffusion tritium stripping and enrichment, and final tritium enrichment by thermal diffusion
ActiveUS7815890B2Economical and simpleSimpler to start-up and shutdown and operateIsotope separationHydrogen isotopesDiffusionMembrane diffusion
A diffusion based process for tritium removal from water by tritium transfer from water to an elemental hydrogen stream, followed by a membrane diffusion cascade for tritium stripping and enrichment, and final tritium enrichment by one or more thermal diffusion columns. The combination of process steps takes advantage of membrane diffusion's large throughput capability at low tritium concentration with the simplicity of thermal diffusion for small throughput final tritium enrichment. The membrane diffusion stages use supported or unsupported microporous or hydrogen permeable metal membranes (such as Pd / Ag alloy). The diffusion process is compatible with any front-end process to transfer tritium from tritiated water to elemental hydrogen. The process may be designed and operated at low pressure, with small gas inventory, and no inherent overpressure hazard.
Owner:BWXT NUCLEAR ENERGY CANADA INC
Device for monitoring concentration of tritium with different forms in complex environment gas
ActiveCN105067777AConcentration measurementX/gamma/cosmic radiation measurmentMaterial analysisWater concentrationCatalytic oxidation
The invention provides a system for monitoring concentration of tritium with different forms in complex environment gas. The system comprises a sampling device for sampling of environment gas, and further comprises a tritiated water concentration monitoring module connected to the sampling device and used for separating tritiated water from other gases in the environment gas and measuring the concentration of the tritiated water, and a reduced tritium concentration monitoring module connected to the tritiated water concentration monitoring module and used for performing catalytic oxidation on reduced tritium in the other gases to generate tritiated water, separating the oxidized tritiated water from the other gases, measuring the concentration of the oxidized tritiated water, and acquiring the concentration of reduced tritium according to the concentration of the oxidized tritiated water. Through the adoption of the system, the concentrations of both tritiated water and reduced tritium in the complex environment gas containing tritium with different forms and various radionuclides can be measured.
Owner:SHANGHAI INST OF APPLIED PHYSICS - CHINESE ACAD OF SCI
Treatment device for tritium gas and tritiated water
InactiveCN105741898AReduce poisonReduce risk of exposureRadioactive decontaminationWater vaporCatalytic oxidation
The invention provides a treatment device for tritium gas and tritiated water, which integrates catalytic oxidation of the tritium gas with collection of tritiated water together, and can be used as a tritium sampler. The device comprises a tritium gas catalytic oxidation working room and a refrigeration system, wherein to-be-treated exhaust gas containing tritium firstly flows through the tritium gas catalytic oxidation working room; under the action of a catalyst, the tritium gas is subjected to catalytic oxidation to generate tritiated water vapor; the tritiated water vapor enters into a convection chamber of the refrigeration system and is quickly condensed to generate liquid tritiated water; the liquid tritiated water is collected by a collector. The treatment device for tritium gas and tritiated water, disclosed by the invention, can be directly connected to a tritium gas circulating front end of a purification system for treatment of the to-be-treated exhaust gas containing tritium, and also can be connected to a tritium circulating middle part of a nuclear facility, in order to monitor tritium in the nuclear facility environment in real time by catalyzing, condensing and collecting tritium in the atmosphere; meanwhile, the device is further applicable to emergency treatment for high radioactive tritium gas and tritiated water in the nuclear accident field.
Owner:INST OF NUCLEAR PHYSICS & CHEM CHINA ACADEMY OF
Systems and method for reducing tritium migration
ActiveUS20120106692A1Reducing tritium mitigationMoisture suppressionNuclear energy generationShieldingHermetic sealEngineering
A system and method for reducing tritium migration. In one aspect, the invention is a method of reducing tritium mitigation from a spent nuclear fuel pool containing a body of tritiated water having an exposed surface, the method comprising hermetically sealing the exposed surface of the body of tritiated water with a cover movable between an open-state and a close-state.
Owner:KEENAN JEFFRIE JOSEPH
Inter-well monitoring method for radioactive isotope
The invention belongs to the technical field of tracer test, and in particular relates to an inter-well monitoring method for radioactive isotope. The inter-well monitoring method for the radioactive isotope comprises the steps of obtaining a background sample; treating tritiated water as a radioactive isotope tracer agent and calculating the filling quantity of the tritiated water; transferring the tritiated water of which the filling quantity is calculated into a liquid releasing device; filling the tritiated water into a water filling well through the liquid releasing device; sampling from a monitoring oil well; processing the obtained oil-water sample and preparing into a detection-level sample; transferring the detection-level sample into a beta-ray detecting instruction for detecting to obtain detection data; further analyzing and processing; preparing a tracer agent response curve. According to the inter-well monitoring method for the radioactive isotope, the tritiated water is used as the radioactive isotope tracer agent; the radioactive isotope tracer agent has the advantages of being low in detection cycle, high in chemical and radiochemistry stability, free of attaching to rock and the oil well, and low in toxicity; a low background liquid scintiloscope and an ultralow background liquid scintiloscope is utilized to detect the strength of beta rays; therefore, the sensitivity of instruments is high; the experiment data are accurate.
Owner:TIANJIN DAGANG OILFIELD SHENGDA TECH
Method for detecting specific activity of tritiated steam in air
InactiveCN105842725AImprove collection efficiencyHigh precisionX/gamma/cosmic radiation measurmentMolecular sieveFreeze-drying
The invention discloses a method for detecting specific activity of tritiated steam in air. The method particularly comprises the steps of absorbing the tritium steam in air by means of a 3A molecular sieve, collecting tritiated water absorbed in the 3A molecular sieve through freezing and sublimating in a freeze drying device, performing absorption and micro-filtering on the collected tritiated water after collection, and detecting the specific activity of the tritiated water. Because the method of the invention realizes relatively high collecting efficiency on the tritiated water and small residual amount of sampling medium, the method can be used for collecting the tritiated water in the air. Furthermore the specific activity of the tritiated water can be detected on condition of relatively low specific activity and furthermore relatively high data precision is realized. The collecting efficiency of the method can reach 99%, and the residual amount of the sampling medium is lower than 1%.
Owner:NUCLEAR & RADIATION SAFETY MONITORING CENT OF SHANDONG PROVINCE
Tritium distillation device
InactiveUS7927463B2Simple structureEasy to assembleAuxillariesEvaporators/condensersWater sourceReactive distillation
Owner:INST NUCLEAR ENERGY RES ROCAEC
Method for separating tritiated water from light water
Provided is an industrially feasible method for separating tritiated water from light water.The method comprises:a step of removing tritiated water and heavy water from light water by adding heavy water to a liquid mixture containing tritiated water and light water,by converting into a gas hydrate consisting essentially of tritiated water and heavy water as the crystal structure under a condition of converting into the gas hydrate of at least one of heavy water and tritiated water, and yet keeping light water in the liquid state, anda step of separating tritiated water from heavy waterby breaking the gas hydrate structure containing tritiated water and heavy water, so as to get a liquid mixture,by converting the liquid mixture containing tritiated water and heavy water into a gas hydrate containing tritiated water in the crystal structure under a condition of converting into a gas hydrate containing tritiated water in the crystal structure and yet keeping heavy water in the liquid condition and then,by breaking the gas hydrate structure of tritiated water, so as to collecting tritiated water in that order.
Owner:GLOBAL CLEAN TECH INC +1
Advanced tritium system and advanced permeation system for separation of tritium from radioactive wastes
ActiveUS20160310898A1Specific isotope recoveryWater treatment parameter controlHydrogenRadioactive waste
A liquid phase catalytic exchange column with a catalyst is configured to receive hydrogen gas. The system uses the catalyst to exchange the hydrogen gas with the tritiated source yielding HT gas and tritiated water. The system monitors tritium content of the tritiated water. When a predetermined tritium level is detected, the tritiated water is released. The system also includes a gaseous permeation system comprising a permeable barrier for the selective extraction of gases.
Owner:VEOLIA NUCLEAR SOLUTIONS INC
Gaseous tritiated water online detection system based on plastic scintillator
InactiveCN108646282AQuick responseEasy to measureX/gamma/cosmic radiation measurmentScale unitTritiated water
The invention provides a gaseous tritiated water online detection system based on a plastic scintillator. By using the system, the activity of gaseous tritiated water can be measured in real time. According to the system, a pump is used for extracting a gaseous tritiated water sample from a sampling area and sending the gaseous tritiated water sample into a purification separator, the gas subjected to purification and separation is sent into a detection region, and the activity of tritiated water can be obtained in real time. The system comprises a sampling unit, a purification and separationunit, a measurement unit and a control unit. The gaseous tritiated water online detection system can measure gaseous tritiated water samples in various activities in real time, and has the advantagesof being short in measurement time and rapid in reaction. The problem about measuring tritium in real time is solved. The system further has the advantages of being easy to operate, capable of achieving software control and the like.
Owner:安徽伯华氢能源科技有限公司
Tritiated water preparation apparatus and method
The invention relates to a tritiated water preparation apparatus and method, and belongs to the field of tritiated water preparation. The tritiated water preparation apparatus comprises a tritium storage metal tank, a first gas mass flow controller, an oxygen bottle, a second gas mass flow controller, a tritium and oxygen composite catalytic reactor, a cold trap, a tail gas collecting tank and a vacuum pump, the tritium storage metal tank communicates with the first gas mass flow controller, the oxygen bottle communicates with the second gas mass flow controller, the first gas mass flow controller and the second gas mass flow controller respectively communicate with the tritium and oxygen composite catalytic reactor, the tritium and oxygen composite catalytic reactor communicates with the cold trap, and the tail gas collecting tank and the vacuum pump respectively communicate with the cold trap. The tritiated water preparation method comprises working steps of the apparatus. The tritiated water preparation apparatus and the tritiated water preparation method realize rapid compounding of tritium and oxygen, recycling of tail gas tritium and obtaining of highly pure tritiated water, and have the characteristics of high preparation efficiency, low cost and high safety.
Owner:MATERIAL INST OF CHINA ACADEMY OF ENG PHYSICS
Method and device for limiting the degassing of tritiated waste issued from the nuclear industry
InactiveUS20130178686A1Reduce in quantityReduce the probability of spreadingNuclear energy generationSolid waste disposalMolecular sieveHydrogen
A method and device for limiting the degassing of tritiated waste issued from the nuclear industry are provided. The method reduces an amount of generated tritiated hydrogen (T2 or HT) and / or tritiated water (HTO or T2O) including at least one piece of tritiated waste from the nuclear industry. The method includes placing the package in contact with a mixture including manganese dioxide (MnO2) combined with a component that includes silver; and placing the package in contact with a molecular sieve.
Owner:COMMISSARIAT A LENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
Experimental device for preparing carbon-14 liquid sample in radioactive graphite
The invention discloses an experimental device for preparing a carbon-14 liquid sample in radioactive graphite. The experimental device comprises a pressure-bearing steel cylinder, a top end cover, a sealing cover, two electrodes, an igniting wire, a sample crucible bracket, a charging-discharging valve and an adsorption device, wherein the adsorption device contains tritiated water vapor; when in use, the adsorption device is arranged in the pressure-bearing steel cylinder; an internal space of the pressure-bearing steel cylinder is partitioned into a first space and a second space; the adsorption device is provided with a plurality of through holes; the first space communicates with the second space only through the adsorption device.
Owner:TSINGHUA UNIV
Tritiated water electrolytic concentration device and method
InactiveCN106467975ASolve dead volume correction issueSimple structural designCellsWater/sewage treatmentHydrogenTritiated water
The invention provides a tritiated water electrolytic concentration device and method. The device comprises an electrolytic cell, a sample bottle, an oxygen exhaust device and a hydrogen exhaust device, wherein the electrolytic cell is used for electrolyzing tritiated water and comprises a water inlet, a hydrogen outlet and an oxygen outlet; the sample bottle comprises a sample inlet and a water outlet, the sample inlet is used for introducing tritiated water samples into the sample bottle, and the water outlet is used for guiding the tritiated water samples out and connected with the water inlet of the electrolytic cell; the oxygen exhaust device is connected to the oxygen outlet of the electrolytic cell and used for exhausting oxygen generated through electrolyzing to the environment; the hydrogen exhaust device is connected with the hydrogen outlet of the electrolytic cell and used for exhausting hydrogen generated through electrolyzing to the environment; and the hydrogen exhaust device comprises a mass flowmeter used for measuring the accumulative mass flow of the hydrogen generated through electrolyzing. According to the technical scheme, the structure design is simple, operation is convenient, the electrolytic efficiency is high, the volume concentration rate is computed accurately, safety is achieved, pollution is avoided, and safe, effective and stable electrolytic concentration of environmental low-level tritiated water is achieved.
Owner:NUCLEAR & RADIATION SAFETY CENT
Portable sampling device used for air tritiated water
InactiveCN106596203AEasy to measureFast samplingWithdrawing sample devicesInsulation layerWater vapor
The invention provides a portable sampling device used for air tritiated water. A semiconductor refrigeration sheet and a cooling fan inside of the sampling device are connected to a power supply through wires, the heating surface of the semiconductor refrigeration sheet is tightly close to the cooling fan, the refrigeration surface of the semiconductor refrigeration sheet is wrapped with a heat insulation layer housing, a temperature sensor and an accommodation container are placed in a heat insulation layer canvity body, an air inlet, an air outlet and a power air pump outlet are all connected to a hose, a flow display controller is connected to a power air pump through a signal line, and the power air pump is connected to the power supply. According to the sampling device, the power air pump is utilized to adjust inhalational water vapor flow containing tritium in the environment, and the semiconductor refrigeration sheet is utilized to fast condense the water vapor flow containing tritium and collect the condensed water vapor flow containing tritium into a container to form tritiated water. The sampling device can be applicable to fast sampling of the water vapor flow containing tritium near a respiratory zone of working staffs in a tritium related place, has the advantages of being small in size and strong in practicability, and can provide support for tritium radiation protection for tritium related working staffs.
Owner:INST OF NUCLEAR PHYSICS & CHEM CHINA ACADEMY OF
System for reducing concentration of gas-borne tritium in nuclear power plant building
InactiveCN108053908AReduce occupational exposureReduced airborne tritium concentrationRadioactive decontaminationNuclear plantOccupational exposure
The invention belongs to the technical field of radiation protection, and specifically relates to a system for reducing the concentration of gas-borne tritium in a nuclear power plant building. The system is used for removing tritiated water vapor in to-be-treated gas which is gas in the nuclear power plant building and in a ventilation system in the nuclear power plant building. The system comprises a tritiated water dehumidifying device and a tritiated water collecting device which are arranged in a device box (1), wherein the to-be-treated gas in the ventilation system enters the device box(1); the tritiated water vapor in the to-be-treated gas is converted into tritiated water through the tritiated water dehumidifying device; the tritiated water is collected through the tritiated water collecting device; and the to-be-treated gas with the tritiated water vapor removed is used as regenerated gas and discharged out of the device box (1). The system provided by the invention has fewactive components, is simple in maintenance, facilitates reducing of occupational exposure of workers, can reduce the content of the tritiated water vapor in the environment of the nuclear power plantbuilding, and reduces the concentration of the gas-borne tritium in the nuclear power plant building.
Owner:CHINA NUCLEAR POWER ENG CO LTD
Advanced tritium system and advanced permeation system for separation of tritium from radioactive wastes
ActiveUS10940437B2Specific isotope recoveryWater treatment parameter controlPtru catalystEngineering
Owner:VEOLIA NUCLEAR SOLUTIONS INC
Tritium protection system and method for helium-3 transient test
InactiveCN110491536AGuaranteed purityImprove diffusion abilityNuclear energy generationNuclear monitoringThree levelMulti method
The invention discloses a tritium protection system and method for a helium-3 transient test. The system is composed of a helium-3 gas loop, a glove box containing system, a glove box emergency systemand a tritium online monitoring system. The helium-3 gas loop, the glove box containing system and a sealing process chamber form a three-level containing barrier for tritium in helium-3 gas, and each containing system of the tritium online monitoring system performs multi-point sampling and multi-method online monitoring. According to the helium-3 gas loop, tritium gas and tritiated water are removed through the combination of a tritium remover and a molecular sieve dryer for the loop, and Al2O3 coating is performed on the surfaces of the tritium remover and the helium-3 gas screen structure, so that the permeation amount of high-temperature and high-pressure tritium is reduced. According to the glove box emergency system, accidents of relatively long-time tiny tritium leakage and relatively short-time massive tritium leakage of a helium-3 loop are respectively handled through glove box purification adsorption and air exhaust compression storage modes. The tritium protection system and method can be used for nuclear fuel power transient tests, online irradiation tritium production tests, tritium breeding agent in-reactor irradiation and the like.
Owner:NUCLEAR POWER INSTITUTE OF CHINA
Apparatus and method for separating tritated and heavy water from light water via a conical configuration
An system for separating tritiated water from common water, using gravity and the freezing point of tritiated water to cause tritiated water to freeze along the inside of a conically-shaped collection chamber. The common water and liquid tritiated water that pass out the bottom of the conically-shaped collection chamber are pumped back to the top of the conically-shaped collection chamber for repeated runs until sufficient tritiated water has frozen to the inside of the conically-shaped collection chamber. A water wheel is positioned to assist in powering the pump that drives water through repeated runs.
Owner:MUCHNIK BORIS J
Sampling method for tritiated water in air
InactiveCN106840766AEasy to sampleSimple samplingWithdrawing sample devicesPreparing sample for investigationInsulation layerWater vapor
The invention provides a sampling method for tritiated water in air. A system used by the sampling method comprises a cooling fan, a semiconductor refrigeration sheet, a heat insulation layer, a collection container, a movable cover plate, a hose I, a hose II, a hose III, a power air pump, a power supply, an AC plug, a temperature display, a temperature sensor and a flow display controller. The sampling method comprises the steps of adjusting an intake flow rate equivalent to short-term respiratory volume of a person through the power air pump; pumping tritiated water vapor in air by using a peltier effect of the semiconductor refrigeration sheet; quickly condensing the tritiated water vapor into tritiated water through a coil of the collection container; carrying out volume measurement and liquid scintillation counting on the collected tritiated water; and obtaining the inhalation dose of tritium in air near a respiratory zone of a worker of a tritium-related place according to a calculation formula. The sampling method is suitable for fast sampling of the tritiated water of the air near the worker of the tritium-related place, and is a practical and simple sampling method; and a support can be provided for radiation protection of the worker of the tritium-related place.
Owner:INST OF NUCLEAR PHYSICS & CHEM CHINA ACADEMY OF
Tritium water electrolysis concentration equipment and method
InactiveCN106467975BSolve dead volume correction issueSimple structural designCellsWater/sewage treatmentHydrogenBottle
Owner:NUCLEAR & RADIATION SAFETY CENT
System and method for preparing low-deuterium tritiated water
The invention discloses a system and a method for preparing low-deuterium tritiated water. The system comprises a hydrogen production device, an oxygen delivery device and a water generation device. A deep seawater extraction device is connected with a seawater purification device. Purified seawater is delivered to the hydrogen production device to serve as part of raw materials of the hydrogen production device. The hydrogen production device is provided with a membrane separation device. Protium in hydrogen is separated out by the membrane separation device. Deuterium and tritium in the hydrogen cannot be filtered out by the membrane separation device. The oxygen delivery device provides oxygen through preparation or only delivers prepared oxygen. The water generation device receives the hydrogen produced by the hydrogen production device and the oxygen delivered by the oxygen delivery device to obtain healthy water. The system and the method have the advantages that light water not containing radioactive elements of the deuterium and the tritium can be prepared, so that life quality of people can be improved and people's demand for health can be met; in addition, the system is portable and convenient for the people to carry.
Owner:SHANGHAI HYDROGEN MOBILE REFRMER INSTR
Multi-concentration tritiated water vapor generating device
ActiveCN114870411AImprove production efficiencyImprove efficiencyNuclear energy generationEvaporation apparatusDiaphragm pumpWater vapor
The invention discloses a multi-concentration tritiated water vapor generating device which comprises a bubbler containing standard tritiated water, a cold hydrazine, a temperature regulator and a thermometer, an air inlet pipe is installed at the input end of the bubbler, and an inlet valve, a diaphragm pump, a dryer, a filter, a flow control valve, a flow meter and a valve are sequentially installed on the air inlet pipe. An air outlet pipe is mounted at the output end of the bubbler, one end of the air outlet pipe extends into the upper layer in the bubbler and is communicated with air in the upper layer in the bubbler, and an outlet valve is mounted on the air outlet pipe. According to the invention, the temperature of standard tritiated water for bubbling can be changed through the temperature regulator and the cold hydrazine without disassembly, so that the isotope fractionation coefficient and the saturated water content are further changed, the generation of standard tritiated water with different concentrations is finally realized, the complexity of the tritiated water operation link and the field calibration process by personnel is greatly reduced, and the production efficiency is improved. And the exposure risk of tritium water to operators is greatly reduced, so that the radiation safety of field calibration workers is enhanced.
Owner:中国人民解放军火箭军工程大学 +1
Who we serve
- R&D Engineer
- R&D Manager
- IP Professional
Why Patsnap Eureka
- Industry Leading Data Capabilities
- Powerful AI technology
- Patent DNA Extraction
Social media
Patsnap Eureka Blog
Learn More Browse by: Latest US Patents, China's latest patents, Technical Efficacy Thesaurus, Application Domain, Technology Topic, Popular Technical Reports.
© 2024 PatSnap. All rights reserved.Legal|Privacy policy|Modern Slavery Act Transparency Statement|Sitemap|About US| Contact US: help@patsnap.com