26 results about "Tritiated water" patented technology

The invention discloses a tritiated waste ash purification method and system based on cooperation of multistage adsorption and low-temperature distillation. The method comprises the following steps: S1, sorting treatment; s2, acid leaching treatment; the waste ash to be treated is subjected to acid leaching treatment, and acid leaching slurry is obtained; s3, carrying out separation treatment; carrying out separation treatment on the acid leaching slurry to obtain acid leaching residues and leachate; s4, adsorption treatment; carrying out adsorption treatment on the leachate to obtain penetrating liquid; s5, catalytic treatment; performing catalytic treatment on the penetrating liquid to obtain tritiated water and catalytic treatment tail gas; and S6, carrying out adsorption treatment on the catalytic treatment tail gas. According to the tritiated waste ash purification method, multi-stage adsorption and low-temperature distillation cooperative treatment is adopted, and the tritiated waste ash purification efficiency is greatly improved. According to the tritiated waste ash purification system, pretreatment, adsorption-catalysis and rectification concentration unit independent packaging are achieved through modular design, and rapid disassembly and assembly and multi-line parallel treatment are supported.

The invention discloses a tritiated water measurement method, device, equipment, medium and product, and relates to the field of radiation detection, the method comprises the following steps: obtaining an actual nuclear pulse signal detected by a double-layer scintillator detector, and carrying out classification by using a trained convolutional neural network according to the actual nuclear pulse signal to obtain an actual energy deposition mode type; the actual energy deposition mode types include that the particles do not deposit energy in the scintillators, the particles only deposit energy in the second layer of scintillators, the particles only deposit energy in the first layer of scintillators and the particles have energy deposition in the two layers of scintillators, and the tritium beta rays are determined according to the actual energy deposition mode types. According to the invention, accurate measurement of tritium water can be realized.

The invention relates to a method for testing the tritium release rate of a tritium-containing waste package, and the method comprises the steps: guiding tritium-containing waste gas released by the tritium-containing waste package in an exhaust hood to be continuously input into an ionization chamber online monitoring system, and determining the initial tritium activity concentration; when the first threshold value is lower than the first threshold value, the tritium-containing waste gas flows into an initial bubbling sampler after passing through a refrigerating system to collect tritiated water, and target gas is obtained; enabling the target gas to circularly pass through the operation of the initial bubbling sampler, and replacing a new bubbling sampler every time a first preset time is reached; after a second preset time is reached, stopping the cyclic operation, and testing the target tritium activity concentration of liquid in the bubbling sampler which is replaced for multiple times and the current bubbling sampler by adopting a liquid scintillation counter; and calculating the tritium release rate based on the target tritium activity concentration. Target gas is discharged into the exhaust hood again, tritiated water absorption is carried out on tritium-containing waste gas multiple times, and the technical effects that tritiated water absorption is more complete due to multiple times of cyclic absorption, and the tritium release rate detection result is more accurate are achieved.

The present application relates to a kind of bubble method tritium sampler sampling efficiency determination method, gas generated by water vapor generator is passed into tritium sampler, sampling flow in gas path is controlled by flowmeter, after sampling, sampling efficiency is the ratio of the mass of tritium sampler and the mass of water vapor generator.The present application realizes using water vapor generator to generate water vapor as sampling gas source to replace non-radioactive method of tritium water vapor gas source, while using weighing method to measure and calculate bubble method tritium sampler, sampler sampling efficiency, effectively avoids the problem of tritium water vapor activity concentration traceability, avoids the risk of contamination of tritium sampler, sampler and tritiated water vapor leakage in the process of efficiency determination using tritiated water vapor gas source.The present application provides a convenient, fast, non-polluting, no need to operate radioactive source and safe determination method for bubble method tritium sampler, sampler sampling efficiency determination.

The invention provides a combined automatic treatment system and method for tritium and carbon-14 in gaseous effluent, and particularly relates to the technical field of nuclear facility gaseous effluent monitoring. The treatment system comprises a gas inlet unit, a catalytic oxidation unit, a tritium trapping unit, a carbon trapping unit and a circuit control unit, a gas inlet of the catalytic oxidation unit is communicated with the gas inlet unit, and the catalytic oxidation unit is used for converting tritium gas and organic tritium in gaseous effluent into tritiated water vapor and converting organic carbon into carbon dioxide; the tritium trapping unit is communicated with a gas outlet of the catalytic oxidation unit, and can be used for condensing tritiated water vapor into liquid water and automatically sampling and detecting; the carbon capture unit comprises a neutralizer and a carbon dioxide sensor, a NaOH solution for absorbing carbon dioxide is arranged in the neutralizer, and the carbon dioxide sensor detects the absorption efficiency of carbon dioxide in real time; and the circuit control unit controls the operation of each unit. According to the system, catalytic oxidation, tritium condensation and carbon absorption are integrated, and synchronous treatment and monitoring of tritium and carbon-14 can be achieved.

The application discloses a zero-escape cold set composite tritium enrichment system and method, which comprises a molecular sieve body and an air inlet pipe connected with the molecular sieve body; the molecular sieve body is further connected with a cold trap for condensing and collecting tritiated water in air; a circulating conveying pipeline is connected between the cold trap and the molecular sieve body, and a circulating pump for improving the recovery rate by circulating conveying air is installed on the circulating conveying pipeline; the cold trap comprises an outer shell, a cold plate installed in the outer shell, and coarse and fine zigzag mechanisms installed on both sides of the cold plate to improve the air contact area and multi-stage adsorption.

The present application relates to a kind of measurement device of tritium adsorption coefficient, including experimental cavity, with the adsorption cavity and absorption device being connected with experimental cavity, and with the exhaust cavity being connected with adsorption cavity, with tritium-containing solution temporary storage tank being connected with absorption device, monitoring instrument is arranged between the experimental cavity, adsorption cavity and exhaust cavity, valve is arranged between each connecting component.The present application indirectly calculates the adsorption coefficient of unit volume, unit surface area experimental cavity in the material to be measured under different temperature, tritium concentration conditions by weighing the weight change of silica gel and other adsorption materials in adsorption cavity.It has practical significance for studying the adsorption coefficient of material itself, the anti-tritium penetration effect of surface coating material.The experimental device can be widely used to measure the adsorption coefficient of tritiated water, organic tritium in material.

The invention discloses an air tritiated water sampling method and system for all climate, and relates to the field of air tritiated water sampling, and the method comprises the following steps: obtaining four environmental parameters of the temperature, the relative humidity, the atmospheric pressure and the air velocity of a sampling point in real time; inputting the environment parameters obtained in real time into a preset dynamic parameter generator, and outputting a group of optimal key sampling parameter combinations; dynamically adjusting a sampling pump and a temperature adjusting device according to the optimal key sampling parameter combination so as to execute sampling operation; the effective adsorption capacity of the adsorbent is continuously monitored in the whole sampling period, and early warning information of adsorbent replacement is provided for a user. According to the invention, the problems of condensation and icing, premature saturation or desorption of an adsorbent and the like in all weather can be effectively avoided, and the sampling efficiency and accuracy are remarkably improved; meanwhile, continuous and stable sampling is guaranteed through adsorbent residual capacity monitoring and failure early warning, and high-precision and intelligent air tritiated water sampling under any weather condition is achieved.

The invention discloses a water tritium removal system and method for a fusion reactor. The water tritium removal system comprises a water rectification subsystem, a combined electrolysis catalysis exchange subsystem and a low-temperature rectification subsystem, and the water rectification subsystem is sequentially connected with the combined electrolysis catalysis exchange subsystem and the low-temperature rectification subsystem; the water rectification subsystem is used for treating and concentrating low-concentration tritium-containing water; the combined electrolysis catalysis exchange subsystem is used for treating high-concentration tritium-containing water; and the low-temperature rectification subsystem is used for concentrating and recycling tritium in tritium-containing hydrogen generated by electrolysis. Aiming at tritium-containing water with different concentrations, efficient treatment of the tritium-containing water can be guaranteed, the operation energy consumption of the whole system can be reduced, and the problem of poor economical efficiency is solved.

The invention belongs to the technical field of environmental radiation monitoring, and particularly relates to a method for estimating the sampling amount and collection efficiency of tritiated water vapor in environmental air, and the method comprises the steps: setting constant sampling flow and recording interval time by an intelligent recorder after a sampling device arrives at a sampling site, and starting sampling by the sampling device; the intelligent recorder sequentially records corresponding temperature and humidity data according to the interval time; various data recorded on the intelligent recorder are obtained, and the real-time water vapor sampling amount of the sampling device is calculated in real time according to the various data; and the sampling efficiency of the sampling device is calculated according to various data recorded on the intelligent recorder and the real-time sampling amount. According to the method for estimating the sampling amount and the collection efficiency of the tritiated water vapor in the ambient air, the sampling amount and the collection efficiency of the sampling device can be calculated in real time, the accuracy is high, and automatic monitoring and efficiency evaluation in the sampling process are achieved.

Methods and systems directed to the separation of tritium from an aqueous stream are described. The separation method is a multistage method that includes a purification stage during which tritium of a tritium-contaminated aqueous stream is adsorbed onto a cooled and wet separation phase, a regeneration stage during which the adsorbed tritium is exchanged with hydrogen in a gaseous stream to regenerate the separation phase and provide a gaseous stream with a high tritium concentration, and a third stage during which the tritium of the gaseous stream is separated from the gaseous stream as a gaseous tritium product.

The invention belongs to the technical field of nuclear reactor waste gas treatment and radionuclide recovery, and particularly relates to a magnesium-nickel alloy for low-temperature efficient recovery of deuterized water and tritiated water in reactor waste gas and a preparation method and application of the magnesium-nickel alloy. The magnesium-nickel alloy is magnesium-nickel alloy particles, and the preparation method comprises the steps that after magnesium metal and magnesium-nickel intermediate alloy are mixed according to the design proportion, high-temperature melting is conducted, the liquid alloy is stirred till components are uniform, then pouring and natural cooling are conducted, and a magnesium-nickel alloy ingot is obtained; and then the magnesium-nickel alloy ingot is processed into magnesium-nickel alloy particles, and finally the magnesium-nickel alloy particles meeting the requirements are screened. In the magnesium-nickel alloy, the nickel element forms a micro-couple with a magnesium matrix to accelerate electrochemical corrosion and destroy the integrity mechanism of a magnesium surface oxidation film, the reaction activity of the magnesium-nickel alloy with deuterized water and tritiated water vapor is jointly improved, and deuterium and tritium isotopes in waste gas are efficiently and selectively adsorbed and fixed.

The invention provides a polymorphic gaseous tritium on-line measurement system and method, the system comprises a filtering mechanism, a first tritiated water measurement mechanism, an oxidation furnace, a cooler, a second tritiated water measurement mechanism and an air pump, the air inlet end of the filtering mechanism is communicated with an external gas conveying pipeline; the gas inlet end of the first tritiated water measuring mechanism is communicated with the gas outlet end of the filtering mechanism and is used for carrying out enrichment and activity concentration measurement on tritiated water in gas, and the gas inlet end of the oxidizing furnace is communicated with the gas outlet end of the first tritiated water measuring mechanism; the air inlet end of the cooler is communicated with the air outlet end of the oxidizing furnace; the gas inlet end of the second tritiated water measuring mechanism is communicated with the gas outlet end of the cooler, and the second tritiated water measuring mechanism is used for enriching the cooled gas and measuring the activity concentration of non-oxide tritium. And an effective technical support is provided for tritium radiation hazards and tritium leakage hidden dangers of nuclear personnel.

An embodiment of the present application discloses a tritium removal system and a tritium removal method. The tritium removal system includes a tritium removal unit, an input unit, a regeneration unit, an output unit, and a venting unit. In the process of using the tritium removal system provided by the embodiment of the present application, helium gas containing tritiated water can enter the tritium removal unit through the input unit. After the tritium removal unit dries and adsorbs the tritiated water in the helium gas through a drying tower, the helium gas is then discharged into the helium gas circuit through the output unit. The tritium removal unit of the tritium removal system provided by the embodiment of the present application includes a plurality of tritium removal components arranged in parallel. Through the setting of a first control valve and a second control valve, each drying tower can work independently, and the molecular sieve desiccant in the drying tower is heated and regenerated through the regeneration unit, which has the characteristics of high tritium removal efficiency, large gas processing capacity, and long continuous operation time.

The invention relates to the technical field of radioactive substance content measurement, and discloses a tritiated hydrogen sample preparation device for liquid flash measurement and a sample preparation and measurement method. During sample preparation, a gas supply module provides a to-be-measured tritiated hydrogen sample, hydrogen, air and water vapor, and the flow of each gas is adjusted through a corresponding mass flow meter and a control valve; the method comprises the following steps: taking tritiated hydrogen as a gas source, mixing the gas, performing catalytic oxidation on the mixed gas through a catalytic oxidation module, converting the tritiated hydrogen into a tritiated water sample, and collecting the converted tritiated water sample by a collection module for measuring the content of the tritiated hydrogen. In combination with the measurement of the low background liquid flash instrument, the measurement of the tritiated hydrogen with low activity content can be realized, and the measurement requirement of the tritiated hydrogen with wide measuring range can be met.

The present invention discloses a method, device and application for tritium separation and purification from tritium-containing wastewater. The method includes the following steps: The purified raw water enters the rectification unit for rectification separation. The qualified low-tritium product is obtained at the top of the last rectification column in the rectification unit, and pure tritiated water with a concentration of 99% or more is obtained at the bottom of the first rectification column in the rectification unit. The pure tritiated water and the non-condensable gases from each rectification column are deoxygenated, and then hydrogen isotope separation is carried out to obtain pure tritium gas and other gases. The other gases are oxidized and then sent back to the rectification unit for circulation. In the present invention, water rectification and adsorption separation are organically combined. While reducing the volume of tritium-containing wastewater, the tritium in the wastewater is concentrated and purified to obtain utilizable tritium resources; the operating conditions of the water rectification process are mild, with negative pressure operation and no risk of tritium leakage; the adsorption separation operation process is simple, easy to operate, safe and reliable; it can meet the disposal requirements of large-capacity tritium-containing wastewater and obtain high-purity tritium products.

The present application relates to the technical field of nuclear radiation detection, and particularly relates to a radon-tritium separation discrimination measurement device and method in a high-radon environment, which comprises a first measurement channel, a second measurement channel, a third measurement channel and a fourth measurement channel, and respectively measures a first current value I1, a second current value I2, a third current value I3 and a fourth current value I4, and respectively calculates the activity concentration C Rn of radon Rn, the activity concentration C HTO of tritiated water HTO and the activity concentration C HT of tritium gas HT according to the first current value I1, the second current value I2, the third current value I3 and the fourth current value I4. The present application focuses on the characteristics of indoor environment, considers the influence of indoor radon on tritium measurement, adopts a series-parallel differential mode, avoids the low detection limit influence caused by multi-channel measurement, is more suitable for low-concentration-level environment measurement, saves the need of purging gas, and simplifies the device structure.

The invention relates to a method: The fusion reaction thus makes it possible to produce tritium continuously Tritium is extracted from heavy water at the "Tritium Removal Facility" (TRF) in two stages: Catalytic extraction in the vapor phase, then cryogenic distillation Tritium is extremely rare in its natural state (approximately one atom of tritium for 1018 atoms It would require A 150 MW Type K15 pressurized water reactor Can be mounted with tritium up to 3200 MW therefore 15 kg of tritium fuel, The fusion reaction of deuterium and tritium is the nuclear fusion reaction which releases the More energy: 17 MeV Fusion does not emit CO2 With one kilo of deuterium and tritium, as much energy is generated as with 100 kg of uranium Or 6 million kilos of natural gas. A fusion reactor with a power of 1 GW Will require by example 50 kg of tritium per year.So it would consist of on-board storage With A tokamak is a machine capable of creating and confining a hot plasma at nearly 150 million degrees in a ring-shaped magnetic cage. It consists of creating an intense current (of the order of several Mega-Amps) inside the plasma, a current which will itself generate the additional magnetic field Separation of hydrogen isotopes between 20 and 25k Cryogenic distillation process of non-exchangeable TRITIUM fuel, the sample also undergoes combustion in order to release the tritium in the form of gas which will then be trapped to form tritiated water.

The application discloses an on-line measuring device and method for typical form tritium radiation dose rate in air, which comprises a gas-water separation unit, an ionization chamber measuring unit and a processing display unit, wherein the gas-water separation unit is used for separating tritiated water and tritiated hydrogen in the to-be-measured gas, sending the penetrated tritiated water and tritiated hydrogen to the ionization chamber measuring unit, and sending the measured to-be-measured gas flow rate M 测 and the purging gas flow rate M 吹 to the processing display unit; the ionization chamber measuring unit is used for measuring the tritium activity concentration in the input gas and sending the tritium activity concentration A to the processing display unit; and the processing display unit is used for calculating and displaying the tritium radiation dose rate value D in air. The application can directly measure and further calculate the tritium radiation dose rate value in air, so that the on-site real-time measurement of the tritium radiation dose rate is realized.

The application discloses a device and method for online monitoring of tritium concentration in liquid effluent of a nuclear facility. The device comprises a bypass monitoring pipeline, a tritiated water vapor generator connected to the bypass monitoring pipeline, and an output end of a gaseous tritium concentration measuring instrument communicated with a nuclear facility effluent discharge pipeline through an exhaust pipe. The method comprises the following steps: 1) collecting liquid effluent of the nuclear facility; 2) starting a gas pump to start bubbling; 3) measuring the temperature of the liquid in the bubbler; 4) obtaining the liquid tritiated water concentration in a first temperature value range; 5) obtaining the liquid tritiated water concentration in a second temperature value range; 6) obtaining the liquid tritiated water concentration in a next temperature value range; 7) obtaining the final liquid tritiated water concentration under N different temperature data; and 8) calculating the tritium concentration value in the liquid effluent of the nuclear facility. The application converts the monitoring of liquid tritium in the liquid effluent into the monitoring of gaseous tritium, and then obtains the liquid tritium concentration through back calculation, so that the real-time online monitoring target is achieved, and the monitoring is safe and accurate.

A spherical body 10 has magnesium as a principal component and the outer surface thereof is coated with a magnesium oxide coating film. An inertial nuclear fusion fuel 11 includes a combination of deuterium water and tritiated water, only deuterium water, a combination of light hydrogen water and boron, or a mixture thereof, and is filled in a fuel hole provided in advance in the vicinity of the center of the spherical body. In addition, as a result of an inertial nuclear fusion fuel pellet 1 according to the present invention being charged into carbon dioxide at a high temperature equal to or higher than a predetermined combustion temperature at which the magnesium and carbon dioxide are combusted, the spherical body is expanded, the magnesium oxide coating film is broken, the magnesium of the spherical body reacts with the carbon dioxide, shock wave heating is performed, and the nuclear fusion reaction of the inertial nuclear fusion fuel occurs.

The application discloses a kind of air tritiated water sampling method and system for all-weather, it is related to air tritiated water sampling field, the method comprises: four kinds of environmental parameters of temperature, relative humidity, atmospheric pressure and air flow rate of sampling point are acquired in real time;The environmental parameters acquired in real time are input to the preset dynamic parameter generator, and output a set of optimized key sampling parameter combination;According to the optimized key sampling parameter combination, dynamically adjust sampling pump, temperature adjusting device to execute sampling operation;In the whole sampling cycle, the effective adsorption capacity of adsorbent is continuously monitored, and the early warning information of adsorbent replacement is provided to the user.The problems such as condensation icing, adsorbent premature saturation or resolution under all-weather can be effectively avoided by the application, and the sampling efficiency and accuracy are significantly improved;At the same time, through adsorbent residual capacity monitoring and failure warning, the sampling is continuously stable, and high-precision, intelligent air tritiated water sampling under any weather condition is realized.

The invention provides a system and a method for removing radioactive tritium from inert gas. The system comprises: a filter unit for removing organic components and inorganic particles in the inert gas; the gas buffer tank is used for mixing oxygen and inert gas from the filtering unit; the oxygen supply unit is used for supplying oxygen into the gas buffer tank; the catalytic oxidation unit is used for converting element-state tritium contained in the inert gas into tritiated water; the catalytic washing unit is used for transferring radioactive tritium contained in the inert gas from the catalytic oxidation unit into liquid-phase water; the natural water supply unit is used for supplying natural water into the catalytic washing unit; and the condensing unit is used for condensing the tritium-removed inert gas flowing out of the catalytic washing unit. According to the system and the method, the residual quantity of tritium in the inert gas can be effectively reduced, so that the inert gas reaches the safe emission standard.

A method for treating to-be-treated water containing tritiated water and light water, the method includes providing a temperature difference in a heavy water gas hydrate substrate which may contain tritiated water, and to-be-treated water containing tritiated water and light water in the presence of a guest molecular gas based on a heavy water gas hydrate crystallization temperature zone and its vicinity under a pressure condition where heavy water gas hydrate or tritiated water gas hydrate can be crystallized.

1. The name of the design product: atmospheric tritiated water sampler. 2. The use of the design product: for radiation monitoring, collecting radioactive aerosols or iodine in the air. 3. The design points of the design product: in the combination of shape and pattern. 4. The picture or photo that best indicates the design points: refer to the drawings.

To achieve rapid containment, within the next 5 to 10 years, of the Fukushima Daiichi nuclear power plant, which suffered an explosion due to the earthquake and tsunami in 2011, by neutralizing the radiation contaminated water and solids.SOLUTION: Water stored in tanks containing filtered tritiated water is allowed to fall from the tanks to concentrate the tritiated water. β and α decay of radiation contaminated water is forced using ultrasonic impacts without going through a purification process.SELECTED DRAWING: Figure 5